From 642afb5adbbf061f6c103bdfa1f694bdfe0c81a3 Mon Sep 17 00:00:00 2001 From: Jonathan Shimwell Date: Mon, 5 Oct 2020 13:51:44 +0100 Subject: [PATCH 01/79] added git actions workflow file --- github/workflows/dockerhub-publish-dev.yml | 32 ++++++++++++++++++++++ 1 file changed, 32 insertions(+) create mode 100644 github/workflows/dockerhub-publish-dev.yml diff --git a/github/workflows/dockerhub-publish-dev.yml b/github/workflows/dockerhub-publish-dev.yml new file mode 100644 index 0000000000..f025e2ab2d --- /dev/null +++ b/github/workflows/dockerhub-publish-dev.yml @@ -0,0 +1,32 @@ +name: dockerhub-publish + +on: + push: + branches: develop + +jobs: + main: + runs-on: ubuntu-latest + steps: + - + name: Set up QEMU + uses: docker/setup-qemu-action@v1 + - + name: Set up Docker Buildx + uses: docker/setup-buildx-action@v1 + - + name: Login to DockerHub + uses: docker/login-action@v1 + with: + username: ${{ secrets.DOCKERHUB_USERNAME }} + password: ${{ secrets.DOCKERHUB_TOKEN }} + - + name: Build and push + id: docker_build + uses: docker/build-push-action@v2 + with: + push: true + tags: openmc/openmc:dev + - + name: Image digest + run: echo ${{ steps.docker_build.outputs.digest }} From 1c01fe751d61aa75e0eb7823e36cbe34b4d43d13 Mon Sep 17 00:00:00 2001 From: Jonathan Shimwell Date: Thu, 8 Oct 2020 17:08:24 +0100 Subject: [PATCH 02/79] added helpful dict with reaction names as keys --- openmc/data/reaction.py | 2 ++ openmc/deplete/helpers.py | 9 ++++----- 2 files changed, 6 insertions(+), 5 deletions(-) diff --git a/openmc/data/reaction.py b/openmc/data/reaction.py index 9360d05289..6da151e040 100644 --- a/openmc/data/reaction.py +++ b/openmc/data/reaction.py @@ -64,6 +64,8 @@ REACTION_NAME.update({i: '(n,3He{})'.format(i - 750) for i in range(750, 799)}) REACTION_NAME.update({i: '(n,a{})'.format(i - 800) for i in range(800, 849)}) REACTION_NAME.update({i: '(n,2n{})'.format(i - 875) for i in range(875, 891)}) +REACTION_NUMBER = dict(zip(REACTION_NAME.values(), REACTION_NAME.keys())) + FISSION_MTS = (18, 19, 20, 21, 38) diff --git a/openmc/deplete/helpers.py b/openmc/deplete/helpers.py index b275dc0a58..4ffcdb245a 100644 --- a/openmc/deplete/helpers.py +++ b/openmc/deplete/helpers.py @@ -11,7 +11,7 @@ from numpy import dot, zeros, newaxis, asarray from . import comm from openmc.checkvalue import check_type, check_greater_than -from openmc.data import JOULE_PER_EV, REACTION_NAME +from openmc.data import JOULE_PER_EV, REACTION_NUMBER from openmc.lib import ( Tally, MaterialFilter, EnergyFilter, EnergyFunctionFilter) import openmc.lib @@ -168,10 +168,9 @@ class FluxCollapseHelper(ReactionRateHelper): """ self._materials = materials - # Convert reactions to MT values (needed when collapsing) - mt_values = {v: k for k, v in REACTION_NAME.items()} - mt_values['fission'] = 18 - self._mts = [mt_values[x] for x in scores] + # adds an entry for fisson to the dictionary of reactions + REACTION_NUMBER['fission'] = 18 + self._mts = [REACTION_NUMBER[x] for x in scores] self._scores = scores # Create flux tally with material and energy filters From e71e09884d9a87d18725ac89c52ca752ade6da54 Mon Sep 17 00:00:00 2001 From: Jonathan Shimwell Date: Thu, 8 Oct 2020 17:28:52 +0100 Subject: [PATCH 03/79] allowing plot types to be reaction strings --- openmc/plotter.py | 6 ++++++ 1 file changed, 6 insertions(+) diff --git a/openmc/plotter.py b/openmc/plotter.py index dfa6a13ba1..28dfcdf885 100644 --- a/openmc/plotter.py +++ b/openmc/plotter.py @@ -404,6 +404,12 @@ def _calculate_cexs_nuclide(this, types, temperature=294., sab_name=None, ops.append((np.add,) * (len(tmp_mts) - 2) + (np.multiply,)) else: ops.append((np.add,) * (len(tmp_mts) - 1)) + if line in openmc.data.REACTION_NUMBER: + openmc.data.REACTION_NUMBER[line] + tmp_mts = nuc.get_reaction_components(line) + mts.append(tmp_mts) + ops.append((np.add,) * (len(tmp_mts) - 1)) + yields.append(False) else: # Not a built-in type, we have to parse it ourselves cv.check_type('MT in types', line, Integral) From 336b09b358d23d3654a55aa2e1fc7895f70fd4a3 Mon Sep 17 00:00:00 2001 From: Jonathan Shimwell Date: Thu, 8 Oct 2020 17:33:05 +0100 Subject: [PATCH 04/79] added to altered functions docstring --- openmc/plotter.py | 5 +++-- 1 file changed, 3 insertions(+), 2 deletions(-) diff --git a/openmc/plotter.py b/openmc/plotter.py index 28dfcdf885..0994094684 100644 --- a/openmc/plotter.py +++ b/openmc/plotter.py @@ -309,8 +309,9 @@ def _calculate_cexs_nuclide(this, types, temperature=294., sab_name=None, Nuclide object to source data from types : Iterable of str or Integral The type of cross sections to calculate; values can either be those - in openmc.PLOT_TYPES or integers which correspond to reaction - channel (MT) numbers. + in openmc.PLOT_TYPES or keys from openmc.data.REACTION_NUMBER which + correspond to a reaction description e.g '(n,2n)' or integers which + correspond to reaction channel (MT) numbers. temperature : float, optional Temperature in Kelvin to plot. If not specified, a default temperature of 294K will be plotted. Note that the nearest From acde663c904eee6b071351b5645ce748e7ac1f89 Mon Sep 17 00:00:00 2001 From: Jonathan Shimwell Date: Thu, 8 Oct 2020 18:23:07 +0100 Subject: [PATCH 05/79] changed if else layout --- openmc/plotter.py | 12 ++++++++---- 1 file changed, 8 insertions(+), 4 deletions(-) diff --git a/openmc/plotter.py b/openmc/plotter.py index 0994094684..ae4b87add3 100644 --- a/openmc/plotter.py +++ b/openmc/plotter.py @@ -405,13 +405,15 @@ def _calculate_cexs_nuclide(this, types, temperature=294., sab_name=None, ops.append((np.add,) * (len(tmp_mts) - 2) + (np.multiply,)) else: ops.append((np.add,) * (len(tmp_mts) - 1)) - if line in openmc.data.REACTION_NUMBER: - openmc.data.REACTION_NUMBER[line] - tmp_mts = nuc.get_reaction_components(line) + elif line in openmc.data.REACTION_NUMBER.keys(): + mt_number = openmc.data.REACTION_NUMBER[line] + cv.check_type('MT in types', mt_number, Integral) + cv.check_greater_than('MT in types', mt_number, 0) + tmp_mts = nuc.get_reaction_components(mt_number) mts.append(tmp_mts) ops.append((np.add,) * (len(tmp_mts) - 1)) yields.append(False) - else: + elif isinstance(line, int): # Not a built-in type, we have to parse it ourselves cv.check_type('MT in types', line, Integral) cv.check_greater_than('MT in types', line, 0) @@ -419,6 +421,8 @@ def _calculate_cexs_nuclide(this, types, temperature=294., sab_name=None, mts.append(tmp_mts) ops.append((np.add,) * (len(tmp_mts) - 1)) yields.append(False) + else: + raise TypeError("Invalid type", line) for i, mt_set in enumerate(mts): # Get the reaction xs data from the nuclide From 7668c7988182ce0397883f65164f33aa653a9e67 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 13 Oct 2020 12:45:35 -0500 Subject: [PATCH 06/79] Remove unused source sampling timer --- include/openmc/timer.h | 1 - src/state_point.cpp | 2 -- src/timer.cpp | 2 -- 3 files changed, 5 deletions(-) diff --git a/include/openmc/timer.h b/include/openmc/timer.h index a43a66bd42..3acf483d6b 100644 --- a/include/openmc/timer.h +++ b/include/openmc/timer.h @@ -21,7 +21,6 @@ extern Timer time_finalize; extern Timer time_inactive; extern Timer time_initialize; extern Timer time_read_xs; -extern Timer time_sample_source; extern Timer time_statepoint; extern Timer time_tallies; extern Timer time_total; diff --git a/src/state_point.cpp b/src/state_point.cpp index 14260051cc..e680c85313 100644 --- a/src/state_point.cpp +++ b/src/state_point.cpp @@ -293,8 +293,6 @@ openmc_statepoint_write(const char* filename, bool* write_source) write_dataset(runtime_group, "synchronizing fission bank", time_bank.elapsed()); write_dataset(runtime_group, "sampling source sites", time_bank_sample.elapsed()); write_dataset(runtime_group, "SEND-RECV source sites", time_bank_sendrecv.elapsed()); - } else { - write_dataset(runtime_group, "sampling source sites", time_sample_source.elapsed()); } write_dataset(runtime_group, "accumulating tallies", time_tallies.elapsed()); write_dataset(runtime_group, "total", time_total.elapsed()); diff --git a/src/timer.cpp b/src/timer.cpp index ff1d91b3a1..395fa0988f 100644 --- a/src/timer.cpp +++ b/src/timer.cpp @@ -16,7 +16,6 @@ Timer time_finalize; Timer time_inactive; Timer time_initialize; Timer time_read_xs; -Timer time_sample_source; Timer time_statepoint; Timer time_tallies; Timer time_total; @@ -76,7 +75,6 @@ void reset_timers() simulation::time_inactive.reset(); simulation::time_initialize.reset(); simulation::time_read_xs.reset(); - simulation::time_sample_source.reset(); simulation::time_statepoint.reset(); simulation::time_tallies.reset(); simulation::time_total.reset(); From 7228bba307a8a48810019f07270622d314de8fdc Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Wed, 14 Oct 2020 07:57:52 -0500 Subject: [PATCH 07/79] Use nbsphinx for rendering Jupyter notebooks in documentation --- docs/requirements-rtd.txt | 1 + docs/source/conf.py | 26 ++-- docs/source/examples/cad-geom.rst | 13 -- docs/source/examples/candu.rst | 13 -- docs/source/examples/expansion-filters.rst | 13 -- docs/source/examples/hexagonal.rst | 13 -- docs/source/examples/index.rst | 18 +-- docs/source/examples/mdgxs-part-i.rst | 13 -- docs/source/examples/mdgxs-part-ii.rst | 13 -- docs/source/examples/mg-mode-part-i.rst | 13 -- docs/source/examples/mg-mode-part-ii.rst | 13 -- docs/source/examples/mg-mode-part-iii.rst | 13 -- docs/source/examples/mgxs-part-i.rst | 13 -- docs/source/examples/mgxs-part-ii.rst | 13 -- docs/source/examples/mgxs-part-iii.rst | 13 -- .../nuclear-data-resonance-covariance.rst | 13 -- docs/source/examples/nuclear-data.rst | 13 -- docs/source/examples/pandas-dataframes.rst | 13 -- docs/source/examples/pincell-depletion.rst | 14 --- docs/source/examples/pincell.rst | 13 -- docs/source/examples/post-processing.rst | 13 -- docs/source/examples/search.rst | 13 -- docs/source/examples/tally-arithmetic.rst | 11 -- docs/source/examples/triso.rst | 13 -- .../examples/unstructured-mesh-part-i.rst | 13 -- .../examples/unstructured-mesh-part-ii.rst | 13 -- docs/sphinxext/LICENSE | 68 ---------- docs/sphinxext/notebook_sphinxext.py | 117 ------------------ examples/jupyter/cad-based-geometry.ipynb | 10 +- examples/jupyter/candu.ipynb | 3 +- examples/jupyter/expansion-filters.ipynb | 3 +- examples/jupyter/hexagonal-lattice.ipynb | 3 +- examples/jupyter/mdgxs-part-i.ipynb | 3 +- examples/jupyter/mdgxs-part-ii.ipynb | 5 +- examples/jupyter/mg-mode-part-i.ipynb | 9 +- examples/jupyter/mg-mode-part-ii.ipynb | 21 ++-- examples/jupyter/mg-mode-part-iii.ipynb | 19 +-- examples/jupyter/mgxs-part-i.ipynb | 3 +- examples/jupyter/mgxs-part-ii.ipynb | 3 +- examples/jupyter/mgxs-part-iii.ipynb | 3 +- .../nuclear-data-resonance-covariance.ipynb | 3 +- examples/jupyter/nuclear-data.ipynb | 3 +- examples/jupyter/pandas-dataframes.ipynb | 3 +- examples/jupyter/pincell.ipynb | 3 +- examples/jupyter/pincell_depletion.ipynb | 15 +-- examples/jupyter/post-processing.ipynb | 3 +- examples/jupyter/search.ipynb | 9 +- examples/jupyter/tally-arithmetic.ipynb | 3 +- examples/jupyter/triso.ipynb | 3 +- .../jupyter/unstructured-mesh-part-i.ipynb | 4 +- .../jupyter/unstructured-mesh-part-ii.ipynb | 4 +- setup.py | 3 +- 52 files changed, 101 insertions(+), 568 deletions(-) delete mode 100644 docs/source/examples/cad-geom.rst delete mode 100644 docs/source/examples/candu.rst delete mode 100644 docs/source/examples/expansion-filters.rst delete mode 100644 docs/source/examples/hexagonal.rst delete mode 100644 docs/source/examples/mdgxs-part-i.rst delete mode 100644 docs/source/examples/mdgxs-part-ii.rst delete mode 100644 docs/source/examples/mg-mode-part-i.rst delete mode 100644 docs/source/examples/mg-mode-part-ii.rst delete mode 100644 docs/source/examples/mg-mode-part-iii.rst delete mode 100644 docs/source/examples/mgxs-part-i.rst delete mode 100644 docs/source/examples/mgxs-part-ii.rst delete mode 100644 docs/source/examples/mgxs-part-iii.rst delete mode 100644 docs/source/examples/nuclear-data-resonance-covariance.rst delete mode 100644 docs/source/examples/nuclear-data.rst delete mode 100644 docs/source/examples/pandas-dataframes.rst delete mode 100644 docs/source/examples/pincell-depletion.rst delete mode 100644 docs/source/examples/pincell.rst delete mode 100644 docs/source/examples/post-processing.rst delete mode 100644 docs/source/examples/search.rst delete mode 100644 docs/source/examples/tally-arithmetic.rst delete mode 100644 docs/source/examples/triso.rst delete mode 100644 docs/source/examples/unstructured-mesh-part-i.rst delete mode 100644 docs/source/examples/unstructured-mesh-part-ii.rst delete mode 100644 docs/sphinxext/LICENSE delete mode 100644 docs/sphinxext/notebook_sphinxext.py diff --git a/docs/requirements-rtd.txt b/docs/requirements-rtd.txt index 7801c670f8..776bbc24d6 100644 --- a/docs/requirements-rtd.txt +++ b/docs/requirements-rtd.txt @@ -2,3 +2,4 @@ sphinx-numfig jupyter sphinxcontrib-katex sphinxcontrib-svg2pdfconverter +nbsphinx diff --git a/docs/source/conf.py b/docs/source/conf.py index 2410a887db..5ea2ec8ae9 100644 --- a/docs/source/conf.py +++ b/docs/source/conf.py @@ -20,13 +20,12 @@ on_rtd = os.environ.get('READTHEDOCS', None) == 'True' # ImportErrors when building documentation from unittest.mock import MagicMock - MOCK_MODULES = [ 'numpy', 'numpy.polynomial', 'numpy.polynomial.polynomial', 'numpy.ctypeslib', 'scipy', 'scipy.sparse', 'scipy.sparse.linalg', - 'scipy.interpolate', 'scipy.integrate', 'scipy.optimize', 'scipy.special', - 'scipy.stats', 'scipy.spatial', 'h5py', 'pandas', 'uncertainties', - 'matplotlib', 'matplotlib.pyplot', 'openmoc', + 'scipy.interpolate', 'scipy.integrate', 'scipy.optimize', 'scipy.signal', + 'scipy.special', 'scipy.stats', 'scipy.spatial', 'h5py', 'pandas', + 'uncertainties', 'matplotlib', 'matplotlib.pyplot', 'openmoc', 'openmc.data.reconstruct', 'openmc.checkvalue' ] sys.modules.update((mod_name, MagicMock()) for mod_name in MOCK_MODULES) @@ -39,7 +38,6 @@ np.polynomial.Polynomial = MagicMock # If extensions (or modules to document with autodoc) are in another directory, # add these directories to sys.path here. If the directory is relative to the # documentation root, use os.path.abspath to make it absolute, like shown here. -sys.path.insert(0, os.path.abspath('../sphinxext')) sys.path.insert(0, os.path.abspath('../..')) @@ -47,14 +45,16 @@ sys.path.insert(0, os.path.abspath('../..')) # Add any Sphinx extension module names here, as strings. They can be extensions # coming with Sphinx (named 'sphinx.ext.*') or your custom ones. -extensions = ['sphinx.ext.autodoc', - 'sphinx.ext.napoleon', - 'sphinx.ext.autosummary', - 'sphinx.ext.intersphinx', - 'sphinx.ext.viewcode', - 'sphinxcontrib.katex', - 'sphinx_numfig', - 'notebook_sphinxext'] +extensions = [ + 'sphinx.ext.autodoc', + 'sphinx.ext.napoleon', + 'sphinx.ext.autosummary', + 'sphinx.ext.intersphinx', + 'sphinx.ext.viewcode', + 'sphinxcontrib.katex', + 'sphinx_numfig', + 'nbsphinx' +] if not on_rtd: extensions.append('sphinxcontrib.rsvgconverter') diff --git a/docs/source/examples/cad-geom.rst b/docs/source/examples/cad-geom.rst deleted file mode 100644 index c5251c7ca1..0000000000 --- a/docs/source/examples/cad-geom.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_cad-geom: - -========================== -Using CAD-Based Geometries -========================== - -.. only:: html - - .. notebook:: ../../../examples/jupyter/cad-based-geometry.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/candu.rst b/docs/source/examples/candu.rst deleted file mode 100644 index 463a3c76e6..0000000000 --- a/docs/source/examples/candu.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_candu: - -======================= -Modeling a CANDU Bundle -======================= - -.. only:: html - - .. notebook:: ../../../examples/jupyter/candu.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/expansion-filters.rst b/docs/source/examples/expansion-filters.rst deleted file mode 100644 index f06d2bde6b..0000000000 --- a/docs/source/examples/expansion-filters.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_expansion: - -===================== -Functional Expansions -===================== - -.. only:: html - - .. notebook:: ../../../examples/jupyter/expansion-filters.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/hexagonal.rst b/docs/source/examples/hexagonal.rst deleted file mode 100644 index 8955fdb3fe..0000000000 --- a/docs/source/examples/hexagonal.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_hexagonal: - -=========================== -Modeling Hexagonal Lattices -=========================== - -.. only:: html - - .. notebook:: ../../../examples/jupyter/hexagonal-lattice.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/index.rst b/docs/source/examples/index.rst index 14565e64af..304137bcbc 100644 --- a/docs/source/examples/index.rst +++ b/docs/source/examples/index.rst @@ -23,7 +23,7 @@ General Usage search nuclear-data nuclear-data-resonance-covariance - pincell-depletion + pincell_depletion -------- Geometry @@ -32,14 +32,14 @@ Geometry .. toctree:: :maxdepth: 1 - hexagonal + hexagonal-lattice triso candu - cad-geom + cad-based-geometry ------------------------------------- -Multi-Group Cross Section Generation ------------------------------------- +----------------------------------- +Multigroup Cross Section Generation +----------------------------------- .. toctree:: :maxdepth: 1 @@ -50,9 +50,9 @@ Multi-Group Cross Section Generation mdgxs-part-i mdgxs-part-ii ----------------- -Multi-Group Mode ----------------- +--------------- +Multigroup Mode +--------------- .. toctree:: :maxdepth: 1 diff --git a/docs/source/examples/mdgxs-part-i.rst b/docs/source/examples/mdgxs-part-i.rst deleted file mode 100644 index 2899f126bd..0000000000 --- a/docs/source/examples/mdgxs-part-i.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_mdgxs_part_i: - -=================================================================== -Multi-Group (Delayed) Cross Section Generation Part I: Introduction -=================================================================== - -.. only:: html - - .. notebook:: ../../../examples/jupyter/mdgxs-part-i.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/mdgxs-part-ii.rst b/docs/source/examples/mdgxs-part-ii.rst deleted file mode 100644 index c5d52df629..0000000000 --- a/docs/source/examples/mdgxs-part-ii.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_mdgxs_part_ii: - -========================================================================= -Multi-Group (Delayed) Cross Section Generation Part II: Advanced Features -========================================================================= - -.. only:: html - - .. notebook:: ../../../examples/jupyter/mdgxs-part-ii.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/mg-mode-part-i.rst b/docs/source/examples/mg-mode-part-i.rst deleted file mode 100644 index e54c21c2fd..0000000000 --- a/docs/source/examples/mg-mode-part-i.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_mg_mode_part_i: - -===================================== -Multi-Group Mode Part I: Introduction -===================================== - -.. only:: html - - .. notebook:: ../../../examples/jupyter/mg-mode-part-i.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/mg-mode-part-ii.rst b/docs/source/examples/mg-mode-part-ii.rst deleted file mode 100644 index 9b4e574ae3..0000000000 --- a/docs/source/examples/mg-mode-part-ii.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_mg_mode_part_ii: - -============================================================= -Multi-Group Mode Part II: MGXS Library Generation With OpenMC -============================================================= - -.. only:: html - - .. notebook:: ../../../examples/jupyter/mg-mode-part-ii.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/mg-mode-part-iii.rst b/docs/source/examples/mg-mode-part-iii.rst deleted file mode 100644 index 86657c9675..0000000000 --- a/docs/source/examples/mg-mode-part-iii.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_mg_mode_part_iii: - -==================================================== -Multi-Group Mode Part III: Advanced Feature Showcase -==================================================== - -.. only:: html - - .. notebook:: ../../../examples/jupyter/mg-mode-part-iii.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/mgxs-part-i.rst b/docs/source/examples/mgxs-part-i.rst deleted file mode 100644 index d956e72616..0000000000 --- a/docs/source/examples/mgxs-part-i.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_mgxs_part_i: - -========================= -MGXS Part I: Introduction -========================= - -.. only:: html - - .. notebook:: ../../../examples/jupyter/mgxs-part-i.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/mgxs-part-ii.rst b/docs/source/examples/mgxs-part-ii.rst deleted file mode 100644 index 64efc57525..0000000000 --- a/docs/source/examples/mgxs-part-ii.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_mgxs_part_ii: - -=============================== -MGXS Part II: Advanced Features -=============================== - -.. only:: html - - .. notebook:: ../../../examples/jupyter/mgxs-part-ii.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/mgxs-part-iii.rst b/docs/source/examples/mgxs-part-iii.rst deleted file mode 100644 index 12f3265291..0000000000 --- a/docs/source/examples/mgxs-part-iii.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_mgxs_part_iii: - -======================== -MGXS Part III: Libraries -======================== - -.. only:: html - - .. notebook:: ../../../examples/jupyter/mgxs-part-iii.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/nuclear-data-resonance-covariance.rst b/docs/source/examples/nuclear-data-resonance-covariance.rst deleted file mode 100644 index 4b505c9a58..0000000000 --- a/docs/source/examples/nuclear-data-resonance-covariance.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_nuclear_data_resonance_covariance: - -================================== -Nuclear Data: Resonance Covariance -================================== - -.. only:: html - - .. notebook:: ../../../examples/jupyter/nuclear-data-resonance-covariance.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/nuclear-data.rst b/docs/source/examples/nuclear-data.rst deleted file mode 100644 index 15dfbde180..0000000000 --- a/docs/source/examples/nuclear-data.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_nuclear_data: - -============ -Nuclear Data -============ - -.. only:: html - - .. notebook:: ../../../examples/jupyter/nuclear-data.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/pandas-dataframes.rst b/docs/source/examples/pandas-dataframes.rst deleted file mode 100644 index 701f1630c1..0000000000 --- a/docs/source/examples/pandas-dataframes.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _examples_pandas: - -================= -Pandas Dataframes -================= - -.. only:: html - - .. notebook:: ../../../examples/jupyter/pandas-dataframes.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/pincell-depletion.rst b/docs/source/examples/pincell-depletion.rst deleted file mode 100644 index 348f3c6b95..0000000000 --- a/docs/source/examples/pincell-depletion.rst +++ /dev/null @@ -1,14 +0,0 @@ -.. _notebook_depletion: - -================= -Pincell Depletion -================= - - -.. only:: html - - .. notebook:: ../../../examples/jupyter/pincell_depletion.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/pincell.rst b/docs/source/examples/pincell.rst deleted file mode 100644 index 0f149107c1..0000000000 --- a/docs/source/examples/pincell.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_pincell: - -=================== -Modeling a Pin-Cell -=================== - -.. only:: html - - .. notebook:: ../../../examples/jupyter/pincell.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/post-processing.rst b/docs/source/examples/post-processing.rst deleted file mode 100644 index 09c4454e77..0000000000 --- a/docs/source/examples/post-processing.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_post_processing: - -=============== -Post Processing -=============== - -.. only:: html - - .. notebook:: ../../../examples/jupyter/post-processing.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/search.rst b/docs/source/examples/search.rst deleted file mode 100644 index 1d56ff53ae..0000000000 --- a/docs/source/examples/search.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_search: - -================== -Criticality Search -================== - -.. only:: html - - .. notebook:: ../../../examples/jupyter/search.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/tally-arithmetic.rst b/docs/source/examples/tally-arithmetic.rst deleted file mode 100644 index 7e653e8ff8..0000000000 --- a/docs/source/examples/tally-arithmetic.rst +++ /dev/null @@ -1,11 +0,0 @@ -================ -Tally Arithmetic -================ - -.. only:: html - - .. notebook:: ../../../examples/jupyter/tally-arithmetic.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/triso.rst b/docs/source/examples/triso.rst deleted file mode 100644 index 98f2f16439..0000000000 --- a/docs/source/examples/triso.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_triso: - -======================== -Modeling TRISO Particles -======================== - -.. only:: html - - .. notebook:: ../../../examples/jupyter/triso.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/unstructured-mesh-part-i.rst b/docs/source/examples/unstructured-mesh-part-i.rst deleted file mode 100644 index ed2c9c2fd3..0000000000 --- a/docs/source/examples/unstructured-mesh-part-i.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_unstructured_mesh_part_i: - -=============================== -Unstructured Mesh: Introduction -=============================== - -.. only:: html - - .. notebook:: ../../../examples/jupyter/unstructured-mesh-part-i.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/examples/unstructured-mesh-part-ii.rst b/docs/source/examples/unstructured-mesh-part-ii.rst deleted file mode 100644 index c30be88590..0000000000 --- a/docs/source/examples/unstructured-mesh-part-ii.rst +++ /dev/null @@ -1,13 +0,0 @@ -.. _notebook_unstructured_mesh_part_ii: - -=================================================================================== -Unstructured Mesh: Unstructured Mesh Tallies with CAD and Point Cloud Visualization -=================================================================================== - -.. only:: html - - .. notebook:: ../../../examples/jupyter/unstructured-mesh-part-ii.ipynb - -.. only:: latex - - IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/sphinxext/LICENSE b/docs/sphinxext/LICENSE deleted file mode 100644 index 2d508d2be9..0000000000 --- a/docs/sphinxext/LICENSE +++ /dev/null @@ -1,68 +0,0 @@ -The file notebook_sphinxext.py was derived from code in PyNE and yt. - -PyNE has the following license: - -------------------------------------------------------------------------------- -Copyright 2011-2015, the PyNE Development Team. All rights reserved. - -Redistribution and use in source and binary forms, with or without modification, are -permitted provided that the following conditions are met: - - 1. Redistributions of source code must retain the above copyright notice, this list of - conditions and the following disclaimer. - - 2. Redistributions in binary form must reproduce the above copyright notice, this list - of conditions and the following disclaimer in the documentation and/or other materials - provided with the distribution. - -THIS SOFTWARE IS PROVIDED BY THE PYNE DEVELOPMENT TEAM ``AS IS'' AND ANY EXPRESS OR IMPLIED -WARRANTIES, INCLUDING, BUT NOT LIMITED TO, THE IMPLIED WARRANTIES OF MERCHANTABILITY AND -FITNESS FOR A PARTICULAR PURPOSE ARE DISCLAIMED. IN NO EVENT SHALL OR -CONTRIBUTORS BE LIABLE FOR ANY DIRECT, INDIRECT, INCIDENTAL, SPECIAL, EXEMPLARY, OR -CONSEQUENTIAL DAMAGES (INCLUDING, BUT NOT LIMITED TO, PROCUREMENT OF SUBSTITUTE GOODS OR -SERVICES; LOSS OF USE, DATA, OR PROFITS; OR BUSINESS INTERRUPTION) HOWEVER CAUSED AND ON -ANY THEORY OF LIABILITY, WHETHER IN CONTRACT, STRICT LIABILITY, OR TORT (INCLUDING -NEGLIGENCE OR OTHERWISE) ARISING IN ANY WAY OUT OF THE USE OF THIS SOFTWARE, EVEN IF -ADVISED OF THE POSSIBILITY OF SUCH DAMAGE. - -The views and conclusions contained in the software and documentation are those of the -authors and should not be interpreted as representing official policies, either expressed -or implied, of the stakeholders of the PyNE project or the employers of PyNE developers. -------------------------------------------------------------------------------- - -yt has the following license: - -------------------------------------------------------------------------------- -yt is licensed under the terms of the Modified BSD License (also known as New -or Revised BSD), as follows: - -Copyright (c) 2013-, yt Development Team -Copyright (c) 2006-2013, Matthew Turk - -All rights reserved. - -Redistribution and use in source and binary forms, with or without -modification, are permitted provided that the following conditions are met: - -Redistributions of source code must retain the above copyright notice, this -list of conditions and the following disclaimer. - -Redistributions in binary form must reproduce the above copyright notice, this -list of conditions and the following disclaimer in the documentation and/or -other materials provided with the distribution. - -Neither the name of the yt Development Team nor the names of its -contributors may be used to endorse or promote products derived from this -software without specific prior written permission. - -THIS SOFTWARE IS PROVIDED BY THE COPYRIGHT HOLDERS AND CONTRIBUTORS "AS IS" AND -ANY EXPRESS OR IMPLIED WARRANTIES, INCLUDING, BUT NOT LIMITED TO, THE IMPLIED -WARRANTIES OF MERCHANTABILITY AND FITNESS FOR A PARTICULAR PURPOSE ARE -DISCLAIMED. IN NO EVENT SHALL THE COPYRIGHT OWNER OR CONTRIBUTORS BE LIABLE -FOR ANY DIRECT, INDIRECT, INCIDENTAL, SPECIAL, EXEMPLARY, OR CONSEQUENTIAL -DAMAGES (INCLUDING, BUT NOT LIMITED TO, PROCUREMENT OF SUBSTITUTE GOODS OR -SERVICES; LOSS OF USE, DATA, OR PROFITS; OR BUSINESS INTERRUPTION) HOWEVER -CAUSED AND ON ANY THEORY OF LIABILITY, WHETHER IN CONTRACT, STRICT LIABILITY, -OR TORT (INCLUDING NEGLIGENCE OR OTHERWISE) ARISING IN ANY WAY OUT OF THE USE -OF THIS SOFTWARE, EVEN IF ADVISED OF THE POSSIBILITY OF SUCH DAMAGE. -------------------------------------------------------------------------------- diff --git a/docs/sphinxext/notebook_sphinxext.py b/docs/sphinxext/notebook_sphinxext.py deleted file mode 100644 index eab93cc8a5..0000000000 --- a/docs/sphinxext/notebook_sphinxext.py +++ /dev/null @@ -1,117 +0,0 @@ -import sys -import os.path -import re -import time -from docutils import io, nodes, statemachine, utils -try: - from docutils.utils.error_reporting import ErrorString # the new way -except ImportError: - from docutils.error_reporting import ErrorString # the old way -from docutils.parsers.rst import Directive, convert_directive_function -from docutils.parsers.rst import directives, roles, states -from docutils.parsers.rst.roles import set_classes -from docutils.transforms import misc - -from nbconvert import html - - -class Notebook(Directive): - """Use nbconvert to insert a notebook into the environment. - This is based on the Raw directive in docutils - """ - required_arguments = 1 - optional_arguments = 0 - final_argument_whitespace = True - option_spec = {} - has_content = False - - def run(self): - # check if raw html is supported - if not self.state.document.settings.raw_enabled: - raise self.warning('"%s" directive disabled.' % self.name) - - # set up encoding - attributes = {'format': 'html'} - encoding = self.options.get( - 'encoding', self.state.document.settings.input_encoding) - e_handler = self.state.document.settings.input_encoding_error_handler - - # get path to notebook - source_dir = os.path.dirname( - os.path.abspath(self.state.document.current_source)) - nb_path = os.path.normpath(os.path.join(source_dir, - self.arguments[0])) - nb_path = utils.relative_path(None, nb_path) - - # convert notebook to html - exporter = html.HTMLExporter(template_file='full') - output, resources = exporter.from_filename(nb_path) - header = output.split('', 1)[1].split('',1)[0] - body = output.split('', 1)[1].split('',1)[0] - - # add HTML5 scoped attribute to header style tags - header = header.replace(''] - lines.append(header) - lines.append(body) - lines.append('') - text = '\n'.join(lines) - - # add dependency - self.state.document.settings.record_dependencies.add(nb_path) - attributes['source'] = nb_path - - # create notebook node - nb_node = notebook('', text, **attributes) - (nb_node.source, nb_node.line) = \ - self.state_machine.get_source_and_line(self.lineno) - - return [nb_node] - - -class notebook(nodes.raw): - pass - - -def visit_notebook_node(self, node): - self.visit_raw(node) - - -def depart_notebook_node(self, node): - self.depart_raw(node) - - -def setup(app): - app.add_node(notebook, - html=(visit_notebook_node, depart_notebook_node)) - - app.add_directive('notebook', Notebook) diff --git a/examples/jupyter/cad-based-geometry.ipynb b/examples/jupyter/cad-based-geometry.ipynb index b13c010cb1..5f84ae5e5c 100644 --- a/examples/jupyter/cad-based-geometry.ipynb +++ b/examples/jupyter/cad-based-geometry.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Using CAD-Based Geometries\n", "In this notebook we'll be exploring how to use CAD-based geometries in OpenMC via the [DagMC](https://svalinn.github.io/DAGMC/index.html) toolkit. The models we'll be using in this notebook have already been created using [Trelis](https://www.csimsoft.com/trelis) and faceted into a surface mesh represented as `.h5m` files in the [Mesh Oriented DatABase](https://press3.mcs.anl.gov/sigma/moab-library/) format. We'll be retrieving these files using the function below.\n", "\n" ] @@ -40,13 +41,6 @@ "This notebook is intended to demonstrate how DagMC problems are run in OpenMC. For more information on how DagMC models are created, please refer to the [DagMC User's Guide](https://svalinn.github.io/DAGMC/usersguide/index.html).\n" ] }, - { - "cell_type": "markdown", - "metadata": {}, - "source": [ - "# CAD-Based Geometry in OpenMC using [DagMC](https://svalinn.github.io/DAGMC/)" - ] - }, { "cell_type": "code", "execution_count": 2, @@ -756,7 +750,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.6.6" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/candu.ipynb b/examples/jupyter/candu.ipynb index b078d8ac62..eaf1e36d21 100644 --- a/examples/jupyter/candu.ipynb +++ b/examples/jupyter/candu.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Modeling a CANDU Bundle\n", "In this example, we will create a typical CANDU bundle with rings of fuel pins. At present, OpenMC does not have a specialized lattice for this type of fuel arrangement, so we must resort to manual creation of the array of fuel pins." ] }, @@ -1107,7 +1108,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.8.5" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/expansion-filters.ipynb b/examples/jupyter/expansion-filters.ipynb index 0975fca1b6..3b0413a058 100644 --- a/examples/jupyter/expansion-filters.ipynb +++ b/examples/jupyter/expansion-filters.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Functional Expansions\n", "OpenMC's general tally system accommodates a wide range of tally *filters*. While most filters are meant to identify regions of phase space that contribute to a tally, there are a special set of functional expansion filters that will multiply the tally by a set of orthogonal functions, e.g. Legendre polynomials, so that continuous functions of space or angle can be reconstructed from the tallied moments.\n", "\n", "In this example, we will determine the spatial dependence of the flux along the $z$ axis by making a Legendre polynomial expansion. Let us represent the flux along the z axis, $\\phi(z)$, by the function\n", @@ -1539,7 +1540,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.7.4" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/hexagonal-lattice.ipynb b/examples/jupyter/hexagonal-lattice.ipynb index f47b3bc603..07c3ab8344 100644 --- a/examples/jupyter/hexagonal-lattice.ipynb +++ b/examples/jupyter/hexagonal-lattice.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Modeling Hexagonal Lattices\n", "In this example, we will create a hexagonal lattice and show how the orientation can be changed via the cell rotation property. Let's first just set up some materials and universes that we will use to fill the lattice." ] }, @@ -402,7 +403,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.8.5" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/mdgxs-part-i.ipynb b/examples/jupyter/mdgxs-part-i.ipynb index 239b0f2df6..cda79d30a3 100644 --- a/examples/jupyter/mdgxs-part-i.ipynb +++ b/examples/jupyter/mdgxs-part-i.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Multigroup (Delayed) Cross Section Generation Part I: Introduction\n", "This IPython Notebook introduces the use of the `openmc.mgxs` module to calculate multi-energy-group and multi-delayed-group cross sections for an infinite homogeneous medium. In particular, this Notebook introduces the the following features:\n", "\n", "* Creation of multi-delayed-group cross sections for an **infinite homogeneous medium**\n", @@ -1486,7 +1487,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.7.0" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/mdgxs-part-ii.ipynb b/examples/jupyter/mdgxs-part-ii.ipynb index 77b5b55253..bb95384566 100644 --- a/examples/jupyter/mdgxs-part-ii.ipynb +++ b/examples/jupyter/mdgxs-part-ii.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Multigroup (Delayed) Cross Section Generation Part II: Advanced Features\n", "This IPython Notebook illustrates the use of the **`openmc.mgxs.Library`** class. The `Library` class is designed to automate the calculation of multi-group cross sections for use cases with one or more domains, cross section types, and/or nuclides. In particular, this Notebook illustrates the following features:\n", "\n", "* Calculation of multi-energy-group and multi-delayed-group cross sections for a **fuel assembly**\n", @@ -644,7 +645,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Using Tally Arithmetic to Compute the Delayed Neutron Precursor Concentrations" + "## Using Tally Arithmetic to Compute the Delayed Neutron Precursor Concentrations" ] }, { @@ -1170,7 +1171,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.7.0" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/mg-mode-part-i.ipynb b/examples/jupyter/mg-mode-part-i.ipynb index 23227b1ed3..a4f3822f28 100644 --- a/examples/jupyter/mg-mode-part-i.ipynb +++ b/examples/jupyter/mg-mode-part-i.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Multigroup Mode Part I: Introduction\n", "This Notebook illustrates the usage of OpenMC's multi-group calculational mode with the Python API. This example notebook creates and executes the 2-D [C5G7](https://www.oecd-nea.org/science/docs/2003/nsc-doc2003-16.pdf) benchmark model using the `openmc.MGXSLibrary` class to create the supporting data library on the fly." ] }, @@ -11,7 +12,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Generate MGXS Library" + "## Generate MGXS Library" ] }, { @@ -137,7 +138,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Generate 2-D C5G7 Problem Input Files" + "## Generate 2-D C5G7 Problem Input Files" ] }, { @@ -622,7 +623,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Results Visualization\n", + "## Results Visualization\n", "\n", "Now that we have run the simulation, let's look at the fission rate and flux tallies that we tallied." ] @@ -693,7 +694,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.6.7" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/mg-mode-part-ii.ipynb b/examples/jupyter/mg-mode-part-ii.ipynb index 85a8d73675..ef9e00017b 100644 --- a/examples/jupyter/mg-mode-part-ii.ipynb +++ b/examples/jupyter/mg-mode-part-ii.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Multigroup Mode Part II: MGXS Library Generation with OpenMC\n", "The previous Notebook in this series used multi-group mode to perform a calculation with previously defined cross sections. However, in many circumstances the multi-group data is not given and one must instead generate the cross sections for the specific application (or at least verify the use of cross sections from another application). \n", "\n", "This Notebook illustrates the use of the openmc.mgxs.Library class specifically for the calculation of MGXS to be used in OpenMC's multi-group mode. This example notebook is therefore very similar to the MGXS Part III notebook, except OpenMC is used as the multi-group solver instead of OpenMOC.\n", @@ -20,7 +21,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Generate Input Files" + "## Generate Input Files" ] }, { @@ -361,7 +362,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Create an MGXS Library\n", + "## Create an MGXS Library\n", "\n", "Now we are ready to generate multi-group cross sections! First, let's define a 2-group structure using the built-in EnergyGroups class." ] @@ -680,7 +681,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Tally Data Processing\n", + "## Tally Data Processing\n", "\n", "Our simulation ran successfully and created statepoint and summary output files. Let's begin by loading the StatePoint file." ] @@ -727,7 +728,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Multi-Group OpenMC Calculation" + "## Multi-Group OpenMC Calculation" ] }, { @@ -1005,7 +1006,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Results Comparison\n", + "## Results Comparison\n", "Now we can compare the multi-group and continuous-energy results.\n", "\n", "We will begin by loading the multi-group statepoint file we just finished writing and extracting the calculated keff." @@ -1092,7 +1093,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Pin Power Visualizations" + "## Pin Power Visualizations" ] }, { @@ -1208,7 +1209,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Scattering Anisotropy Treatments\n", + "## Scattering Anisotropy Treatments\n", "\n", "We will next show how we can work with the scattering angular distributions. OpenMC's MG solver has the capability to use group-to-group angular distributions which are represented as any of the following: a truncated Legendre series of up to the 10th order, a histogram distribution, and a tabular distribution. Any combination of these representations can be used by OpenMC during the transport process, so long as all constituents of a given material use the same representation. This means it is possible to have water represented by a tabular distribution and fuel represented by a Legendre if so desired.\n", "\n", @@ -1224,7 +1225,7 @@ "metadata": {}, "source": [ "\n", - "## Global P0 Scattering\n", + "### Global P0 Scattering\n", "First we begin by re-running with P0 scattering (i.e., isotropic) everywhere. If a global maximum order is requested, the most effective way to do this is to use the `max_order` attribute of our `openmc.Settings` object." ] }, @@ -1355,7 +1356,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "## Mixed Scattering Representations\n", + "### Mixed Scattering Representations\n", "OpenMC's Multi-Group mode also includes a feature where not every data in the library is required to have the same scattering treatment. For example, we could represent the water with P3 scattering, and the fuel and cladding with P0 scattering. This series will show how this can be done.\n", "\n", "First we will convert the data to P0 scattering, unless its water, then we will leave that as P3 data." @@ -1531,7 +1532,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.6.7" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/mg-mode-part-iii.ipynb b/examples/jupyter/mg-mode-part-iii.ipynb index e953d64d33..ea1e773f8d 100644 --- a/examples/jupyter/mg-mode-part-iii.ipynb +++ b/examples/jupyter/mg-mode-part-iii.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Multigroup Mode Part III: Advanced Feature Showcase\n", "This Notebook illustrates the use of the the more advanced features of OpenMC's multi-group mode and the openmc.mgxs.Library class. During this process, this notebook will illustrate the following features:\n", "\n", " - Calculation of multi-group cross sections for a simplified BWR 8x8 assembly with isotropic and angle-dependent MGXS.\n", @@ -17,7 +18,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Generate Input Files" + "## Generate Input Files" ] }, { @@ -456,7 +457,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Create an MGXS Library\n", + "## Create an MGXS Library\n", "\n", "Now we are ready to generate multi-group cross sections! First, let's define a 2-group structure using the built-in EnergyGroups class." ] @@ -817,7 +818,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Tally Data Processing\n", + "## Tally Data Processing\n", "\n", "Our simulation ran successfully and created statepoint and summary output files. Let's begin by loading the StatePoint file, but not automatically linking the summary file." ] @@ -878,7 +879,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Isotropic Multi-Group OpenMC Calculation" + "## Isotropic Multi-Group OpenMC Calculation" ] }, { @@ -1100,7 +1101,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Angle-Dependent Multi-Group OpenMC Calculation\n", + "## Angle-Dependent Multi-Group OpenMC Calculation\n", "\n", "Let's now run the calculation with the angle-dependent multi-group cross sections. This process will be the exact same as above, except this time we will use the angle-dependent Library as our starting point.\n", "\n", @@ -1200,7 +1201,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Results Comparison\n", + "## Results Comparison\n", "In this section we will compare the eigenvalues and fission rate distributions of the continuous-energy, isotropic multi-group and angle-dependent multi-group cases.\n", "\n", "We will begin by loading the multi-group statepoint files, first the isotropic, then angle-dependent. The angle-dependent was not renamed, so we can autolink its summary." @@ -1225,7 +1226,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "## Eigenvalue Comparison\n", + "### Eigenvalue Comparison\n", "Next, we can load the eigenvalues for comparison and do that comparison" ] }, @@ -1280,7 +1281,7 @@ "\n", "It is important to note that both eigenvalues can be improved by the application of finer geometric or energetic discretizations, but this shows that the angle discretization may be a factor for consideration.\n", "\n", - "## Fission Rate Distribution Comparison\n", + "### Fission Rate Distribution Comparison\n", "Next we will visualize the mesh tally results obtained from our three cases.\n", "\n", "This will be performed by first obtaining the one-group fission rate tally information from our state point files. After we have this information we will re-shape the data to match the original mesh laydown. We will then normalize, and finally create side-by-side plots of all." @@ -1417,7 +1418,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.7.0" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/mgxs-part-i.ipynb b/examples/jupyter/mgxs-part-i.ipynb index 264f8967cd..62a9b70b10 100644 --- a/examples/jupyter/mgxs-part-i.ipynb +++ b/examples/jupyter/mgxs-part-i.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Multigroup Cross Section Generation Part I: Introduction\n", "This IPython Notebook introduces the use of the `openmc.mgxs` module to calculate multi-group cross sections for an infinite homogeneous medium. In particular, this Notebook introduces the the following features:\n", "\n", "* **General equations** for scalar-flux averaged multi-group cross sections\n", @@ -1130,7 +1131,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.7.0" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/mgxs-part-ii.ipynb b/examples/jupyter/mgxs-part-ii.ipynb index 9e5cde42d2..dd5b21a551 100644 --- a/examples/jupyter/mgxs-part-ii.ipynb +++ b/examples/jupyter/mgxs-part-ii.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Multigroup Cross Section Generation Part II: Advanced Features\n", "This IPython Notebook illustrates the use of the `openmc.mgxs` module to calculate multi-group cross sections for a heterogeneous fuel pin cell geometry. In particular, this Notebook illustrates the following features:\n", "\n", "* Creation of multi-group cross sections on a **heterogeneous geometry**\n", @@ -2736,7 +2737,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.7.0" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/mgxs-part-iii.ipynb b/examples/jupyter/mgxs-part-iii.ipynb index a4c440b3a8..b05dbabd5c 100644 --- a/examples/jupyter/mgxs-part-iii.ipynb +++ b/examples/jupyter/mgxs-part-iii.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Multigroup Cross Section Generation Part III: Libraries\n", "This IPython Notebook illustrates the use of the **`openmc.mgxs.Library`** class. The `Library` class is designed to automate the calculation of multi-group cross sections for use cases with one or more domains, cross section types, and/or nuclides. In particular, this Notebook illustrates the following features:\n", "\n", "* Calculation of multi-group cross sections for a **fuel assembly**\n", @@ -1659,7 +1660,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.7.0" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/nuclear-data-resonance-covariance.ipynb b/examples/jupyter/nuclear-data-resonance-covariance.ipynb index d8bca235dc..8fe85161d2 100644 --- a/examples/jupyter/nuclear-data-resonance-covariance.ipynb +++ b/examples/jupyter/nuclear-data-resonance-covariance.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Nuclear Data: Resonance Covariance\n", "In this notebook we will explore features of the Python API that allow us to import and manipulate resonance covariance data. A full description of the ENDF-VI and ENDF-VII formats can be found in the [ENDF102 manual](https://www.oecd-nea.org/dbdata/data/manual-endf/endf102.pdf)." ] }, @@ -954,7 +955,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.7.0" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/nuclear-data.ipynb b/examples/jupyter/nuclear-data.ipynb index e13b143e4d..c63c24a17f 100644 --- a/examples/jupyter/nuclear-data.ipynb +++ b/examples/jupyter/nuclear-data.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Nuclear Data\n", "In this notebook, we will go through the salient features of the `openmc.data` package in the Python API. This package enables inspection, analysis, and conversion of nuclear data from ACE files. Most importantly, the package provides a mean to generate HDF5 nuclear data libraries that are used by the transport solver." ] }, @@ -1495,7 +1496,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.7.0" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/pandas-dataframes.ipynb b/examples/jupyter/pandas-dataframes.ipynb index ddc8ee429b..f5e5142b51 100644 --- a/examples/jupyter/pandas-dataframes.ipynb +++ b/examples/jupyter/pandas-dataframes.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Pandas Dataframes\n", "This notebook demonstrates how systematic analysis of tally scores is possible using Pandas dataframes. A dataframe can be automatically generated using the `Tally.get_pandas_dataframe(...)` method. Furthermore, by linking the tally data in a statepoint file with geometry and material information from a summary file, the dataframe can be shown with user-supplied labels." ] }, @@ -2687,7 +2688,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.8.5" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/pincell.ipynb b/examples/jupyter/pincell.ipynb index 0f11ca6559..dd0cf13136 100644 --- a/examples/jupyter/pincell.ipynb +++ b/examples/jupyter/pincell.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Modeling a Pin-Cell\n", "This notebook is intended to demonstrate the basic features of the Python API for constructing input files and running OpenMC. In it, we will show how to create a basic reflective pin-cell model that is equivalent to modeling an infinite array of fuel pins. If you have never used OpenMC, this can serve as a good starting point to learn the Python API. We highly recommend having a copy of the [Python API reference documentation](https://docs.openmc.org/en/stable/pythonapi/index.html) open in another browser tab that you can refer to." ] }, @@ -1574,7 +1575,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.8.5" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/pincell_depletion.ipynb b/examples/jupyter/pincell_depletion.ipynb index 94ec479f62..3fa46c00bd 100644 --- a/examples/jupyter/pincell_depletion.ipynb +++ b/examples/jupyter/pincell_depletion.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Pincell Depletion\n", "This notebook is intended to introduce the reader to the depletion interface contained in OpenMC. It is recommended that you are moderately familiar with building models using the OpenMC Python API. The earlier examples are excellent starting points, as this notebook will not focus heavily on model building.\n", "\n", "If you have a real power reactor, the fuel composition is constantly changing as fission events produce energy, remove some fissile isotopes, and produce fission products. Other reactions, like $(n, \\alpha)$ and $(n, \\gamma)$ will alter the composition as well. Furthermore, some nuclides undergo spontaneous decay with widely ranging frequencies. Depletion is the process of modeling this behavior.\n", @@ -26,7 +27,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Build the Geometry\n", + "## Build the Geometry\n", "\n", "Much of this section is borrowed from the \"Modeling a Pin-Cell\" example. If you find yourself not understanding some aspects of this section, feel free to refer to that example, as some details may be glossed over for brevity.\n", "\n", @@ -309,7 +310,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Setting up for depletion\n", + "## Setting up for depletion\n", "\n", "The OpenMC depletion interface can be accessed from the `openmc.deplete` module, and has a variety of classes that will help us." ] @@ -475,7 +476,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Processing the outputs\n", + "## Processing the outputs\n", "\n", "The depletion simulation produces a few output files. First, the statepoint files from each individual transport simulation are written to `openmc_simulation_n.h5`, where `` indicates the current depletion step. Any tallies that we defined in `tallies.xml` will be included in these files across our simulations. We have 7 such files, one for each our of 6 depletion steps and the initial state." ] @@ -708,7 +709,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Helpful tips\n", + "## Helpful tips\n", "\n", "Depletion is a tricky task to get correct. Use too short of time steps and you may never get your results due to running many transport simulations. Use long of time steps and you may get incorrect answers. Consider the xenon plot from above. Xenon-135 is a fission product with a thermal absorption cross section on the order of millions of barns, but has a half life of ~9 hours. Taking smaller time steps at the beginning of your simulation to build up some equilibrium in your fission products is highly recommended.\n", "\n", @@ -770,7 +771,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Register depletion chain\n", + "## Register depletion chain\n", "\n", "The depletion chain we created can be registered into the OpenMC `cross_sections.xml` file, so we don't have to always pass the `chain_file` argument to the `Operator`. To do this, we create a `DataLibrary` using `openmc.data`. Without any arguments, the `from_xml` method will look for the file located at `OPENMC_CROSS_SECTIONS`. For this example, we will just create a bare library." ] @@ -911,7 +912,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Choice of depletion step size\n", + "## Choice of depletion step size\n", "\n", "A general rule of thumb is to use depletion step sizes around 2 MWd/kgHM, where kgHM is really the initial heavy metal mass in kg. If your problem includes integral burnable absorbers, these typically require shorter time steps at or below 1 MWd/kgHM. These are typically valid for the predictor scheme, as the point of recent schemes is to extend this step size. A good convergence study, where the step size is decreased until some convergence metric is satisfied, is a beneficial exercise.\n", "\n", @@ -988,7 +989,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.7.4" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/post-processing.ipynb b/examples/jupyter/post-processing.ipynb index 44a2c2d4e8..d31af5831e 100644 --- a/examples/jupyter/post-processing.ipynb +++ b/examples/jupyter/post-processing.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Post Processing\n", "This notebook demonstrates some basic post-processing tasks that can be performed with the Python API, such as plotting a 2D mesh tally and plotting neutron source sites from an eigenvalue calculation. The problem we will use is a simple reflected pin-cell." ] }, @@ -971,7 +972,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.8.5" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/search.ipynb b/examples/jupyter/search.ipynb index 6c3e2169e3..a712726410 100644 --- a/examples/jupyter/search.ipynb +++ b/examples/jupyter/search.ipynb @@ -4,7 +4,8 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "This Notebook illustrates the usage of the OpenMC Python API's generic eigenvalue search capability. In this Notebook, we will do a critical boron concentration search of a typical PWR pin cell.\n", + "# Criticality Search\n", + "This notebook illustrates the usage of the OpenMC Python API's generic eigenvalue search capability. In this Notebook, we will do a critical boron concentration search of a typical PWR pin cell.\n", "\n", "To use the search functionality, we must create a function which creates our model according to the input parameter we wish to search for (in this case, the boron concentration). \n", "\n", @@ -31,7 +32,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Create Parametrized Model\n", + "## Create Parametrized Model\n", "\n", "To perform the search we will use the `openmc.search_for_keff` function. This function requires a different function be defined which creates an parametrized model to analyze. This model is required to be stored in an `openmc.model.Model` object. The first parameter of this function will be modified during the search process for our critical eigenvalue.\n", "\n", @@ -127,7 +128,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Search for the Critical Boron Concentration\n", + "## Search for the Critical Boron Concentration\n", "\n", "To perform the search we imply call the `openmc.search_for_keff` function and pass in the relvant arguments. For our purposes we will be passing in the model building function (`build_model` defined above), a bracketed range for the expected critical Boron concentration (1,000 to 2,500 ppm), the tolerance, and the method we wish to use. \n", "\n", @@ -225,7 +226,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.8.5" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/tally-arithmetic.ipynb b/examples/jupyter/tally-arithmetic.ipynb index 40eb2b05ff..0e8b53ac71 100644 --- a/examples/jupyter/tally-arithmetic.ipynb +++ b/examples/jupyter/tally-arithmetic.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Tally Arithmetic\n", "This notebook shows the how tallies can be combined (added, subtracted, multiplied, etc.) using the Python API in order to create derived tallies. Since no covariance information is obtained, it is assumed that tallies are completely independent of one another when propagating uncertainties. The target problem is a simple pin cell." ] }, @@ -1745,7 +1746,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.7.0" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/triso.ipynb b/examples/jupyter/triso.ipynb index 882463efc9..ae17ee3441 100644 --- a/examples/jupyter/triso.ipynb +++ b/examples/jupyter/triso.ipynb @@ -4,6 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ + "# Modeling TRISO Particles\n", "OpenMC includes a few convenience functions for generationing TRISO particle locations and placing them in a lattice. To be clear, this capability is not a stochastic geometry capability like that included in MCNP. It's also important to note that OpenMC does not use delta tracking, which would normally speed up calculations in geometries with tons of surfaces and cells. However, the computational burden can be eased by placing TRISO particles in a lattice." ] }, @@ -357,7 +358,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.8.5" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/unstructured-mesh-part-i.ipynb b/examples/jupyter/unstructured-mesh-part-i.ipynb index 4e6d873cc8..f307469de2 100644 --- a/examples/jupyter/unstructured-mesh-part-i.ipynb +++ b/examples/jupyter/unstructured-mesh-part-i.ipynb @@ -4,7 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Unstructured Mesh Tallies in OpenMC\n", + "# Unstructured Mesh: Introduction\n", "\n", "In this example we'll look at how to setup and use unstructured mesh tallies in OpenMC. Unstructured meshes are able to provide results over spatial regions of a problem while conforming to a specific geometric features -- something that is often difficult to do using the regular and rectilinear meshes in OpenMC.\n", "\n", @@ -696,7 +696,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.7.3" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/examples/jupyter/unstructured-mesh-part-ii.ipynb b/examples/jupyter/unstructured-mesh-part-ii.ipynb index 8c04ace568..92089cabc1 100644 --- a/examples/jupyter/unstructured-mesh-part-ii.ipynb +++ b/examples/jupyter/unstructured-mesh-part-ii.ipynb @@ -4,7 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "# Unstructured Mesh Tallies with CAD Geometry in OpenMC\n", + "# Unstructured Mesh: Tallies with CAD and Point Cloud Visualization\n", "\n", "In the first notebook on this topic, we looked at how to set up a tally using an unstructured mesh in OpenMC.\n", "In this notebook, we will explore using unstructured mesh in conjunction with CAD-based geometry to perform detailed geometry analysis on complex geomerty.\n", @@ -647,7 +647,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython3", - "version": "3.7.3" + "version": "3.8.3" } }, "nbformat": 4, diff --git a/setup.py b/setup.py index 6afac4df1b..02f3c08429 100755 --- a/setup.py +++ b/setup.py @@ -72,7 +72,8 @@ kwargs = { 'extras_require': { 'depletion-mpi': ['mpi4py'], 'docs': ['sphinx', 'sphinxcontrib-katex', 'sphinx-numfig', 'jupyter', - 'sphinxcontrib-svg2pdfconverter', 'sphinx-rtd-theme'], + 'sphinxcontrib-svg2pdfconverter', 'sphinx-rtd-theme', + 'nbsphinx'], 'test': ['pytest', 'pytest-cov', 'colorama'], 'vtk': ['vtk'], }, From 4f7617e90cb6a905fdb93566d737d31c52e1853d Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Wed, 14 Oct 2020 15:10:03 -0500 Subject: [PATCH 08/79] Fix documentation for source site attributes --- docs/source/io_formats/source.rst | 8 ++++---- docs/source/io_formats/statepoint.rst | 10 +++++----- openmc/statepoint.py | 7 ++++--- 3 files changed, 13 insertions(+), 12 deletions(-) diff --git a/docs/source/io_formats/source.rst b/docs/source/io_formats/source.rst index 6058241e1f..4cd023e12e 100644 --- a/docs/source/io_formats/source.rst +++ b/docs/source/io_formats/source.rst @@ -15,7 +15,7 @@ is that documented here. :Datasets: - **source_bank** (Compound type) -- Source bank information for each - particle. The compound type has fields ``wgt``, ``xyz``, ``uvw``, - ``E``, ``delayed_group``, and ``particle``, which represent the - weight, position, direction, energy, energy group, delayed group, - and type of the source particle, respectively. + particle. The compound type has fields ``r``, ``u``, ``E``, + ``wgt``, ``delayed_group``, and ``particle``, which represent the + position, direction, energy, weight, delayed group, and particle + type (0=neutron, 1=photon, 2=electron, 3=positron), respectively. diff --git a/docs/source/io_formats/statepoint.rst b/docs/source/io_formats/statepoint.rst index f90d5b3af5..3a2ad1600e 100644 --- a/docs/source/io_formats/statepoint.rst +++ b/docs/source/io_formats/statepoint.rst @@ -51,11 +51,11 @@ The current version of the statepoint file format is 17.0. - **global_tallies** (*double[][2]*) -- Accumulated sum and sum-of-squares for each global tally. - **source_bank** (Compound type) -- Source bank information for each - particle. The compound type has fields ``wgt``, ``xyz``, ``uvw``, - ``E``, ``g``, and ``delayed_group``, which represent the weight, - position, direction, energy, energy group, and delayed_group of the - source particle, respectively. Only present when `run_mode` is - 'eigenvalue'. + particle. The compound type has fields ``r``, ``u``, ``E``, + ``wgt``, ``delayed_group``, and ``particle``, which represent the + position, direction, energy, weight, delayed group, and particle + type (0=neutron, 1=photon, 2=electron, 3=positron), respectively. + Only present when `run_mode` is 'eigenvalue'. **/tallies/** diff --git a/openmc/statepoint.py b/openmc/statepoint.py index 294f6c546d..f6177fcc4a 100644 --- a/openmc/statepoint.py +++ b/openmc/statepoint.py @@ -93,9 +93,10 @@ class StatePoint: seed : int Pseudorandom number generator seed source : numpy.ndarray of compound datatype - Array of source sites. The compound datatype has fields 'wgt', 'xyz', - 'uvw', and 'E' corresponding to the weight, position, direction, and - energy of the source site. + Array of source sites. The compound datatype has fields 'r', 'u', + 'E', 'wgt', 'delayed_group', and 'particle', corresponding to the + position, direction, energy, weight, delayed group, and particle type + of the source site, respectively. source_present : bool Indicate whether source sites are present sparse : bool From 441d081dd51dab4d7943abf906f4ea3f2112847e Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Wed, 14 Oct 2020 15:16:50 -0500 Subject: [PATCH 09/79] Implement write_source_file function --- docs/source/pythonapi/base.rst | 10 ++++ openmc/source.py | 88 ++++++++++++++++++++++++++++++++++ 2 files changed, 98 insertions(+) diff --git a/docs/source/pythonapi/base.rst b/docs/source/pythonapi/base.rst index d621637bb1..544e7009cb 100644 --- a/docs/source/pythonapi/base.rst +++ b/docs/source/pythonapi/base.rst @@ -22,9 +22,19 @@ Simulation Settings :template: myclass.rst openmc.Source + openmc.SourceParticle openmc.VolumeCalculation openmc.Settings +The following function can be used for generating a source file: + +.. autosummary:: + :toctree: generated + :nosignatures: + :template: myfunction.rst + + openmc.write_source_file + Material Specification ---------------------- diff --git a/openmc/source.py b/openmc/source.py index 22952b4a59..3863bb826a 100644 --- a/openmc/source.py +++ b/openmc/source.py @@ -1,6 +1,10 @@ +from enum import Enum from numbers import Real from xml.etree import ElementTree as ET +import numpy as np +import h5py + import openmc.checkvalue as cv from openmc.stats.multivariate import UnitSphere, Spatial from openmc.stats.univariate import Univariate @@ -226,3 +230,87 @@ class Source: source.energy = Univariate.from_xml_element(energy) return source + + +class ParticleType(Enum): + NEUTRON = 0 + PHOTON = 1 + ELECTRON = 2 + POSITRON = 3 + + +class SourceParticle: + """Source particle + + This class can be used to create source particles that can be written to a + file and used by OpenMC + + Parameters + ---------- + r : iterable of float + Position of particle in Cartesian coordinates + u : iterable of float + Directional cosines + E : float + Energy of particle in [eV] + wgt : float + Weight of the particle + delayed_group : int + Delayed group particle was created in (neutrons only) + particle : ParticleType + Type of the particle + + """ + def __init__(self, r=(0., 0., 0.), u=(0., 0., 1.), E=1.0e6, wgt=1.0, + delayed_group=0, particle=ParticleType.NEUTRON): + self.r = tuple(r) + self.u = tuple(u) + self.E = float(E) + self.wgt = float(wgt) + self.delayed_group = delayed_group + self.particle = particle + + def to_tuple(self): + """Return source particle attributes as a tuple + + Returns + ------- + tuple + Source particle attributes + + """ + return (self.r, self.u, self.E, self.wgt, + self.delayed_group, self.particle.value) + + +def write_source_file(source_particles, filename, **kwargs): + """Write a source file using a collection of source particles + + Parameters + ---------- + source_particles : iterable of SourceParticle + Source particles to write to file + filename : str or path-like + Path to source file to write + **kwargs + Keyword arguments to pass to :class:`h5py.File` + + """ + # Create compound datatype for source particles + pos_dtype = np.dtype([('x', ' Date: Wed, 14 Oct 2020 15:47:08 -0500 Subject: [PATCH 10/79] Add test for source file generation --- tests/unit_tests/test_source_file.py | 38 ++++++++++++++++++++++++++++ 1 file changed, 38 insertions(+) create mode 100644 tests/unit_tests/test_source_file.py diff --git a/tests/unit_tests/test_source_file.py b/tests/unit_tests/test_source_file.py new file mode 100644 index 0000000000..e9bcebc92e --- /dev/null +++ b/tests/unit_tests/test_source_file.py @@ -0,0 +1,38 @@ +from random import random + +import h5py +import numpy as np +import openmc + + +def test_source_file(run_in_tmpdir): + # Create source particles + source = [] + n = 1000 + for i in range(n): + source.append(openmc.SourceParticle( + r=(random(), i, 0), + u=(0., 0., 1.), + E=float(n - i), + )) + + # Create source file + openmc.write_source_file(source, 'test_source.h5') + + # Get array of source particles from file + with h5py.File('test_source.h5', 'r') as fh: + arr = fh['source_bank'][...] + + # Ensure data is consistent + r = arr['r'] + assert np.all((r['x'] > 0.0) & (r['x'] < 1.0)) + assert np.all(r['y'] == np.arange(1000)) + assert np.all(r['z'] == 0.0) + u = arr['u'] + assert np.all(u['x'] == 0.0) + assert np.all(u['y'] == 0.0) + assert np.all(u['z'] == 1.0) + assert np.all(arr['E'] == n - np.arange(n)) + assert np.all(arr['wgt'] == 1.0) + assert np.all(arr['delayed_group'] == 0) + assert np.all(arr['particle'] == 0) From 2d8c9aed8108d1c1e638fce599b9f66ed0f86395 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Wed, 14 Oct 2020 15:49:59 -0500 Subject: [PATCH 11/79] Add note in state_point.cpp about updating compoung datatype for source --- src/state_point.cpp | 6 ++++++ 1 file changed, 6 insertions(+) diff --git a/src/state_point.cpp b/src/state_point.cpp index 14260051cc..e1ea52284a 100644 --- a/src/state_point.cpp +++ b/src/state_point.cpp @@ -508,6 +508,12 @@ hid_t h5banktype() { H5Tinsert(postype, "z", HOFFSET(Position, z), H5T_NATIVE_DOUBLE); // Create bank datatype + // + // If you make changes to the compound datatype here, make sure you update: + // - openmc/source.py + // - openmc/statepoint.py + // - docs/source/io_formats/statepoint.rst + // - docs/source/io_formats/source.rst hid_t banktype = H5Tcreate(H5T_COMPOUND, sizeof(struct Particle::Bank)); H5Tinsert(banktype, "r", HOFFSET(Particle::Bank, r), postype); H5Tinsert(banktype, "u", HOFFSET(Particle::Bank, u), postype); From 77015c0b1490e96db397f09f9ba2507cf377be8d Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Thu, 15 Oct 2020 13:46:05 -0500 Subject: [PATCH 12/79] Fixed issue in MG-Mode which surfaced when running problems which have microscopic cross sections defined and multiple fissile isotopes in a material --- include/openmc/constants.h | 4 +- include/openmc/mgxs.h | 2 +- include/openmc/scattdata.h | 3 +- src/material.cpp | 6 +- src/mgxs.cpp | 60 ++++++++++------- src/scattdata.cpp | 121 ++++++++++++++-------------------- src/tallies/tally_scoring.cpp | 16 ++--- src/xsdata.cpp | 17 ++++- 8 files changed, 120 insertions(+), 109 deletions(-) diff --git a/include/openmc/constants.h b/include/openmc/constants.h index 13b62ee87d..e75d8c03ca 100644 --- a/include/openmc/constants.h +++ b/include/openmc/constants.h @@ -289,9 +289,9 @@ enum class MgxsType { ABSORPTION, INVERSE_VELOCITY, DECAY_RATE, + NU_SCATTER, SCATTER, - SCATTER_MULT, - SCATTER_FMU_MULT, + NU_SCATTER_FMU, SCATTER_FMU, FISSION, KAPPA_FISSION, diff --git a/include/openmc/mgxs.h b/include/openmc/mgxs.h index f9c4722e94..ae7a54ad3e 100644 --- a/include/openmc/mgxs.h +++ b/include/openmc/mgxs.h @@ -117,7 +117,7 @@ class Mgxs { int num_group, int num_delay); //! \brief Constructor that initializes and populates all data to build a - //! macroscopic cross section from microscopic cross section. + //! macroscopic cross section from microscopic cross sections. //! //! @param in_name Name of the object. //! @param mat_kTs temperatures (in units of eV) that data is needed. diff --git a/include/openmc/scattdata.h b/include/openmc/scattdata.h index 75fd7a2fdb..aa91d56885 100644 --- a/include/openmc/scattdata.h +++ b/include/openmc/scattdata.h @@ -33,7 +33,8 @@ class ScattData { //! \brief Combines microscopic ScattDatas into a macroscopic one. void - base_combine(size_t max_order, const std::vector& those_scatts, + base_combine(size_t max_order, size_t order_dim, + const std::vector& those_scatts, const std::vector& scalars, xt::xtensor& in_gmin, xt::xtensor& in_gmax, double_2dvec& sparse_mult, double_3dvec& sparse_scatter); diff --git a/src/material.cpp b/src/material.cpp index 1d4e18108e..dd3f7ffd7a 100644 --- a/src/material.cpp +++ b/src/material.cpp @@ -211,10 +211,12 @@ Material::Material(pugi::xml_node node) for (int i = 0; i < n; ++i) { const auto& name {names[i]}; - // Check that this nuclide is listed in the cross_sections.xml file + // Check that this nuclide is listed in the nuclear data library + // (cross_sections.xml for CE and the MGXS HDF5 for MG) LibraryKey key {Library::Type::neutron, name}; if (data::library_map.find(key) == data::library_map.end()) { - fatal_error("Could not find nuclide " + name + " in cross_sections.xml."); + fatal_error("Could not find nuclide " + name + " in the " + "nuclear data library."); } // If this nuclide hasn't been encountered yet, we need to add its name diff --git a/src/mgxs.cpp b/src/mgxs.cpp index d5c144658d..5b61e5dedc 100644 --- a/src/mgxs.cpp +++ b/src/mgxs.cpp @@ -318,7 +318,8 @@ Mgxs::Mgxs(const std::string& in_name, const std::vector& mat_kTs, // Get the minimum data needed to initialize: // Dont need awr, but lets just initialize it anyways double in_awr = -1.; - // start with the assumption it is not fissionable + // start with the assumption it is not fissionable and set + // the fissionable status if we learn differently bool in_fissionable = false; for (int m = 0; m < micros.size(); m++) { if (micros[m]->fissionable) in_fissionable = true; @@ -377,25 +378,43 @@ Mgxs::Mgxs(const std::string& in_name, const std::vector& mat_kTs, } // end switch } // end microscopic temperature loop - // We are about to loop through each of the microscopic objects - // and incorporate the contribution of each microscopic data at - // one of the two temperature interpolants to this macroscopic quantity. - // If we are doing nearest temperature interpolation, then we don't need - // to do the 2nd temperature - int num_interp_points = 2; - if (settings::temperature_method == TemperatureMethod::NEAREST) num_interp_points = 1; - std::vector interp(micros.size()); - std::vector temp_indices(micros.size()); - for (int interp_point = 0; interp_point < num_interp_points; interp_point++) { - for (int m = 0; m < micros.size(); m++) { - interp[m] = (1. - micro_t_interp[m]) * atom_densities[m]; - temp_indices[m] = micro_t[m] + interp_point; - micro_t_interp[m] = 1. - micro_t_interp[m]; + // Now combine the microscopic data at each relevant temperature + // We will do this by treating the multiple temperatures of a nuclide as + // a different nuclide. Mathematically this just means the temperature + // interpolant is included in the number density. + // These interpolants are contained within interp. + std::vector interpolant; // the interpolant for the Mgxs + std::vector temp_indices; // the temperature index for each Mgxs + std::vector mgxs_to_combine; // The Mgxs to combine + // Now go through and build the above vectors so that we can use them to + // combine the data. We will step through each microscopic data and + // add in its lower and upper temperature points + for (int m = 0; m < micros.size(); m++) { + if (settings::temperature_method == TemperatureMethod::NEAREST) { + // Nearest interpolation only has one temperature point per isotope + // and so we dont need to include a temperature interpolant in + // the interpolant vector + interpolant.push_back(atom_densities[m]); + temp_indices.push_back(micro_t[m]); + mgxs_to_combine.push_back(micros[m]); + } else { + // This will be an interpolation between two points so get both these + // points + // Start with the low point + interpolant.push_back((1. - micro_t_interp[m]) * atom_densities[m]); + temp_indices.push_back(micro_t[m]); + mgxs_to_combine.push_back(micros[m]); + // The higher point + interpolant.push_back((micro_t_interp[m]) * atom_densities[m]); + temp_indices.push_back(micro_t[m] + 1); + mgxs_to_combine.push_back(micros[m]); } + } - combine(micros, interp, temp_indices, t); - } // end loop to sum all micros across the temperatures + // And finally, combine the data + combine(mgxs_to_combine, interpolant, temp_indices, t); } // end temperature (t) loop + } //============================================================================== @@ -407,9 +426,6 @@ Mgxs::combine(const std::vector& micros, const std::vector& scala // Build the vector of pointers to the xs objects within micros std::vector those_xs(micros.size()); for (int i = 0; i < micros.size(); i++) { - if (!xs[this_t].equiv(micros[i]->xs[micro_ts[i]])) { - fatal_error("Cannot combine the Mgxs objects!"); - } those_xs[i] = &(micros[i]->xs[micro_ts[i]]); } @@ -448,9 +464,9 @@ Mgxs::get_xs(MgxsType xstype, int gin, const int* gout, const double* mu, case MgxsType::KAPPA_FISSION: val = fissionable ? xs_t->kappa_fission(a, gin) : 0.; break; + case MgxsType::NU_SCATTER: case MgxsType::SCATTER: - case MgxsType::SCATTER_MULT: - case MgxsType::SCATTER_FMU_MULT: + case MgxsType::NU_SCATTER_FMU: case MgxsType::SCATTER_FMU: val = xs_t->scatter[a]->get_xs(xstype, gin, gout, mu); break; diff --git a/src/scattdata.cpp b/src/scattdata.cpp index e3c97512c3..dca906cb1d 100644 --- a/src/scattdata.cpp +++ b/src/scattdata.cpp @@ -5,6 +5,7 @@ #include #include "xtensor/xbuilder.hpp" +#include "xtensor/xview.hpp" #include "openmc/constants.h" #include "openmc/error.h" @@ -36,6 +37,13 @@ ScattData::base_init(int order, const xt::xtensor& in_gmin, energy[gin] = in_energy[gin]; mult[gin] = in_mult[gin]; + // Make sure the multiplicity does not have 0s + for (int go = 0; go < mult[gin].size(); go++) { + if (mult[gin][go] == 0.) { + mult[gin][go] = 1.; + } + } + // Make sure the energy is normalized double norm = std::accumulate(energy[gin].begin(), energy[gin].end(), 0.); @@ -54,77 +62,45 @@ ScattData::base_init(int order, const xt::xtensor& in_gmin, //============================================================================== void -ScattData::base_combine(size_t max_order, - const std::vector& those_scatts, const std::vector& scalars, - xt::xtensor& in_gmin, xt::xtensor& in_gmax, double_2dvec& sparse_mult, +ScattData::base_combine(size_t max_order, size_t order_dim, + const std::vector& those_scatts, + const std::vector& scalars, xt::xtensor& in_gmin, + xt::xtensor& in_gmax, double_2dvec& sparse_mult, double_3dvec& sparse_scatter) { size_t groups = those_scatts[0] -> energy.size(); // Now allocate and zero our storage spaces - xt::xtensor this_matrix({groups, groups, max_order}, 0.); - xt::xtensor mult_numer({groups, groups}, 0.); - xt::xtensor mult_denom({groups, groups}, 0.); - // TODO: Need to review this: - if (this->scattxs.size() > 0) { - this_matrix = this->get_matrix(max_order); - } + xt::xtensor this_nuscatt_matrix({groups, groups, order_dim}, 0.); + xt::xtensor this_nuscatt_P0({groups, groups}, 0.); + xt::xtensor this_scatt_P0({groups, groups}, 0.); + xt::xtensor this_mult({groups, groups}, 1.); + // Build the dense scattering and multiplicity matrices - // Get the multiplicity_matrix - // To combine from nuclidic data we need to use the final relationship - // mult_{gg'} = sum_i(N_i*nuscatt_{i,g,g'}) / - // sum_i(N_i*(nuscatt_{i,g,g'} / mult_{i,g,g'})) - // Developed as follows: - // mult_{gg'} = nuScatt{g,g'} / Scatt{g,g'} - // mult_{gg'} = sum_i(N_i*nuscatt_{i,g,g'}) / sum(N_i*scatt_{i,g,g'}) - // mult_{gg'} = sum_i(N_i*nuscatt_{i,g,g'}) / - // sum_i(N_i*(nuscatt_{i,g,g'} / mult_{i,g,g'})) - // nuscatt_{i,g,g'} can be reconstructed from the energy and scattxs member - // variables for (int i = 0; i < those_scatts.size(); i++) { ScattData* that = those_scatts[i]; // Build the dense matrix for that object xt::xtensor that_matrix = that->get_matrix(max_order); - // Now add that to this for the scattering and multiplicity + // Now add that to this for the nu-scatter matrix + this_nuscatt_matrix += scalars[i] * that_matrix; + + // Do the same with the P0 matrices for (int gin = 0; gin < groups; gin++) { - // Only spend time adding that's gmin to gmax data since the rest will - // be zeros - int i_gout = 0; - for (int gout = that->gmin(gin); gout <= that->gmax(gin); gout++) { - // Do the scattering matrix - for (int l = 0; l < max_order; l++) { - this_matrix(gin, gout, l) += scalars[i] * that_matrix(gin, gout, l); - } - - // Incorporate that's contribution to the multiplicity matrix data - double nuscatt = that->scattxs(gin) * that->energy[gin][i_gout]; - mult_numer(gin, gout) += scalars[i] * nuscatt; - if (that->mult[gin][i_gout] > 0.) { - mult_denom(gin, gout) += scalars[i] * nuscatt / that->mult[gin][i_gout]; - } else { - mult_denom(gin, gout) += scalars[i]; - } - i_gout++; + for (int go = 0; go < groups; go++) { + this_nuscatt_P0(gin, go) += + scalars[i] * that->get_xs(MgxsType::NU_SCATTER, gin, &go, nullptr); + this_scatt_P0(gin, go) += + scalars[i] * + that->get_xs(MgxsType::SCATTER, gin, &go, nullptr); } } } - // Combine mult_numer and mult_denom into the combined multiplicity matrix - xt::xtensor this_mult({groups, groups}, 1.); - // TODO: Need to check this too - for (int gin = 0; gin < groups; gin++) { - for (int gout = 0; gout < groups; gout++) { - if (std::abs(mult_denom(gin, gout)) > 0.0) { - this_mult(gin, gout) = mult_numer(gin, gout) / mult_denom(gin, gout); - } else { - if (mult_numer(gin, gout) == 0.0) { - this_mult(gin, gout) = 1.0; - } - } - } - } + // Now we have the dense nuscatt and scatt, we can easily compute the + // multiplicity matrix by dividing the two and fixing any nans + this_mult = xt::nan_to_num(this_nuscatt_P0 / this_scatt_P0); // We have the data, now we need to convert to a jagged array and then use // the initialize function to store it on the object. @@ -133,8 +109,8 @@ ScattData::base_combine(size_t max_order, int gmin_; for (gmin_ = 0; gmin_ < groups; gmin_++) { bool non_zero = false; - for (int l = 0; l < this_matrix.shape()[2]; l++) { - if (this_matrix(gin, gmin_, l) != 0.) { + for (int l = 0; l < this_nuscatt_matrix.shape()[2]; l++) { + if (this_nuscatt_matrix(gin, gmin_, l) != 0.) { non_zero = true; break; } @@ -144,8 +120,8 @@ ScattData::base_combine(size_t max_order, int gmax_; for (gmax_ = groups - 1; gmax_ >= 0; gmax_--) { bool non_zero = false; - for (int l = 0; l < this_matrix.shape()[2]; l++) { - if (this_matrix(gin, gmax_, l) != 0.) { + for (int l = 0; l < this_nuscatt_matrix.shape()[2]; l++) { + if (this_nuscatt_matrix(gin, gmax_, l) != 0.) { non_zero = true; break; } @@ -168,9 +144,9 @@ ScattData::base_combine(size_t max_order, sparse_mult[gin].resize(gmax_ - gmin_ + 1); int i_gout = 0; for (int gout = gmin_; gout <= gmax_; gout++) { - sparse_scatter[gin][i_gout].resize(this_matrix.shape()[2]); - for (int l = 0; l < this_matrix.shape()[2]; l++) { - sparse_scatter[gin][i_gout][l] = this_matrix(gin, gout, l); + sparse_scatter[gin][i_gout].resize(this_nuscatt_matrix.shape()[2]); + for (int l = 0; l < this_nuscatt_matrix.shape()[2]; l++) { + sparse_scatter[gin][i_gout][l] = this_nuscatt_matrix(gin, gout, l); } sparse_mult[gin][i_gout] = this_mult(gin, gout); i_gout++; @@ -178,6 +154,7 @@ ScattData::base_combine(size_t max_order, } } + //============================================================================== void @@ -212,10 +189,10 @@ ScattData::get_xs(MgxsType xstype, int gin, const int* gout, const double* mu) double val = scattxs[gin]; switch(xstype) { - case MgxsType::SCATTER: + case MgxsType::NU_SCATTER: if (gout != nullptr) val *= energy[gin][i_gout]; break; - case MgxsType::SCATTER_MULT: + case MgxsType::SCATTER: if (gout != nullptr) { val *= energy[gin][i_gout] / mult[gin][i_gout]; } else { @@ -223,7 +200,7 @@ ScattData::get_xs(MgxsType xstype, int gin, const int* gout, const double* mu) energy[gin].begin(), 0.0); } break; - case MgxsType::SCATTER_FMU_MULT: + case MgxsType::NU_SCATTER_FMU: if ((gout != nullptr) && (mu != nullptr)) { val *= energy[gin][i_gout] * calc_f(gin, *gout, *mu); } else { @@ -407,7 +384,6 @@ ScattDataLegendre::combine(const std::vector& those_scatts, size_t that_order = that->get_order(); if (that_order > max_order) max_order = that_order; } - max_order++; // Add one since this is a Legendre size_t groups = those_scatts[0] -> energy.size(); @@ -419,8 +395,9 @@ ScattDataLegendre::combine(const std::vector& those_scatts, // The rest of the steps do not depend on the type of angular representation // so we use a base class method to sum up xs and create new energy and mult // matrices - ScattData::base_combine(max_order, those_scatts, scalars, in_gmin, in_gmax, - sparse_mult, sparse_scatter); + size_t order_dim = max_order + 1; + ScattData::base_combine(max_order, order_dim, those_scatts, scalars, in_gmin, + in_gmax, sparse_mult, sparse_scatter); // Got everything we need, store it. init(in_gmin, in_gmax, sparse_mult, sparse_scatter); @@ -636,8 +613,9 @@ ScattDataHistogram::combine(const std::vector& those_scatts, // The rest of the steps do not depend on the type of angular representation // so we use a base class method to sum up xs and create new energy and mult // matrices - ScattData::base_combine(max_order, those_scatts, scalars, in_gmin, in_gmax, - sparse_mult, sparse_scatter); + size_t order_dim = max_order; + ScattData::base_combine(max_order, order_dim, those_scatts, scalars, in_gmin, + in_gmax, sparse_mult, sparse_scatter); // Got everything we need, store it. init(in_gmin, in_gmax, sparse_mult, sparse_scatter); @@ -854,8 +832,9 @@ ScattDataTabular::combine(const std::vector& those_scatts, // The rest of the steps do not depend on the type of angular representation // so we use a base class method to sum up xs and create new energy and mult // matrices - ScattData::base_combine(max_order, those_scatts, scalars, in_gmin, in_gmax, - sparse_mult, sparse_scatter); + size_t order_dim = max_order; + ScattData::base_combine(max_order, order_dim, those_scatts, scalars, in_gmin, + in_gmax, sparse_mult, sparse_scatter); // Got everything we need, store it. init(in_gmin, in_gmax, sparse_mult, sparse_scatter); diff --git a/src/tallies/tally_scoring.cpp b/src/tallies/tally_scoring.cpp index 396ab2f82b..894cdecea4 100644 --- a/src/tallies/tally_scoring.cpp +++ b/src/tallies/tally_scoring.cpp @@ -1566,17 +1566,17 @@ score_general_mg(Particle& p, int i_tally, int start_index, int filter_index, score = p.wgt_last_ * flux; if (i_nuclide >= 0) { score *= atom_density * nuc_xs.get_xs( - MgxsType::SCATTER_FMU_MULT, p.g_last_, &p.g_, &p.mu_, nullptr) + MgxsType::SCATTER_FMU, p.g_last_, &p.g_, &p.mu_, nullptr) / macro_xs.get_xs( - MgxsType::SCATTER_FMU_MULT, p.g_last_, &p.g_, &p.mu_, nullptr); + MgxsType::SCATTER_FMU, p.g_last_, &p.g_, &p.mu_, nullptr); } } else { if (i_nuclide >= 0) { score = atom_density * flux * nuc_xs.get_xs( - MgxsType::SCATTER_MULT, p_g, nullptr, &p.mu_, nullptr); + MgxsType::SCATTER, p_g, nullptr, &p.mu_, nullptr); } else { score = flux * macro_xs.get_xs( - MgxsType::SCATTER_MULT, p_g, nullptr, &p.mu_, nullptr); + MgxsType::SCATTER, p_g, nullptr, &p.mu_, nullptr); } } break; @@ -1595,16 +1595,16 @@ score_general_mg(Particle& p, int i_tally, int start_index, int filter_index, // adjust the score by the actual probability for that nuclide. if (i_nuclide >= 0) { score *= atom_density - * nuc_xs.get_xs(MgxsType::SCATTER_FMU, p.g_last_, &p.g_, + * nuc_xs.get_xs(MgxsType::NU_SCATTER_FMU, p.g_last_, &p.g_, &p.mu_, nullptr) - / macro_xs.get_xs(MgxsType::SCATTER_FMU, p.g_last_, &p.g_, + / macro_xs.get_xs(MgxsType::NU_SCATTER_FMU, p.g_last_, &p.g_, &p.mu_, nullptr); } } else { if (i_nuclide >= 0) { - score = atom_density * flux * nuc_xs.get_xs(MgxsType::SCATTER, p_g); + score = atom_density * flux * nuc_xs.get_xs(MgxsType::NU_SCATTER, p_g); } else { - score = flux * macro_xs.get_xs(MgxsType::SCATTER, p_g); + score = flux * macro_xs.get_xs(MgxsType::NU_SCATTER, p_g); } } break; diff --git a/src/xsdata.cpp b/src/xsdata.cpp index d4698e2a08..ff360c0529 100644 --- a/src/xsdata.cpp +++ b/src/xsdata.cpp @@ -529,12 +529,25 @@ XsData::combine(const std::vector& those_xs, kappa_fission += scalar * that->kappa_fission; fission += scalar * that->fission; delayed_nu_fission += scalar * that->delayed_nu_fission; - chi_prompt += scalar * that->chi_prompt; - chi_delayed += scalar * that->chi_delayed; + chi_prompt += scalar * + xt::view(xt::sum(that->prompt_nu_fission, {1}), + xt::all(), xt::newaxis(), xt::newaxis()) * + that->chi_prompt; + chi_delayed += scalar * + xt::view(xt::sum(that->delayed_nu_fission, {2}), + xt::all(), xt::all(), xt::newaxis(), xt::newaxis()) * + that->chi_delayed; } decay_rate += scalar * that->decay_rate; } + // Ensure the chi_prompt and chi_delayed are normalized to 1 for each + // azimuthal angle and delayed group (for chi_delayed) + chi_prompt /= + xt::view(xt::sum(chi_prompt, {2}), xt::all(), xt::all(), xt::newaxis()); + chi_delayed /= xt::view(xt::sum(chi_delayed, {3}), xt::all(), xt::all(), + xt::all(), xt::newaxis()); + // Allow the ScattData object to combine itself for (size_t a = 0; a < total.shape()[0]; a++) { // Build vector of the scattering objects to incorporate From 4ea666703db713d745f8f504406bdb1590d8c838 Mon Sep 17 00:00:00 2001 From: aprilnovak Date: Wed, 7 Oct 2020 18:53:47 -0500 Subject: [PATCH 13/79] Ensure correct initialization of shape_ and n_dimension_ for RegularMesh and simplify error checking. --- src/mesh.cpp | 32 ++++++++++++++------------------ 1 file changed, 14 insertions(+), 18 deletions(-) diff --git a/src/mesh.cpp b/src/mesh.cpp index 54d99250c8..5122c2b617 100644 --- a/src/mesh.cpp +++ b/src/mesh.cpp @@ -122,12 +122,20 @@ RegularMesh::RegularMesh(pugi::xml_node node) fatal_error("All entries on the element for a tally " "mesh must be positive."); } + } else { + fatal_error("Must specify on a mesh."); } // Check for lower-left coordinates if (check_for_node(node, "lower_left")) { // Read mesh lower-left corner location lower_left_ = get_node_xarray(node, "lower_left"); + + // Make sure lower_left and dimension match + if (n_dimension_ != lower_left_.size()) { + fatal_error("Number of entries on must be the same " + "as the number of entries on ."); + } } else { fatal_error("Must specify on a mesh."); } @@ -141,8 +149,7 @@ RegularMesh::RegularMesh(pugi::xml_node node) width_ = get_node_xarray(node, "width"); // Check to ensure width has same dimensions - auto n = width_.size(); - if (n != lower_left_.size()) { + if (n_dimension_ != width_.size()) { fatal_error("Number of entries on must be the same as " "the number of entries on ."); } @@ -158,9 +165,8 @@ RegularMesh::RegularMesh(pugi::xml_node node) } else if (check_for_node(node, "upper_right")) { upper_right_ = get_node_xarray(node, "upper_right"); - // Check to ensure width has same dimensions - auto n = upper_right_.size(); - if (n != lower_left_.size()) { + // Check to ensure upper right has same dimensions + if (n_dimension_ != upper_right_.size()) { fatal_error("Number of entries on must be the " "same as the number of entries on ."); } @@ -172,23 +178,13 @@ RegularMesh::RegularMesh(pugi::xml_node node) } // Set width - if (shape_.size() > 0) { - width_ = xt::eval((upper_right_ - lower_left_) / shape_); - } + width_ = xt::eval((upper_right_ - lower_left_) / shape_); } else { fatal_error("Must specify either and on a mesh."); } - // Make sure lower_left and dimension match - if (shape_.size() > 0) { - if (shape_.size() != lower_left_.size()) { - fatal_error("Number of entries on must be the same " - "as the number of entries on ."); - } - - // Set volume fraction - volume_frac_ = 1.0/xt::prod(shape_)(); - } + // Set volume fraction + volume_frac_ = 1.0/xt::prod(shape_)(); } int RegularMesh::get_bin(Position r) const From eb326df89dd0954235be5f6721416d11aea9477c Mon Sep 17 00:00:00 2001 From: aprilnovak Date: Thu, 15 Oct 2020 12:34:12 -0500 Subject: [PATCH 14/79] Correct typo in assigning ID to UFS mesh. --- src/settings.cpp | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/src/settings.cpp b/src/settings.cpp index d2980701c7..160811c8f1 100644 --- a/src/settings.cpp +++ b/src/settings.cpp @@ -582,7 +582,7 @@ void read_settings_xml() // Assign ID and set mapping model::meshes.back()->id_ = 10001; - model::mesh_map[10001] = index_entropy_mesh; + model::mesh_map[10001] = i_ufs_mesh; } if (i_ufs_mesh >= 0) { From 4215669492886df8f0cdc303795216fbb3003830 Mon Sep 17 00:00:00 2001 From: aprilnovak Date: Thu, 15 Oct 2020 13:28:05 -0500 Subject: [PATCH 15/79] Use heuristic in setting the entropy mesh dimension if not provided. --- openmc/settings.py | 9 ++++++++- src/settings.cpp | 39 ++++++--------------------------------- 2 files changed, 14 insertions(+), 34 deletions(-) diff --git a/openmc/settings.py b/openmc/settings.py index 16d4e9578d..1f0627207b 100644 --- a/openmc/settings.py +++ b/openmc/settings.py @@ -3,6 +3,7 @@ from enum import Enum from pathlib import Path from numbers import Real, Integral from xml.etree import ElementTree as ET +from math import ceil import openmc.checkvalue as cv from . import VolumeCalculation, Source, RegularMesh @@ -58,7 +59,7 @@ class Settings: Set whether the calculation should be continuous-energy or multi-group. entropy_mesh : openmc.RegularMesh Mesh to be used to calculate Shannon entropy. If the mesh dimensions are - not specified. OpenMC assigns a mesh such that 20 source sites per mesh + not specified, OpenMC assigns a mesh such that 20 source sites per mesh cell are to be expected on average. event_based : bool Indicate whether to use event-based parallelism instead of the default @@ -927,6 +928,12 @@ class Settings: def _create_entropy_mesh_subelement(self, root): if self.entropy_mesh is not None: + # use default heuristic for entropy mesh if not set by user + if self.entropy_mesh.dimension is None: + n = ceil((self.particles / 20.0)**(1.0 / 3.0)) + d = len(self.entropy_mesh.lower_left) + self.entropy_mesh.dimension = (n,)*d + # See if a element already exists -- if not, add it path = "./mesh[@id='{}']".format(self.entropy_mesh.id) if root.find(path) is None: diff --git a/src/settings.cpp b/src/settings.cpp index 160811c8f1..dc4535131a 100644 --- a/src/settings.cpp +++ b/src/settings.cpp @@ -510,52 +510,25 @@ void read_settings_xml() read_meshes(root); // Shannon Entropy mesh - int32_t index_entropy_mesh = -1; if (check_for_node(root, "entropy_mesh")) { int temp = std::stoi(get_node_value(root, "entropy_mesh")); if (model::mesh_map.find(temp) == model::mesh_map.end()) { fatal_error(fmt::format( "Mesh {} specified for Shannon entropy does not exist.", temp)); } - index_entropy_mesh = model::mesh_map.at(temp); - } else if (check_for_node(root, "entropy")) { - warning("Specifying a Shannon entropy mesh via the element " - "is deprecated. Please create a mesh using and then reference " - "it by specifying its ID in an element."); - - // Read entropy mesh from - auto node_entropy = root.child("entropy"); - model::meshes.push_back(std::make_unique(node_entropy)); - - // Set entropy mesh index - index_entropy_mesh = model::meshes.size() - 1; - - // Assign ID and set mapping - model::meshes.back()->id_ = 10000; - model::mesh_map[10000] = index_entropy_mesh; - } - - if (index_entropy_mesh >= 0) { auto* m = dynamic_cast( - model::meshes[index_entropy_mesh].get()); + model::meshes[model::mesh_map.at(temp)].get()); if (!m) fatal_error("Only regular meshes can be used as an entropy mesh"); simulation::entropy_mesh = m; - if (m->shape_.size() == 0) { - // If the user did not specify how many mesh cells are to be used in - // each direction, we automatically determine an appropriate number of - // cells - int n = std::ceil(std::pow(n_particles / 20.0, 1.0/3.0)); - m->shape_ = {n, n, n}; - m->n_dimension_ = 3; - - // Calculate width - m->width_ = (m->upper_right_ - m->lower_left_) / m->shape_; - } - // Turn on Shannon entropy calculation entropy_on = true; + + } else if (check_for_node(root, "entropy")) { + fatal_error("Specifying a Shannon entropy mesh via the element " + "is deprecated. Please create a mesh using and then reference " + "it by specifying its ID in an element."); } // Uniform fission source weighting mesh From b4deb90ad84f8dcf0b9f58311073f181bc82d59c Mon Sep 17 00:00:00 2001 From: aprilnovak Date: Fri, 16 Oct 2020 15:27:36 -0500 Subject: [PATCH 16/79] Ensure user sets particles before using entropy mesh dimension heuristic. --- openmc/settings.py | 10 +++++++--- 1 file changed, 7 insertions(+), 3 deletions(-) diff --git a/openmc/settings.py b/openmc/settings.py index 1f0627207b..7166a5119c 100644 --- a/openmc/settings.py +++ b/openmc/settings.py @@ -930,9 +930,13 @@ class Settings: if self.entropy_mesh is not None: # use default heuristic for entropy mesh if not set by user if self.entropy_mesh.dimension is None: - n = ceil((self.particles / 20.0)**(1.0 / 3.0)) - d = len(self.entropy_mesh.lower_left) - self.entropy_mesh.dimension = (n,)*d + if self.particles is None: + raise RuntimeError("Number of particles must be set in order to " \ + "use entropy mesh dimension heuristic") + else: + n = ceil((self.particles / 20.0)**(1.0 / 3.0)) + d = len(self.entropy_mesh.lower_left) + self.entropy_mesh.dimension = (n,)*d # See if a element already exists -- if not, add it path = "./mesh[@id='{}']".format(self.entropy_mesh.id) From 15190e632e986d1c13abb31509de5e5b305b7c9c Mon Sep 17 00:00:00 2001 From: aprilnovak Date: Fri, 16 Oct 2020 15:31:52 -0500 Subject: [PATCH 17/79] Deprecate uniform_fs XML syntax. --- src/settings.cpp | 27 +++++-------------- .../regression_tests/uniform_fs/settings.xml | 6 +++-- 2 files changed, 10 insertions(+), 23 deletions(-) diff --git a/src/settings.cpp b/src/settings.cpp index dc4535131a..8e402b7110 100644 --- a/src/settings.cpp +++ b/src/settings.cpp @@ -532,39 +532,24 @@ void read_settings_xml() } // Uniform fission source weighting mesh - int32_t i_ufs_mesh = -1; if (check_for_node(root, "ufs_mesh")) { auto temp = std::stoi(get_node_value(root, "ufs_mesh")); if (model::mesh_map.find(temp) == model::mesh_map.end()) { fatal_error(fmt::format("Mesh {} specified for uniform fission site " "method does not exist.", temp)); } - i_ufs_mesh = model::mesh_map.at(temp); - } else if (check_for_node(root, "uniform_fs")) { - warning("Specifying a UFS mesh via the element " - "is deprecated. Please create a mesh using and then reference " - "it by specifying its ID in a element."); - - // Read entropy mesh from - auto node_ufs = root.child("uniform_fs"); - model::meshes.push_back(std::make_unique(node_ufs)); - - // Set entropy mesh index - i_ufs_mesh = model::meshes.size() - 1; - - // Assign ID and set mapping - model::meshes.back()->id_ = 10001; - model::mesh_map[10001] = i_ufs_mesh; - } - - if (i_ufs_mesh >= 0) { - auto* m = dynamic_cast(model::meshes[i_ufs_mesh].get()); + auto* m = dynamic_cast(model::meshes[model::mesh_map.at(temp)].get()); if (!m) fatal_error("Only regular meshes can be used as a UFS mesh"); simulation::ufs_mesh = m; // Turn on uniform fission source weighting ufs_on = true; + + } else if (check_for_node(root, "uniform_fs")) { + fatal_error("Specifying a UFS mesh via the element " + "is deprecated. Please create a mesh using and then reference " + "it by specifying its ID in a element."); } // Check if the user has specified to write state points diff --git a/tests/regression_tests/uniform_fs/settings.xml b/tests/regression_tests/uniform_fs/settings.xml index 3e6ef672fd..e2c9c095eb 100644 --- a/tests/regression_tests/uniform_fs/settings.xml +++ b/tests/regression_tests/uniform_fs/settings.xml @@ -10,10 +10,12 @@ - + 10 10 10 -10. -10. -10. 10. 10. 10. - + + + 1 From 96b580d42435192c96cfd67d4d65f1af2b307207 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Mon, 19 Oct 2020 06:35:07 -0500 Subject: [PATCH 18/79] Incorporating changes requested by @giudgiud --- openmc/mgxs/mgxs.py | 14 +++++++------- src/mgxs.cpp | 2 +- src/scattdata.cpp | 9 +++++++++ 3 files changed, 17 insertions(+), 8 deletions(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 175742b970..0fc6716f35 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -2872,7 +2872,7 @@ class DiffusionCoefficient(TransportXS): \phi \rangle}{\langle \phi \rangle} \\ D = \frac{1}{3 \sigma_{tr}} \end{aligned} - + To incorporate the effect of scattering multiplication in the above relation, the `nu` parameter can be set to `True`. @@ -3057,7 +3057,7 @@ class DiffusionCoefficient(TransportXS): filter_bins=[('P1',)], squeeze=True) p1_tally._scores = ['scatter-1'] - + total = self.tallies['total'] / self.tallies['flux (tracklength)'] trans_corr = p1_tally / self.tallies['flux (analog)'] transport = (total - trans_corr) @@ -3066,7 +3066,7 @@ class DiffusionCoefficient(TransportXS): else: dif_coef = self.rxn_rate_tally - + flux_tally = condensed_xs.tallies['flux (tracklength)'] condensed_xs._tallies = OrderedDict() condensed_xs._tallies[self._rxn_type] = dif_coef @@ -5633,8 +5633,8 @@ class Chi(MGXS): """ # Store whether or not the number density should be removed for microscopic - # values of this data; since this chi data is normalized to 1.0, the - # data should not be divided by the number density + # values of this data; since this chi data is normalized to 1.0, the + # data should not be divided by the number density _divide_by_density = False def __init__(self, domain=None, domain_type=None, groups=None, @@ -6554,7 +6554,7 @@ class MeshSurfaceMGXS(MGXS): surfaces = df.pop(col_key) df.insert(len(self.domain.dimension), col_key, surfaces) if len(self.domain.dimension) == 1: - df.sort_values(by=[(mesh_str, 'x'), (mesh_str, 'surf')] + df.sort_values(by=[(mesh_str, 'x'), (mesh_str, 'surf')] + columns, inplace=True) elif len(self.domain.dimension) == 2: df.sort_values(by=[(mesh_str, 'x'), (mesh_str, 'y'), @@ -6642,7 +6642,7 @@ class Current(MeshSurfaceMGXS): is None unless the multi-group cross section has been computed. num_subdomains : int The number of subdomains is equal to the number of mesh surfaces times - two to account for both the incoming and outgoing current from the + two to account for both the incoming and outgoing current from the mesh cell surfaces. num_nuclides : int Unused in MeshSurfaceMGXS diff --git a/src/mgxs.cpp b/src/mgxs.cpp index 5b61e5dedc..dec505f3cc 100644 --- a/src/mgxs.cpp +++ b/src/mgxs.cpp @@ -382,7 +382,7 @@ Mgxs::Mgxs(const std::string& in_name, const std::vector& mat_kTs, // We will do this by treating the multiple temperatures of a nuclide as // a different nuclide. Mathematically this just means the temperature // interpolant is included in the number density. - // These interpolants are contained within interp. + // These interpolants are contained within interpolant. std::vector interpolant; // the interpolant for the Mgxs std::vector temp_indices; // the temperature index for each Mgxs std::vector mgxs_to_combine; // The Mgxs to combine diff --git a/src/scattdata.cpp b/src/scattdata.cpp index dca906cb1d..6c20b8e37d 100644 --- a/src/scattdata.cpp +++ b/src/scattdata.cpp @@ -38,12 +38,21 @@ ScattData::base_init(int order, const xt::xtensor& in_gmin, mult[gin] = in_mult[gin]; // Make sure the multiplicity does not have 0s + unsigned long int num_converted = 0; for (int go = 0; go < mult[gin].size(); go++) { if (mult[gin][go] == 0.) { + num_converted += 1; mult[gin][go] = 1.; } } + if (num_converted > 0) { + // Raise a warning to the user if we did have to do the conversion + std::string msg = std::to_string(num_converted) + + "entries in the Multiplicity Matrix were changed from 0 to 1"; + warning(msg); + } + // Make sure the energy is normalized double norm = std::accumulate(energy[gin].begin(), energy[gin].end(), 0.); From 975fb850d653d4536f65fe6db416468e411d4806 Mon Sep 17 00:00:00 2001 From: Jonathan Shimwell Date: Mon, 19 Oct 2020 13:33:02 +0100 Subject: [PATCH 19/79] rename varible as suggested in review Co-authored-by: Paul Romano --- openmc/data/reaction.py | 3 ++- openmc/deplete/helpers.py | 5 ++--- openmc/plotter.py | 6 +++--- 3 files changed, 7 insertions(+), 7 deletions(-) diff --git a/openmc/data/reaction.py b/openmc/data/reaction.py index 6da151e040..276218df06 100644 --- a/openmc/data/reaction.py +++ b/openmc/data/reaction.py @@ -64,7 +64,8 @@ REACTION_NAME.update({i: '(n,3He{})'.format(i - 750) for i in range(750, 799)}) REACTION_NAME.update({i: '(n,a{})'.format(i - 800) for i in range(800, 849)}) REACTION_NAME.update({i: '(n,2n{})'.format(i - 875) for i in range(875, 891)}) -REACTION_NUMBER = dict(zip(REACTION_NAME.values(), REACTION_NAME.keys())) +REACTION_MT = {name: mt for mt, name in REACTION_NAME.items()} +REACTION_MT['fission'] = 18 FISSION_MTS = (18, 19, 20, 21, 38) diff --git a/openmc/deplete/helpers.py b/openmc/deplete/helpers.py index 4ffcdb245a..0f55bb910e 100644 --- a/openmc/deplete/helpers.py +++ b/openmc/deplete/helpers.py @@ -11,7 +11,7 @@ from numpy import dot, zeros, newaxis, asarray from . import comm from openmc.checkvalue import check_type, check_greater_than -from openmc.data import JOULE_PER_EV, REACTION_NUMBER +from openmc.data import JOULE_PER_EV, REACTION_MT from openmc.lib import ( Tally, MaterialFilter, EnergyFilter, EnergyFunctionFilter) import openmc.lib @@ -169,8 +169,7 @@ class FluxCollapseHelper(ReactionRateHelper): self._materials = materials # adds an entry for fisson to the dictionary of reactions - REACTION_NUMBER['fission'] = 18 - self._mts = [REACTION_NUMBER[x] for x in scores] + self._mts = [REACTION_MT[x] for x in scores] self._scores = scores # Create flux tally with material and energy filters diff --git a/openmc/plotter.py b/openmc/plotter.py index ae4b87add3..c6f069aa62 100644 --- a/openmc/plotter.py +++ b/openmc/plotter.py @@ -309,7 +309,7 @@ def _calculate_cexs_nuclide(this, types, temperature=294., sab_name=None, Nuclide object to source data from types : Iterable of str or Integral The type of cross sections to calculate; values can either be those - in openmc.PLOT_TYPES or keys from openmc.data.REACTION_NUMBER which + in openmc.PLOT_TYPES or keys from openmc.data.REACTION_MT which correspond to a reaction description e.g '(n,2n)' or integers which correspond to reaction channel (MT) numbers. temperature : float, optional @@ -405,8 +405,8 @@ def _calculate_cexs_nuclide(this, types, temperature=294., sab_name=None, ops.append((np.add,) * (len(tmp_mts) - 2) + (np.multiply,)) else: ops.append((np.add,) * (len(tmp_mts) - 1)) - elif line in openmc.data.REACTION_NUMBER.keys(): - mt_number = openmc.data.REACTION_NUMBER[line] + elif line in openmc.data.REACTION_MT: + mt_number = openmc.data.REACTION_MT[line] cv.check_type('MT in types', mt_number, Integral) cv.check_greater_than('MT in types', mt_number, 0) tmp_mts = nuc.get_reaction_components(mt_number) From 43cb227e981a887b2f21eb97f44d8de8037e6310 Mon Sep 17 00:00:00 2001 From: Jonathan Shimwell Date: Mon, 19 Oct 2020 13:40:41 +0100 Subject: [PATCH 20/79] added latest build for master branch --- .github/workflows/dockerhub-publish-dev.yml | 32 +++++++++++++++++++++ .github/workflows/dockerhub-publish.yml | 32 +++++++++++++++++++++ 2 files changed, 64 insertions(+) create mode 100644 .github/workflows/dockerhub-publish-dev.yml create mode 100644 .github/workflows/dockerhub-publish.yml diff --git a/.github/workflows/dockerhub-publish-dev.yml b/.github/workflows/dockerhub-publish-dev.yml new file mode 100644 index 0000000000..00fab4129a --- /dev/null +++ b/.github/workflows/dockerhub-publish-dev.yml @@ -0,0 +1,32 @@ +name: dockerhub-publish-develop + +on: + push: + branches: develop + +jobs: + main: + runs-on: ubuntu-latest + steps: + - + name: Set up QEMU + uses: docker/setup-qemu-action@v1 + - + name: Set up Docker Buildx + uses: docker/setup-buildx-action@v1 + - + name: Login to DockerHub + uses: docker/login-action@v1 + with: + username: ${{ secrets.DOCKERHUB_USERNAME }} + password: ${{ secrets.DOCKERHUB_TOKEN }} + - + name: Build and push + id: docker_build + uses: docker/build-push-action@v2 + with: + push: true + tags: openmc/openmc:develop + - + name: Image digest + run: echo ${{ steps.docker_build.outputs.digest }} diff --git a/.github/workflows/dockerhub-publish.yml b/.github/workflows/dockerhub-publish.yml new file mode 100644 index 0000000000..0737849e93 --- /dev/null +++ b/.github/workflows/dockerhub-publish.yml @@ -0,0 +1,32 @@ +name: dockerhub-publish-latest + +on: + push: + branches: master + +jobs: + main: + runs-on: ubuntu-latest + steps: + - + name: Set up QEMU + uses: docker/setup-qemu-action@v1 + - + name: Set up Docker Buildx + uses: docker/setup-buildx-action@v1 + - + name: Login to DockerHub + uses: docker/login-action@v1 + with: + username: ${{ secrets.DOCKERHUB_USERNAME }} + password: ${{ secrets.DOCKERHUB_TOKEN }} + - + name: Build and push + id: docker_build + uses: docker/build-push-action@v2 + with: + push: true + tags: openmc/openmc:latest + - + name: Image digest + run: echo ${{ steps.docker_build.outputs.digest }} From 27034923f92ec61d756fc0f533372d35b5b07c0b Mon Sep 17 00:00:00 2001 From: Jonathan Shimwell Date: Mon, 19 Oct 2020 13:42:48 +0100 Subject: [PATCH 21/79] wrong dir, moved file --- github/workflows/dockerhub-publish-dev.yml | 32 ---------------------- 1 file changed, 32 deletions(-) delete mode 100644 github/workflows/dockerhub-publish-dev.yml diff --git a/github/workflows/dockerhub-publish-dev.yml b/github/workflows/dockerhub-publish-dev.yml deleted file mode 100644 index f025e2ab2d..0000000000 --- a/github/workflows/dockerhub-publish-dev.yml +++ /dev/null @@ -1,32 +0,0 @@ -name: dockerhub-publish - -on: - push: - branches: develop - -jobs: - main: - runs-on: ubuntu-latest - steps: - - - name: Set up QEMU - uses: docker/setup-qemu-action@v1 - - - name: Set up Docker Buildx - uses: docker/setup-buildx-action@v1 - - - name: Login to DockerHub - uses: docker/login-action@v1 - with: - username: ${{ secrets.DOCKERHUB_USERNAME }} - password: ${{ secrets.DOCKERHUB_TOKEN }} - - - name: Build and push - id: docker_build - uses: docker/build-push-action@v2 - with: - push: true - tags: openmc/openmc:dev - - - name: Image digest - run: echo ${{ steps.docker_build.outputs.digest }} From 986dc94aedd86aae727b0485798d3b5dc93d556a Mon Sep 17 00:00:00 2001 From: Jonathan Shimwell Date: Mon, 19 Oct 2020 13:48:48 +0100 Subject: [PATCH 22/79] changed trigger to on PR to test if secrets work --- .github/workflows/dockerhub-publish-dev.yml | 2 ++ 1 file changed, 2 insertions(+) diff --git a/.github/workflows/dockerhub-publish-dev.yml b/.github/workflows/dockerhub-publish-dev.yml index 00fab4129a..0a08f848c8 100644 --- a/.github/workflows/dockerhub-publish-dev.yml +++ b/.github/workflows/dockerhub-publish-dev.yml @@ -3,6 +3,8 @@ name: dockerhub-publish-develop on: push: branches: develop + pull_request: + branches: develop jobs: main: From 4068bb8ac51d0431f6c8aec8aa56998acafd12e1 Mon Sep 17 00:00:00 2001 From: Jonathan Shimwell Date: Mon, 19 Oct 2020 13:56:01 +0100 Subject: [PATCH 23/79] removed PR trigger --- .github/workflows/dockerhub-publish-dev.yml | 2 -- 1 file changed, 2 deletions(-) diff --git a/.github/workflows/dockerhub-publish-dev.yml b/.github/workflows/dockerhub-publish-dev.yml index 0a08f848c8..00fab4129a 100644 --- a/.github/workflows/dockerhub-publish-dev.yml +++ b/.github/workflows/dockerhub-publish-dev.yml @@ -3,8 +3,6 @@ name: dockerhub-publish-develop on: push: branches: develop - pull_request: - branches: develop jobs: main: From 2169cd57629f9b4b94558599ecc83110d046b4a2 Mon Sep 17 00:00:00 2001 From: aprilnovak Date: Mon, 19 Oct 2020 09:03:09 -0500 Subject: [PATCH 24/79] Fix indentation. --- openmc/settings.py | 14 +++++++------- 1 file changed, 7 insertions(+), 7 deletions(-) diff --git a/openmc/settings.py b/openmc/settings.py index 7166a5119c..4825432a8e 100644 --- a/openmc/settings.py +++ b/openmc/settings.py @@ -930,13 +930,13 @@ class Settings: if self.entropy_mesh is not None: # use default heuristic for entropy mesh if not set by user if self.entropy_mesh.dimension is None: - if self.particles is None: - raise RuntimeError("Number of particles must be set in order to " \ - "use entropy mesh dimension heuristic") - else: - n = ceil((self.particles / 20.0)**(1.0 / 3.0)) - d = len(self.entropy_mesh.lower_left) - self.entropy_mesh.dimension = (n,)*d + if self.particles is None: + raise RuntimeError("Number of particles must be set in order to " \ + "use entropy mesh dimension heuristic") + else: + n = ceil((self.particles / 20.0)**(1.0 / 3.0)) + d = len(self.entropy_mesh.lower_left) + self.entropy_mesh.dimension = (n,)*d # See if a element already exists -- if not, add it path = "./mesh[@id='{}']".format(self.entropy_mesh.id) From 0b0d03541df161177a92a27c05eadd01aeba166b Mon Sep 17 00:00:00 2001 From: aprilnovak Date: Thu, 15 Oct 2020 16:16:34 -0500 Subject: [PATCH 25/79] Put get_indices implementation into StructuredMesh base class. Refs #1695 --- include/openmc/mesh.h | 21 ++++++++++++--------- src/mesh.cpp | 35 +++++++++++++++-------------------- 2 files changed, 27 insertions(+), 29 deletions(-) diff --git a/include/openmc/mesh.h b/include/openmc/mesh.h index b7dcb017b4..75cc225023 100644 --- a/include/openmc/mesh.h +++ b/include/openmc/mesh.h @@ -116,7 +116,7 @@ public: //! \param[in] r Position to get indices for //! \param[out] ijk Array of mesh indices //! \param[out] in_mesh Whether position is in mesh - virtual void get_indices(Position r, int* ijk, bool* in_mesh) const = 0; + virtual void get_indices(Position r, int* ijk, bool* in_mesh) const; //! Get mesh indices corresponding to a mesh bin // @@ -124,12 +124,19 @@ public: //! \param[out] ijk Mesh indices virtual void get_indices_from_bin(int bin, int* ijk) const = 0; + //! Get mesh index in a particular direction + //! + //! \param[in] r Position to get index for + //! \param[in] i Direction index + virtual int get_index_in_direction(Position r, int i) const = 0; + //! Get a label for the mesh bin std::string bin_label(int bin) const override; // Data members xt::xtensor lower_left_; //!< Lower-left coordinates of mesh xt::xtensor upper_right_; //!< Upper-right coordinates of mesh + xt::xtensor shape_; //!< Number of mesh elements in each dimension }; //============================================================================== @@ -155,10 +162,10 @@ public: int get_bin_from_indices(const int* ijk) const override; - void get_indices(Position r, int* ijk, bool* in_mesh) const override; - void get_indices_from_bin(int bin, int* ijk) const override; + int get_index_in_direction(Position r, int i) const override; + int n_bins() const override; int n_surface_bins() const override; @@ -189,7 +196,6 @@ public: // Data members double volume_frac_; //!< Volume fraction of each mesh element - xt::xtensor shape_; //!< Number of mesh elements in each dimension xt::xtensor width_; //!< Width of each mesh element private: @@ -217,10 +223,10 @@ public: int get_bin_from_indices(const int* ijk) const override; - void get_indices(Position r, int* ijk, bool* in_mesh) const override; - void get_indices_from_bin(int bin, int* ijk) const override; + int get_index_in_direction(Position r, int i) const override; + int n_bins() const override; int n_surface_bins() const override; @@ -240,9 +246,6 @@ public: //! \return Whether the line segment connecting r0 and r1 intersects mesh bool intersects(Position& r0, Position r1, int* ijk) const; - // Data members - xt::xtensor shape_; //!< Number of mesh elements in each dimension - private: std::vector> grid_; }; diff --git a/src/mesh.cpp b/src/mesh.cpp index 5122c2b617..5c4da64617 100644 --- a/src/mesh.cpp +++ b/src/mesh.cpp @@ -102,6 +102,17 @@ StructuredMesh::bin_label(int bin) const { } } +void +StructuredMesh::get_indices(Position r, int* ijk, bool* in_mesh) const +{ + *in_mesh = true; + for (int i = 0; i < n_dimension_; ++i) { + ijk[i] = get_index_in_direction(r, i); + + if (ijk[i] < 1 || ijk[i] > shape_[i]) *in_mesh = false; + } +} + //============================================================================== // RegularMesh implementation //============================================================================== @@ -213,16 +224,9 @@ int RegularMesh::get_bin_from_indices(const int* ijk) const } } -void RegularMesh::get_indices(Position r, int* ijk, bool* in_mesh) const +int RegularMesh::get_index_in_direction(Position r, int i) const { - // Find particle in mesh - *in_mesh = true; - for (int i = 0; i < n_dimension_; ++i) { - ijk[i] = std::ceil((r[i] - lower_left_[i]) / width_[i]); - - // Check if indices are within bounds - if (ijk[i] < 1 || ijk[i] > shape_[i]) *in_mesh = false; - } + return std::ceil((r[i] - lower_left_[i]) / width_[i]); } void RegularMesh::get_indices_from_bin(int bin, int* ijk) const @@ -1175,18 +1179,9 @@ int RectilinearMesh::get_bin_from_indices(const int* ijk) const return ((ijk[2] - 1)*shape_[1] + (ijk[1] - 1))*shape_[0] + ijk[0] - 1; } -void RectilinearMesh::get_indices(Position r, int* ijk, bool* in_mesh) const +int RectilinearMesh::get_index_in_direction(Position r, int i) const { - *in_mesh = true; - - for (int i = 0; i < 3; ++i) { - if (r[i] < grid_[i].front() || r[i] > grid_[i].back()) { - ijk[i] = -1; - *in_mesh = false; - } else { - ijk[i] = lower_bound_index(grid_[i].begin(), grid_[i].end(), r[i]) + 1; - } - } + return lower_bound_index(grid_[i].begin(), grid_[i].end(), r[i]) + 1; } void RectilinearMesh::get_indices_from_bin(int bin, int* ijk) const From 7d0838d27b11def6adc2c627387602e777b234c0 Mon Sep 17 00:00:00 2001 From: aprilnovak Date: Thu, 15 Oct 2020 16:22:27 -0500 Subject: [PATCH 26/79] Move get_bin_from_indices into StructuredMesh base class. Refs #1695 --- include/openmc/mesh.h | 6 +----- src/mesh.cpp | 36 +++++++++++++++--------------------- 2 files changed, 16 insertions(+), 26 deletions(-) diff --git a/include/openmc/mesh.h b/include/openmc/mesh.h index 75cc225023..cfcc137e8e 100644 --- a/include/openmc/mesh.h +++ b/include/openmc/mesh.h @@ -109,7 +109,7 @@ public: // //! \param[in] Array of mesh indices //! \return Mesh bin - virtual int get_bin_from_indices(const int* ijk) const = 0; + virtual int get_bin_from_indices(const int* ijk) const; //! Get mesh indices given a position // @@ -160,8 +160,6 @@ public: int get_bin(Position r) const override; - int get_bin_from_indices(const int* ijk) const override; - void get_indices_from_bin(int bin, int* ijk) const override; int get_index_in_direction(Position r, int i) const override; @@ -221,8 +219,6 @@ public: int get_bin(Position r) const override; - int get_bin_from_indices(const int* ijk) const override; - void get_indices_from_bin(int bin, int* ijk) const override; int get_index_in_direction(Position r, int i) const override; diff --git a/src/mesh.cpp b/src/mesh.cpp index 5c4da64617..fd5b30466d 100644 --- a/src/mesh.cpp +++ b/src/mesh.cpp @@ -102,8 +102,7 @@ StructuredMesh::bin_label(int bin) const { } } -void -StructuredMesh::get_indices(Position r, int* ijk, bool* in_mesh) const +void StructuredMesh::get_indices(Position r, int* ijk, bool* in_mesh) const { *in_mesh = true; for (int i = 0; i < n_dimension_; ++i) { @@ -113,6 +112,20 @@ StructuredMesh::get_indices(Position r, int* ijk, bool* in_mesh) const } } +int StructuredMesh::get_bin_from_indices(const int* ijk) const +{ + switch (n_dimension_) { + case 1: + return ijk[0] - 1; + case 2: + return (ijk[1] - 1)*shape_[0] + ijk[0] - 1; + case 3: + return ((ijk[2] - 1)*shape_[1] + (ijk[1] - 1))*shape_[0] + ijk[0] - 1; + default: + throw std::runtime_error{"Invalid number of mesh dimensions"}; + } +} + //============================================================================== // RegularMesh implementation //============================================================================== @@ -210,20 +223,6 @@ int RegularMesh::get_bin(Position r) const return get_bin_from_indices(ijk.data()); } -int RegularMesh::get_bin_from_indices(const int* ijk) const -{ - switch (n_dimension_) { - case 1: - return ijk[0] - 1; - case 2: - return (ijk[1] - 1)*shape_[0] + ijk[0] - 1; - case 3: - return ((ijk[2] - 1)*shape_[1] + (ijk[1] - 1))*shape_[0] + ijk[0] - 1; - default: - throw std::runtime_error{"Invalid number of mesh dimensions"}; - } -} - int RegularMesh::get_index_in_direction(Position r, int i) const { return std::ceil((r[i] - lower_left_[i]) / width_[i]); @@ -1174,11 +1173,6 @@ int RectilinearMesh::get_bin(Position r) const return get_bin_from_indices(ijk); } -int RectilinearMesh::get_bin_from_indices(const int* ijk) const -{ - return ((ijk[2] - 1)*shape_[1] + (ijk[1] - 1))*shape_[0] + ijk[0] - 1; -} - int RectilinearMesh::get_index_in_direction(Position r, int i) const { return lower_bound_index(grid_[i].begin(), grid_[i].end(), r[i]) + 1; From 45b7dfb5a03b0e48620a7c1ac376e2dce57fca84 Mon Sep 17 00:00:00 2001 From: aprilnovak Date: Thu, 15 Oct 2020 16:26:36 -0500 Subject: [PATCH 27/79] Move implementation of get_indices_from_bin to StructuredMesh base class. Refs #1695 --- include/openmc/mesh.h | 6 +----- src/mesh.cpp | 35 ++++++++++++++--------------------- 2 files changed, 15 insertions(+), 26 deletions(-) diff --git a/include/openmc/mesh.h b/include/openmc/mesh.h index cfcc137e8e..9f1b80c035 100644 --- a/include/openmc/mesh.h +++ b/include/openmc/mesh.h @@ -122,7 +122,7 @@ public: // //! \param[in] bin Mesh bin //! \param[out] ijk Mesh indices - virtual void get_indices_from_bin(int bin, int* ijk) const = 0; + virtual void get_indices_from_bin(int bin, int* ijk) const; //! Get mesh index in a particular direction //! @@ -160,8 +160,6 @@ public: int get_bin(Position r) const override; - void get_indices_from_bin(int bin, int* ijk) const override; - int get_index_in_direction(Position r, int i) const override; int n_bins() const override; @@ -219,8 +217,6 @@ public: int get_bin(Position r) const override; - void get_indices_from_bin(int bin, int* ijk) const override; - int get_index_in_direction(Position r, int i) const override; int n_bins() const override; diff --git a/src/mesh.cpp b/src/mesh.cpp index fd5b30466d..17a87c47df 100644 --- a/src/mesh.cpp +++ b/src/mesh.cpp @@ -126,6 +126,20 @@ int StructuredMesh::get_bin_from_indices(const int* ijk) const } } +void StructuredMesh::get_indices_from_bin(int bin, int* ijk) const +{ + if (n_dimension_ == 1) { + ijk[0] = bin + 1; + } else if (n_dimension_ == 2) { + ijk[0] = bin % shape_[0] + 1; + ijk[1] = bin / shape_[0] + 1; + } else if (n_dimension_ == 3) { + ijk[0] = bin % shape_[0] + 1; + ijk[1] = (bin % (shape_[0] * shape_[1])) / shape_[0] + 1; + ijk[2] = bin / (shape_[0] * shape_[1]) + 1; + } +} + //============================================================================== // RegularMesh implementation //============================================================================== @@ -228,20 +242,6 @@ int RegularMesh::get_index_in_direction(Position r, int i) const return std::ceil((r[i] - lower_left_[i]) / width_[i]); } -void RegularMesh::get_indices_from_bin(int bin, int* ijk) const -{ - if (n_dimension_ == 1) { - ijk[0] = bin + 1; - } else if (n_dimension_ == 2) { - ijk[0] = bin % shape_[0] + 1; - ijk[1] = bin / shape_[0] + 1; - } else if (n_dimension_ == 3) { - ijk[0] = bin % shape_[0] + 1; - ijk[1] = (bin % (shape_[0] * shape_[1])) / shape_[0] + 1; - ijk[2] = bin / (shape_[0] * shape_[1]) + 1; - } -} - int RegularMesh::n_bins() const { int n_bins = 1; @@ -1178,13 +1178,6 @@ int RectilinearMesh::get_index_in_direction(Position r, int i) const return lower_bound_index(grid_[i].begin(), grid_[i].end(), r[i]) + 1; } -void RectilinearMesh::get_indices_from_bin(int bin, int* ijk) const -{ - ijk[0] = bin % shape_[0] + 1; - ijk[1] = (bin % (shape_[0] * shape_[1])) / shape_[0] + 1; - ijk[2] = bin / (shape_[0] * shape_[1]) + 1; -} - int RectilinearMesh::n_bins() const { return xt::prod(shape_)(); From bcc072e0a8774f2cda8e3708ec73cba6631615d4 Mon Sep 17 00:00:00 2001 From: aprilnovak Date: Thu, 15 Oct 2020 16:57:23 -0500 Subject: [PATCH 28/79] Move intersects method up to base class and combine the functionality using new get_index_in_direction function. Refs #1695 --- include/openmc/mesh.h | 40 ++- src/mesh.cpp | 608 +++++++++++++++++------------------------- 2 files changed, 264 insertions(+), 384 deletions(-) diff --git a/include/openmc/mesh.h b/include/openmc/mesh.h index 9f1b80c035..e619c43705 100644 --- a/include/openmc/mesh.h +++ b/include/openmc/mesh.h @@ -126,9 +126,17 @@ public: //! Get mesh index in a particular direction //! - //! \param[in] r Position to get index for + //! \param[in] r Coordinate to get index for //! \param[in] i Direction index - virtual int get_index_in_direction(Position r, int i) const = 0; + virtual int get_index_in_direction(double r, int i) const = 0; + + //! Check where a line segment intersects the mesh and if it intersects at all + // + //! \param[in,out] r0 In: starting position, out: intersection point + //! \param[in] r1 Ending position + //! \param[out] ijk Indices of the mesh bin containing the intersection point + //! \return Whether the line segment connecting r0 and r1 intersects mesh + virtual bool intersects(Position& r0, Position r1, int* ijk) const; //! Get a label for the mesh bin std::string bin_label(int bin) const override; @@ -137,6 +145,11 @@ public: xt::xtensor lower_left_; //!< Lower-left coordinates of mesh xt::xtensor upper_right_; //!< Upper-right coordinates of mesh xt::xtensor shape_; //!< Number of mesh elements in each dimension + +protected: + virtual bool intersects_1d(Position& r0, Position r1, int* ijk) const; + virtual bool intersects_2d(Position& r0, Position r1, int* ijk) const; + virtual bool intersects_3d(Position& r0, Position r1, int* ijk) const; }; //============================================================================== @@ -173,14 +186,6 @@ public: // New methods - //! Check where a line segment intersects the mesh and if it intersects at all - // - //! \param[in,out] r0 In: starting position, out: intersection point - //! \param[in] r1 Ending position - //! \param[out] ijk Indices of the mesh bin containing the intersection point - //! \return Whether the line segment connecting r0 and r1 intersects mesh - bool intersects(Position& r0, Position r1, int* ijk) const; - //! Count number of bank sites in each mesh bin / energy bin // //! \param[in] bank Array of bank sites @@ -193,11 +198,6 @@ public: double volume_frac_; //!< Volume fraction of each mesh element xt::xtensor width_; //!< Width of each mesh element - -private: - bool intersects_1d(Position& r0, Position r1, int* ijk) const; - bool intersects_2d(Position& r0, Position r1, int* ijk) const; - bool intersects_3d(Position& r0, Position r1, int* ijk) const; }; @@ -228,16 +228,6 @@ public: void to_hdf5(hid_t group) const override; - // New methods - - //! Check where a line segment intersects the mesh and if it intersects at all - // - //! \param[in,out] r0 In: starting position, out: intersection point - //! \param[in] r1 Ending position - //! \param[out] ijk Indices of the mesh bin containing the intersection point - //! \return Whether the line segment connecting r0 and r1 intersects mesh - bool intersects(Position& r0, Position r1, int* ijk) const; - private: std::vector> grid_; }; diff --git a/src/mesh.cpp b/src/mesh.cpp index 17a87c47df..c4158df233 100644 --- a/src/mesh.cpp +++ b/src/mesh.cpp @@ -106,7 +106,7 @@ void StructuredMesh::get_indices(Position r, int* ijk, bool* in_mesh) const { *in_mesh = true; for (int i = 0; i < n_dimension_; ++i) { - ijk[i] = get_index_in_direction(r, i); + ijk[i] = get_index_in_direction(r[i], i); if (ijk[i] < 1 || ijk[i] > shape_[i]) *in_mesh = false; } @@ -140,6 +140,250 @@ void StructuredMesh::get_indices_from_bin(int bin, int* ijk) const } } +bool StructuredMesh::intersects(Position& r0, Position r1, int* ijk) const +{ + switch(n_dimension_) { + case 1: + return intersects_1d(r0, r1, ijk); + case 2: + return intersects_2d(r0, r1, ijk); + case 3: + return intersects_3d(r0, r1, ijk); + default: + throw std::runtime_error{"Invalid number of mesh dimensions."}; + } +} + +bool StructuredMesh::intersects_1d(Position& r0, Position r1, int* ijk) const +{ + // Copy coordinates of starting point + double x0 = r0.x; + double y0 = r0.y; + double z0 = r0.z; + + // Copy coordinates of ending point + double x1 = r1.x; + double y1 = r1.y; + double z1 = r1.z; + + // Copy coordinates of mesh lower_left and upper_right + double xm0 = lower_left_[0]; + double xm1 = upper_right_[0]; + + double min_dist = INFTY; + + // Check if line intersects left surface -- calculate the intersection point + // (y,z) + if ((x0 < xm0 && x1 > xm0) || (x0 > xm0 && x1 < xm0)) { + double yi = y0 + (xm0 - x0) * (y1 - y0) / (x1 - x0); + double zi = z0 + (xm0 - x0) * (z1 - z0) / (x1 - x0); + if (check_intersection_point(xm0, x0, yi, yi, zi, zi, r0, min_dist)) { + ijk[0] = 1; + } + } + + // Check if line intersects right surface -- calculate the intersection point + // (y,z) + if ((x0 < xm1 && x1 > xm1) || (x0 > xm1 && x1 < xm1)) { + double yi = y0 + (xm1 - x0) * (y1 - y0) / (x1 - x0); + double zi = z0 + (xm1 - x0) * (z1 - z0) / (x1 - x0); + if (check_intersection_point(xm1, x0, yi, yi, zi, zi, r0, min_dist)) { + ijk[0] = shape_[0]; + } + } + + return min_dist < INFTY; +} + +bool StructuredMesh::intersects_2d(Position& r0, Position r1, int* ijk) const +{ + // Copy coordinates of starting point + double x0 = r0.x; + double y0 = r0.y; + double z0 = r0.z; + + // Copy coordinates of ending point + double x1 = r1.x; + double y1 = r1.y; + double z1 = r1.z; + + // Copy coordinates of mesh lower_left + double xm0 = lower_left_[0]; + double ym0 = lower_left_[1]; + + // Copy coordinates of mesh upper_right + double xm1 = upper_right_[0]; + double ym1 = upper_right_[1]; + + double min_dist = INFTY; + + // Check if line intersects left surface -- calculate the intersection point + // (y,z) + if ((x0 < xm0 && x1 > xm0) || (x0 > xm0 && x1 < xm0)) { + double yi = y0 + (xm0 - x0) * (y1 - y0) / (x1 - x0); + double zi = z0 + (xm0 - x0) * (z1 - z0) / (x1 - x0); + if (yi >= ym0 && yi < ym1) { + if (check_intersection_point(xm0, x0, yi, y0, zi, zi, r0, min_dist)) { + ijk[0] = 1; + ijk[1] = get_index_in_direction(yi, 1); + } + } + } + + // Check if line intersects back surface -- calculate the intersection point + // (x,z) + if ((y0 < ym0 && y1 > ym0) || (y0 > ym0 && y1 < ym0)) { + double xi = x0 + (ym0 - y0) * (x1 - x0) / (y1 - y0); + double zi = z0 + (ym0 - y0) * (z1 - z0) / (y1 - y0); + if (xi >= xm0 && xi < xm1) { + if (check_intersection_point(xi, x0, ym0, y0, zi, zi, r0, min_dist)) { + ijk[0] = get_index_in_direction(xi, 0); + ijk[1] = 1; + } + } + } + + // Check if line intersects right surface -- calculate the intersection point + // (y,z) + if ((x0 < xm1 && x1 > xm1) || (x0 > xm1 && x1 < xm1)) { + double yi = y0 + (xm1 - x0) * (y1 - y0) / (x1 - x0); + double zi = z0 + (xm1 - x0) * (z1 - z0) / (x1 - x0); + if (yi >= ym0 && yi < ym1) { + if (check_intersection_point(xm1, x0, yi, y0, zi, zi, r0, min_dist)) { + ijk[0] = shape_[0]; + ijk[1] = get_index_in_direction(yi, 1); + } + } + } + + // Check if line intersects front surface -- calculate the intersection point + // (x,z) + if ((y0 < ym1 && y1 > ym1) || (y0 > ym1 && y1 < ym1)) { + double xi = x0 + (ym1 - y0) * (x1 - x0) / (y1 - y0); + double zi = z0 + (ym1 - y0) * (z1 - z0) / (y1 - y0); + if (xi >= xm0 && xi < xm1) { + if (check_intersection_point(xi, x0, ym1, y0, zi, zi, r0, min_dist)) { + ijk[0] = get_index_in_direction(xi, 0); + ijk[1] = shape_[1]; + } + } + } + + return min_dist < INFTY; +} + +bool StructuredMesh::intersects_3d(Position& r0, Position r1, int* ijk) const +{ + // Copy coordinates of starting point + double x0 = r0.x; + double y0 = r0.y; + double z0 = r0.z; + + // Copy coordinates of ending point + double x1 = r1.x; + double y1 = r1.y; + double z1 = r1.z; + + // Copy coordinates of mesh lower_left + double xm0 = lower_left_[0]; + double ym0 = lower_left_[1]; + double zm0 = lower_left_[2]; + + // Copy coordinates of mesh upper_right + double xm1 = upper_right_[0]; + double ym1 = upper_right_[1]; + double zm1 = upper_right_[2]; + + double min_dist = INFTY; + + // Check if line intersects left surface -- calculate the intersection point + // (y,z) + if ((x0 < xm0 && x1 > xm0) || (x0 > xm0 && x1 < xm0)) { + double yi = y0 + (xm0 - x0) * (y1 - y0) / (x1 - x0); + double zi = z0 + (xm0 - x0) * (z1 - z0) / (x1 - x0); + if (yi >= ym0 && yi < ym1 && zi >= zm0 && zi < zm1) { + if (check_intersection_point(xm0, x0, yi, y0, zi, z0, r0, min_dist)) { + ijk[0] = 1; + ijk[1] = get_index_in_direction(yi, 1); + ijk[2] = get_index_in_direction(zi, 2); + } + } + } + + // Check if line intersects back surface -- calculate the intersection point + // (x,z) + if ((y0 < ym0 && y1 > ym0) || (y0 > ym0 && y1 < ym0)) { + double xi = x0 + (ym0 - y0) * (x1 - x0) / (y1 - y0); + double zi = z0 + (ym0 - y0) * (z1 - z0) / (y1 - y0); + if (xi >= xm0 && xi < xm1 && zi >= zm0 && zi < zm1) { + if (check_intersection_point(xi, x0, ym0, y0, zi, z0, r0, min_dist)) { + ijk[0] = get_index_in_direction(xi, 0); + ijk[1] = 1; + ijk[2] = get_index_in_direction(zi, 2); + } + } + } + + // Check if line intersects bottom surface -- calculate the intersection + // point (x,y) + if ((z0 < zm0 && z1 > zm0) || (z0 > zm0 && z1 < zm0)) { + double xi = x0 + (zm0 - z0) * (x1 - x0) / (z1 - z0); + double yi = y0 + (zm0 - z0) * (y1 - y0) / (z1 - z0); + if (xi >= xm0 && xi < xm1 && yi >= ym0 && yi < ym1) { + if (check_intersection_point(xi, x0, yi, y0, zm0, z0, r0, min_dist)) { + ijk[0] = get_index_in_direction(xi, 0); + ijk[1] = get_index_in_direction(yi, 1); + ijk[2] = 1; + } + } + } + + // Check if line intersects right surface -- calculate the intersection point + // (y,z) + if ((x0 < xm1 && x1 > xm1) || (x0 > xm1 && x1 < xm1)) { + double yi = y0 + (xm1 - x0) * (y1 - y0) / (x1 - x0); + double zi = z0 + (xm1 - x0) * (z1 - z0) / (x1 - x0); + if (yi >= ym0 && yi < ym1 && zi >= zm0 && zi < zm1) { + if (check_intersection_point(xm1, x0, yi, y0, zi, z0, r0, min_dist)) { + ijk[0] = shape_[0]; + ijk[1] = get_index_in_direction(yi, 1); + ijk[2] = get_index_in_direction(zi, 2); + } + } + } + + // Check if line intersects front surface -- calculate the intersection point + // (x,z) + if ((y0 < ym1 && y1 > ym1) || (y0 > ym1 && y1 < ym1)) { + double xi = x0 + (ym1 - y0) * (x1 - x0) / (y1 - y0); + double zi = z0 + (ym1 - y0) * (z1 - z0) / (y1 - y0); + if (xi >= xm0 && xi < xm1 && zi >= zm0 && zi < zm1) { + if (check_intersection_point(xi, x0, ym1, y0, zi, z0, r0, min_dist)) { + ijk[0] = get_index_in_direction(xi, 0); + ijk[1] = shape_[1]; + ijk[2] = get_index_in_direction(zi, 2); + } + } + } + + // Check if line intersects top surface -- calculate the intersection point + // (x,y) + if ((z0 < zm1 && z1 > zm1) || (z0 > zm1 && z1 < zm1)) { + double xi = x0 + (zm1 - z0) * (x1 - x0) / (z1 - z0); + double yi = y0 + (zm1 - z0) * (y1 - y0) / (z1 - z0); + if (xi >= xm0 && xi < xm1 && yi >= ym0 && yi < ym1) { + if (check_intersection_point(xi, x0, yi, y0, zm1, z0, r0, min_dist)) { + ijk[0] = get_index_in_direction(xi, 0); + ijk[1] = get_index_in_direction(yi, 1); + ijk[2] = shape_[2]; + } + } + } + + return min_dist < INFTY; +} + + //============================================================================== // RegularMesh implementation //============================================================================== @@ -237,9 +481,9 @@ int RegularMesh::get_bin(Position r) const return get_bin_from_indices(ijk.data()); } -int RegularMesh::get_index_in_direction(Position r, int i) const +int RegularMesh::get_index_in_direction(double r, int i) const { - return std::ceil((r[i] - lower_left_[i]) / width_[i]); + return std::ceil((r - lower_left_[i]) / width_[i]); } int RegularMesh::n_bins() const @@ -254,249 +498,6 @@ int RegularMesh::n_surface_bins() const return 4 * n_dimension_ * n_bins(); } -bool RegularMesh::intersects(Position& r0, Position r1, int* ijk) const -{ - switch(n_dimension_) { - case 1: - return intersects_1d(r0, r1, ijk); - case 2: - return intersects_2d(r0, r1, ijk); - case 3: - return intersects_3d(r0, r1, ijk); - default: - throw std::runtime_error{"Invalid number of mesh dimensions."}; - } -} - -bool RegularMesh::intersects_1d(Position& r0, Position r1, int* ijk) const -{ - // Copy coordinates of starting point - double x0 = r0.x; - double y0 = r0.y; - double z0 = r0.z; - - // Copy coordinates of ending point - double x1 = r1.x; - double y1 = r1.y; - double z1 = r1.z; - - // Copy coordinates of mesh lower_left and upper_right - double xm0 = lower_left_[0]; - double xm1 = upper_right_[0]; - - double min_dist = INFTY; - - // Check if line intersects left surface -- calculate the intersection point - // (y,z) - if ((x0 < xm0 && x1 > xm0) || (x0 > xm0 && x1 < xm0)) { - double yi = y0 + (xm0 - x0) * (y1 - y0) / (x1 - x0); - double zi = z0 + (xm0 - x0) * (z1 - z0) / (x1 - x0); - if (check_intersection_point(xm0, x0, yi, yi, zi, zi, r0, min_dist)) { - ijk[0] = 1; - } - } - - // Check if line intersects right surface -- calculate the intersection point - // (y,z) - if ((x0 < xm1 && x1 > xm1) || (x0 > xm1 && x1 < xm1)) { - double yi = y0 + (xm1 - x0) * (y1 - y0) / (x1 - x0); - double zi = z0 + (xm1 - x0) * (z1 - z0) / (x1 - x0); - if (check_intersection_point(xm1, x0, yi, yi, zi, zi, r0, min_dist)) { - ijk[0] = shape_[0]; - } - } - - return min_dist < INFTY; -} - -bool RegularMesh::intersects_2d(Position& r0, Position r1, int* ijk) const -{ - // Copy coordinates of starting point - double x0 = r0.x; - double y0 = r0.y; - double z0 = r0.z; - - // Copy coordinates of ending point - double x1 = r1.x; - double y1 = r1.y; - double z1 = r1.z; - - // Copy coordinates of mesh lower_left - double xm0 = lower_left_[0]; - double ym0 = lower_left_[1]; - - // Copy coordinates of mesh upper_right - double xm1 = upper_right_[0]; - double ym1 = upper_right_[1]; - - double min_dist = INFTY; - - // Check if line intersects left surface -- calculate the intersection point - // (y,z) - if ((x0 < xm0 && x1 > xm0) || (x0 > xm0 && x1 < xm0)) { - double yi = y0 + (xm0 - x0) * (y1 - y0) / (x1 - x0); - double zi = z0 + (xm0 - x0) * (z1 - z0) / (x1 - x0); - if (yi >= ym0 && yi < ym1) { - if (check_intersection_point(xm0, x0, yi, y0, zi, zi, r0, min_dist)) { - ijk[0] = 1; - ijk[1] = std::ceil((yi - lower_left_[1]) / width_[1]); - } - } - } - - // Check if line intersects back surface -- calculate the intersection point - // (x,z) - if ((y0 < ym0 && y1 > ym0) || (y0 > ym0 && y1 < ym0)) { - double xi = x0 + (ym0 - y0) * (x1 - x0) / (y1 - y0); - double zi = z0 + (ym0 - y0) * (z1 - z0) / (y1 - y0); - if (xi >= xm0 && xi < xm1) { - if (check_intersection_point(xi, x0, ym0, y0, zi, zi, r0, min_dist)) { - ijk[0] = std::ceil((xi - lower_left_[0]) / width_[0]); - ijk[1] = 1; - } - } - } - - // Check if line intersects right surface -- calculate the intersection point - // (y,z) - if ((x0 < xm1 && x1 > xm1) || (x0 > xm1 && x1 < xm1)) { - double yi = y0 + (xm1 - x0) * (y1 - y0) / (x1 - x0); - double zi = z0 + (xm1 - x0) * (z1 - z0) / (x1 - x0); - if (yi >= ym0 && yi < ym1) { - if (check_intersection_point(xm1, x0, yi, y0, zi, zi, r0, min_dist)) { - ijk[0] = shape_[0]; - ijk[1] = std::ceil((yi - lower_left_[1]) / width_[1]); - } - } - } - - // Check if line intersects front surface -- calculate the intersection point - // (x,z) - if ((y0 < ym1 && y1 > ym1) || (y0 > ym1 && y1 < ym1)) { - double xi = x0 + (ym1 - y0) * (x1 - x0) / (y1 - y0); - double zi = z0 + (ym1 - y0) * (z1 - z0) / (y1 - y0); - if (xi >= xm0 && xi < xm1) { - if (check_intersection_point(xi, x0, ym1, y0, zi, zi, r0, min_dist)) { - ijk[0] = std::ceil((xi - lower_left_[0]) / width_[0]); - ijk[1] = shape_[1]; - } - } - } - - return min_dist < INFTY; -} - -bool RegularMesh::intersects_3d(Position& r0, Position r1, int* ijk) const -{ - // Copy coordinates of starting point - double x0 = r0.x; - double y0 = r0.y; - double z0 = r0.z; - - // Copy coordinates of ending point - double x1 = r1.x; - double y1 = r1.y; - double z1 = r1.z; - - // Copy coordinates of mesh lower_left - double xm0 = lower_left_[0]; - double ym0 = lower_left_[1]; - double zm0 = lower_left_[2]; - - // Copy coordinates of mesh upper_right - double xm1 = upper_right_[0]; - double ym1 = upper_right_[1]; - double zm1 = upper_right_[2]; - - double min_dist = INFTY; - - // Check if line intersects left surface -- calculate the intersection point - // (y,z) - if ((x0 < xm0 && x1 > xm0) || (x0 > xm0 && x1 < xm0)) { - double yi = y0 + (xm0 - x0) * (y1 - y0) / (x1 - x0); - double zi = z0 + (xm0 - x0) * (z1 - z0) / (x1 - x0); - if (yi >= ym0 && yi < ym1 && zi >= zm0 && zi < zm1) { - if (check_intersection_point(xm0, x0, yi, y0, zi, z0, r0, min_dist)) { - ijk[0] = 1; - ijk[1] = std::ceil((yi - lower_left_[1]) / width_[1]); - ijk[2] = std::ceil((zi - lower_left_[2]) / width_[2]); - } - } - } - - // Check if line intersects back surface -- calculate the intersection point - // (x,z) - if ((y0 < ym0 && y1 > ym0) || (y0 > ym0 && y1 < ym0)) { - double xi = x0 + (ym0 - y0) * (x1 - x0) / (y1 - y0); - double zi = z0 + (ym0 - y0) * (z1 - z0) / (y1 - y0); - if (xi >= xm0 && xi < xm1 && zi >= zm0 && zi < zm1) { - if (check_intersection_point(xi, x0, ym0, y0, zi, z0, r0, min_dist)) { - ijk[0] = std::ceil((xi - lower_left_[0]) / width_[0]); - ijk[1] = 1; - ijk[2] = std::ceil((zi - lower_left_[2]) / width_[2]); - } - } - } - - // Check if line intersects bottom surface -- calculate the intersection - // point (x,y) - if ((z0 < zm0 && z1 > zm0) || (z0 > zm0 && z1 < zm0)) { - double xi = x0 + (zm0 - z0) * (x1 - x0) / (z1 - z0); - double yi = y0 + (zm0 - z0) * (y1 - y0) / (z1 - z0); - if (xi >= xm0 && xi < xm1 && yi >= ym0 && yi < ym1) { - if (check_intersection_point(xi, x0, yi, y0, zm0, z0, r0, min_dist)) { - ijk[0] = std::ceil((xi - lower_left_[0]) / width_[0]); - ijk[1] = std::ceil((yi - lower_left_[1]) / width_[1]); - ijk[2] = 1; - } - } - } - - // Check if line intersects right surface -- calculate the intersection point - // (y,z) - if ((x0 < xm1 && x1 > xm1) || (x0 > xm1 && x1 < xm1)) { - double yi = y0 + (xm1 - x0) * (y1 - y0) / (x1 - x0); - double zi = z0 + (xm1 - x0) * (z1 - z0) / (x1 - x0); - if (yi >= ym0 && yi < ym1 && zi >= zm0 && zi < zm1) { - if (check_intersection_point(xm1, x0, yi, y0, zi, z0, r0, min_dist)) { - ijk[0] = shape_[0]; - ijk[1] = std::ceil((yi - lower_left_[1]) / width_[1]); - ijk[2] = std::ceil((zi - lower_left_[2]) / width_[2]); - } - } - } - - // Check if line intersects front surface -- calculate the intersection point - // (x,z) - if ((y0 < ym1 && y1 > ym1) || (y0 > ym1 && y1 < ym1)) { - double xi = x0 + (ym1 - y0) * (x1 - x0) / (y1 - y0); - double zi = z0 + (ym1 - y0) * (z1 - z0) / (y1 - y0); - if (xi >= xm0 && xi < xm1 && zi >= zm0 && zi < zm1) { - if (check_intersection_point(xi, x0, ym1, y0, zi, z0, r0, min_dist)) { - ijk[0] = std::ceil((xi - lower_left_[0]) / width_[0]); - ijk[1] = shape_[1]; - ijk[2] = std::ceil((zi - lower_left_[2]) / width_[2]); - } - } - } - - // Check if line intersects top surface -- calculate the intersection point - // (x,y) - if ((z0 < zm1 && z1 > zm1) || (z0 > zm1 && z1 < zm1)) { - double xi = x0 + (zm1 - z0) * (x1 - x0) / (z1 - z0); - double yi = y0 + (zm1 - z0) * (y1 - y0) / (z1 - z0); - if (xi >= xm0 && xi < xm1 && yi >= ym0 && yi < ym1) { - if (check_intersection_point(xi, x0, yi, y0, zm1, z0, r0, min_dist)) { - ijk[0] = std::ceil((xi - lower_left_[0]) / width_[0]); - ijk[1] = std::ceil((yi - lower_left_[1]) / width_[1]); - ijk[2] = shape_[2]; - } - } - } - - return min_dist < INFTY; -} - void RegularMesh::bins_crossed(const Particle& p, std::vector& bins, std::vector& lengths) const { @@ -1173,9 +1174,9 @@ int RectilinearMesh::get_bin(Position r) const return get_bin_from_indices(ijk); } -int RectilinearMesh::get_index_in_direction(Position r, int i) const +int RectilinearMesh::get_index_in_direction(double r, int i) const { - return lower_bound_index(grid_[i].begin(), grid_[i].end(), r[i]) + 1; + return lower_bound_index(grid_[i].begin(), grid_[i].end(), r) + 1; } int RectilinearMesh::n_bins() const @@ -1230,117 +1231,6 @@ void RectilinearMesh::to_hdf5(hid_t group) const close_group(mesh_group); } -bool RectilinearMesh::intersects(Position& r0, Position r1, int* ijk) const -{ - // Copy coordinates of starting point - double x0 = r0.x; - double y0 = r0.y; - double z0 = r0.z; - - // Copy coordinates of ending point - double x1 = r1.x; - double y1 = r1.y; - double z1 = r1.z; - - // Copy coordinates of mesh lower_left - double xm0 = grid_[0].front(); - double ym0 = grid_[1].front(); - double zm0 = grid_[2].front(); - - // Copy coordinates of mesh upper_right - double xm1 = grid_[0].back(); - double ym1 = grid_[1].back(); - double zm1 = grid_[2].back(); - - double min_dist = INFTY; - - // Check if line intersects left surface -- calculate the intersection point - // (y,z) - if ((x0 < xm0 && x1 > xm0) || (x0 > xm0 && x1 < xm0)) { - double yi = y0 + (xm0 - x0) * (y1 - y0) / (x1 - x0); - double zi = z0 + (xm0 - x0) * (z1 - z0) / (x1 - x0); - if (yi >= ym0 && yi < ym1 && zi >= zm0 && zi < zm1) { - if (check_intersection_point(xm0, x0, yi, y0, zi, z0, r0, min_dist)) { - ijk[0] = 1; - ijk[1] = lower_bound_index(grid_[1].begin(), grid_[1].end(), yi) + 1; - ijk[2] = lower_bound_index(grid_[2].begin(), grid_[2].end(), zi) + 1; - } - } - } - - // Check if line intersects back surface -- calculate the intersection point - // (x,z) - if ((y0 < ym0 && y1 > ym0) || (y0 > ym0 && y1 < ym0)) { - double xi = x0 + (ym0 - y0) * (x1 - x0) / (y1 - y0); - double zi = z0 + (ym0 - y0) * (z1 - z0) / (y1 - y0); - if (xi >= xm0 && xi < xm1 && zi >= zm0 && zi < zm1) { - if (check_intersection_point(xi, x0, ym0, y0, zi, z0, r0, min_dist)) { - ijk[0] = lower_bound_index(grid_[0].begin(), grid_[0].end(), xi) + 1; - ijk[1] = 1; - ijk[2] = lower_bound_index(grid_[2].begin(), grid_[2].end(), zi) + 1; - } - } - } - - // Check if line intersects bottom surface -- calculate the intersection - // point (x,y) - if ((z0 < zm0 && z1 > zm0) || (z0 > zm0 && z1 < zm0)) { - double xi = x0 + (zm0 - z0) * (x1 - x0) / (z1 - z0); - double yi = y0 + (zm0 - z0) * (y1 - y0) / (z1 - z0); - if (xi >= xm0 && xi < xm1 && yi >= ym0 && yi < ym1) { - if (check_intersection_point(xi, x0, yi, y0, zm0, z0, r0, min_dist)) { - ijk[0] = lower_bound_index(grid_[0].begin(), grid_[0].end(), xi) + 1; - ijk[1] = lower_bound_index(grid_[1].begin(), grid_[1].end(), yi) + 1; - ijk[2] = 1; - } - } - } - - // Check if line intersects right surface -- calculate the intersection point - // (y,z) - if ((x0 < xm1 && x1 > xm1) || (x0 > xm1 && x1 < xm1)) { - double yi = y0 + (xm1 - x0) * (y1 - y0) / (x1 - x0); - double zi = z0 + (xm1 - x0) * (z1 - z0) / (x1 - x0); - if (yi >= ym0 && yi < ym1 && zi >= zm0 && zi < zm1) { - if (check_intersection_point(xm1, x0, yi, y0, zi, z0, r0, min_dist)) { - ijk[0] = shape_[0]; - ijk[1] = lower_bound_index(grid_[1].begin(), grid_[1].end(), yi) + 1; - ijk[2] = lower_bound_index(grid_[2].begin(), grid_[2].end(), zi) + 1; - } - } - } - - // Check if line intersects front surface -- calculate the intersection point - // (x,z) - if ((y0 < ym1 && y1 > ym1) || (y0 > ym1 && y1 < ym1)) { - double xi = x0 + (ym1 - y0) * (x1 - x0) / (y1 - y0); - double zi = z0 + (ym1 - y0) * (z1 - z0) / (y1 - y0); - if (xi >= xm0 && xi < xm1 && zi >= zm0 && zi < zm1) { - if (check_intersection_point(xi, x0, ym1, y0, zi, z0, r0, min_dist)) { - ijk[0] = lower_bound_index(grid_[0].begin(), grid_[0].end(), xi) + 1; - ijk[1] = shape_[1]; - ijk[2] = lower_bound_index(grid_[2].begin(), grid_[2].end(), zi) + 1; - } - } - } - - // Check if line intersects top surface -- calculate the intersection point - // (x,y) - if ((z0 < zm1 && z1 > zm1) || (z0 > zm1 && z1 < zm1)) { - double xi = x0 + (zm1 - z0) * (x1 - x0) / (z1 - z0); - double yi = y0 + (zm1 - z0) * (y1 - y0) / (z1 - z0); - if (xi >= xm0 && xi < xm1 && yi >= ym0 && yi < ym1) { - if (check_intersection_point(xi, x0, yi, y0, zm1, z0, r0, min_dist)) { - ijk[0] = lower_bound_index(grid_[0].begin(), grid_[0].end(), xi) + 1; - ijk[1] = lower_bound_index(grid_[1].begin(), grid_[1].end(), yi) + 1; - ijk[2] = shape_[2]; - } - } - } - - return min_dist < INFTY; -} - //============================================================================== // Helper functions for the C API //============================================================================== From 9a36ea405aeeed940152882199219cdf6a35207c Mon Sep 17 00:00:00 2001 From: aprilnovak Date: Thu, 15 Oct 2020 17:14:32 -0500 Subject: [PATCH 29/79] Move get_bin implementation up to StructuredMesh base class. Refs #1695 --- include/openmc/mesh.h | 10 ++++------ src/mesh.cpp | 36 ++++++++++++------------------------ 2 files changed, 16 insertions(+), 30 deletions(-) diff --git a/include/openmc/mesh.h b/include/openmc/mesh.h index e619c43705..98f0e7a83c 100644 --- a/include/openmc/mesh.h +++ b/include/openmc/mesh.h @@ -105,6 +105,8 @@ public: StructuredMesh(pugi::xml_node node) : Mesh {node} {}; virtual ~StructuredMesh() = default; + int get_bin(Position r) const override; + //! Get bin given mesh indices // //! \param[in] Array of mesh indices @@ -171,9 +173,7 @@ public: void surface_bins_crossed(const Particle& p, std::vector& bins) const override; - int get_bin(Position r) const override; - - int get_index_in_direction(Position r, int i) const override; + int get_index_in_direction(double r, int i) const override; int n_bins() const override; @@ -215,9 +215,7 @@ public: void surface_bins_crossed(const Particle& p, std::vector& bins) const override; - int get_bin(Position r) const override; - - int get_index_in_direction(Position r, int i) const override; + int get_index_in_direction(double r, int i) const override; int n_bins() const override; diff --git a/src/mesh.cpp b/src/mesh.cpp index c4158df233..68a116e3af 100644 --- a/src/mesh.cpp +++ b/src/mesh.cpp @@ -140,6 +140,18 @@ void StructuredMesh::get_indices_from_bin(int bin, int* ijk) const } } +int StructuredMesh::get_bin(Position r) const +{ + // Determine indices + std::vector ijk(n_dimension_); + bool in_mesh; + get_indices(r, ijk.data(), &in_mesh); + if (!in_mesh) return -1; + + // Convert indices to bin + return get_bin_from_indices(ijk.data()); +} + bool StructuredMesh::intersects(Position& r0, Position r1, int* ijk) const { switch(n_dimension_) { @@ -469,18 +481,6 @@ RegularMesh::RegularMesh(pugi::xml_node node) volume_frac_ = 1.0/xt::prod(shape_)(); } -int RegularMesh::get_bin(Position r) const -{ - // Determine indices - std::vector ijk(n_dimension_); - bool in_mesh; - get_indices(r, ijk.data(), &in_mesh); - if (!in_mesh) return -1; - - // Convert indices to bin - return get_bin_from_indices(ijk.data()); -} - int RegularMesh::get_index_in_direction(double r, int i) const { return std::ceil((r - lower_left_[i]) / width_[i]); @@ -1162,18 +1162,6 @@ void RectilinearMesh::surface_bins_crossed(const Particle& p, } } -int RectilinearMesh::get_bin(Position r) const -{ - // Determine indices - int ijk[3]; - bool in_mesh; - get_indices(r, ijk, &in_mesh); - if (!in_mesh) return -1; - - // Convert indices to bin - return get_bin_from_indices(ijk); -} - int RectilinearMesh::get_index_in_direction(double r, int i) const { return lower_bound_index(grid_[i].begin(), grid_[i].end(), r) + 1; From 008a73fa361308987e7141dcdb98be327bbc5b2d Mon Sep 17 00:00:00 2001 From: aprilnovak Date: Thu, 15 Oct 2020 17:18:32 -0500 Subject: [PATCH 30/79] Move n_bins and n_surface_bins implementations to StructuredMesh base class. Refs #1695 --- include/openmc/mesh.h | 12 ++++-------- src/mesh.cpp | 32 ++++++++++---------------------- 2 files changed, 14 insertions(+), 30 deletions(-) diff --git a/include/openmc/mesh.h b/include/openmc/mesh.h index 98f0e7a83c..f3f84ac6b7 100644 --- a/include/openmc/mesh.h +++ b/include/openmc/mesh.h @@ -107,6 +107,10 @@ public: int get_bin(Position r) const override; + int n_bins() const override; + + int n_surface_bins() const override; + //! Get bin given mesh indices // //! \param[in] Array of mesh indices @@ -175,10 +179,6 @@ public: int get_index_in_direction(double r, int i) const override; - int n_bins() const override; - - int n_surface_bins() const override; - std::pair, std::vector> plot(Position plot_ll, Position plot_ur) const override; @@ -217,10 +217,6 @@ public: int get_index_in_direction(double r, int i) const override; - int n_bins() const override; - - int n_surface_bins() const override; - std::pair, std::vector> plot(Position plot_ll, Position plot_ur) const override; diff --git a/src/mesh.cpp b/src/mesh.cpp index 68a116e3af..ca7eb53ab9 100644 --- a/src/mesh.cpp +++ b/src/mesh.cpp @@ -152,6 +152,16 @@ int StructuredMesh::get_bin(Position r) const return get_bin_from_indices(ijk.data()); } +int StructuredMesh::n_bins() const +{ + return xt::prod(shape_)(); +} + +int StructuredMesh::n_surface_bins() const +{ + return 4 * n_dimension_ * n_bins(); +} + bool StructuredMesh::intersects(Position& r0, Position r1, int* ijk) const { switch(n_dimension_) { @@ -486,18 +496,6 @@ int RegularMesh::get_index_in_direction(double r, int i) const return std::ceil((r - lower_left_[i]) / width_[i]); } -int RegularMesh::n_bins() const -{ - int n_bins = 1; - for (auto dim : shape_) n_bins *= dim; - return n_bins; -} - -int RegularMesh::n_surface_bins() const -{ - return 4 * n_dimension_ * n_bins(); -} - void RegularMesh::bins_crossed(const Particle& p, std::vector& bins, std::vector& lengths) const { @@ -1167,16 +1165,6 @@ int RectilinearMesh::get_index_in_direction(double r, int i) const return lower_bound_index(grid_[i].begin(), grid_[i].end(), r) + 1; } -int RectilinearMesh::n_bins() const -{ - return xt::prod(shape_)(); -} - -int RectilinearMesh::n_surface_bins() const -{ - return 4 * n_dimension_ * n_bins(); -} - std::pair, std::vector> RectilinearMesh::plot(Position plot_ll, Position plot_ur) const { From 1207c901be203110b6bc6b0a5b8b791e10a0a1b9 Mon Sep 17 00:00:00 2001 From: aprilnovak Date: Thu, 15 Oct 2020 18:01:02 -0500 Subject: [PATCH 31/79] Move bins_crossed implementation into StructuredMesh base class. Refs #1695 --- include/openmc/mesh.h | 29 +++- src/mesh.cpp | 318 ++++++++++++++++-------------------------- 2 files changed, 141 insertions(+), 206 deletions(-) diff --git a/include/openmc/mesh.h b/include/openmc/mesh.h index f3f84ac6b7..5a8367b8bb 100644 --- a/include/openmc/mesh.h +++ b/include/openmc/mesh.h @@ -111,6 +111,9 @@ public: int n_surface_bins() const override; + void bins_crossed(const Particle& p, std::vector& bins, + std::vector& lengths) const override; + //! Get bin given mesh indices // //! \param[in] Array of mesh indices @@ -144,6 +147,18 @@ public: //! \return Whether the line segment connecting r0 and r1 intersects mesh virtual bool intersects(Position& r0, Position r1, int* ijk) const; + //! Get the coordinate for the mesh grid boundary in the positive direction + //! + //! \param[in] ijk Array of mesh indices + //! \param[in] i Direction index + virtual double positive_grid_boundary(int* ijk, int i) const = 0; + + //! Get the coordinate for the mesh grid boundary in the negative direction + //! + //! \param[in] ijk Array of mesh indices + //! \param[in] i Direction index + virtual double negative_grid_boundary(int* ijk, int i) const = 0; + //! Get a label for the mesh bin std::string bin_label(int bin) const override; @@ -171,14 +186,15 @@ public: // Overriden methods - void bins_crossed(const Particle& p, std::vector& bins, - std::vector& lengths) const override; - void surface_bins_crossed(const Particle& p, std::vector& bins) const override; int get_index_in_direction(double r, int i) const override; + double positive_grid_boundary(int* ijk, int i) const override; + + double negative_grid_boundary(int* ijk, int i) const override; + std::pair, std::vector> plot(Position plot_ll, Position plot_ur) const override; @@ -209,14 +225,15 @@ public: // Overriden methods - void bins_crossed(const Particle& p, std::vector& bins, - std::vector& lengths) const override; - void surface_bins_crossed(const Particle& p, std::vector& bins) const override; int get_index_in_direction(double r, int i) const override; + double positive_grid_boundary(int* ijk, int i) const override; + + double negative_grid_boundary(int* ijk, int i) const override; + std::pair, std::vector> plot(Position plot_ll, Position plot_ur) const override; diff --git a/src/mesh.cpp b/src/mesh.cpp index ca7eb53ab9..d3b671263a 100644 --- a/src/mesh.cpp +++ b/src/mesh.cpp @@ -405,99 +405,7 @@ bool StructuredMesh::intersects_3d(Position& r0, Position r1, int* ijk) const return min_dist < INFTY; } - -//============================================================================== -// RegularMesh implementation -//============================================================================== - -RegularMesh::RegularMesh(pugi::xml_node node) - : StructuredMesh {node} -{ - // Determine number of dimensions for mesh - if (check_for_node(node, "dimension")) { - shape_ = get_node_xarray(node, "dimension"); - int n = n_dimension_ = shape_.size(); - if (n != 1 && n != 2 && n != 3) { - fatal_error("Mesh must be one, two, or three dimensions."); - } - - // Check that dimensions are all greater than zero - if (xt::any(shape_ <= 0)) { - fatal_error("All entries on the element for a tally " - "mesh must be positive."); - } - } else { - fatal_error("Must specify on a mesh."); - } - - // Check for lower-left coordinates - if (check_for_node(node, "lower_left")) { - // Read mesh lower-left corner location - lower_left_ = get_node_xarray(node, "lower_left"); - - // Make sure lower_left and dimension match - if (n_dimension_ != lower_left_.size()) { - fatal_error("Number of entries on must be the same " - "as the number of entries on ."); - } - } else { - fatal_error("Must specify on a mesh."); - } - - if (check_for_node(node, "width")) { - // Make sure both upper-right or width were specified - if (check_for_node(node, "upper_right")) { - fatal_error("Cannot specify both and on a mesh."); - } - - width_ = get_node_xarray(node, "width"); - - // Check to ensure width has same dimensions - if (n_dimension_ != width_.size()) { - fatal_error("Number of entries on must be the same as " - "the number of entries on ."); - } - - // Check for negative widths - if (xt::any(width_ < 0.0)) { - fatal_error("Cannot have a negative on a tally mesh."); - } - - // Set width and upper right coordinate - upper_right_ = xt::eval(lower_left_ + shape_ * width_); - - } else if (check_for_node(node, "upper_right")) { - upper_right_ = get_node_xarray(node, "upper_right"); - - // Check to ensure upper right has same dimensions - if (n_dimension_ != upper_right_.size()) { - fatal_error("Number of entries on must be the " - "same as the number of entries on ."); - } - - // Check that upper-right is above lower-left - if (xt::any(upper_right_ < lower_left_)) { - fatal_error("The coordinates must be greater than " - "the coordinates on a tally mesh."); - } - - // Set width - width_ = xt::eval((upper_right_ - lower_left_) / shape_); - } else { - fatal_error("Must specify either and on a mesh."); - } - - // Set volume fraction - volume_frac_ = 1.0/xt::prod(shape_)(); -} - -int RegularMesh::get_index_in_direction(double r, int i) const -{ - return std::ceil((r - lower_left_[i]) / width_[i]); -} - -void RegularMesh::bins_crossed(const Particle& p, std::vector& bins, - std::vector& lengths) const +void StructuredMesh::bins_crossed(const Particle& p, std::vector& bins, { // ======================================================================== // Determine where the track intersects the mesh and if it intersects at all. @@ -565,10 +473,10 @@ void RegularMesh::bins_crossed(const Particle& p, std::vector& bins, if (std::fabs(u[k]) < FP_PRECISION) { d[k] = INFTY; } else if (u[k] > 0) { - double xyz_cross = lower_left_[k] + ijk0[k] * width_[k]; + double xyz_cross = positive_grid_boundary(ijk0.data(), k); d[k] = (xyz_cross - r0[k]) / u[k]; } else { - double xyz_cross = lower_left_[k] + (ijk0[k] - 1) * width_[k]; + double xyz_cross = negative_grid_boundary(ijk0.data(), k); d[k] = (xyz_cross - r0[k]) / u[k]; } } @@ -602,6 +510,111 @@ void RegularMesh::bins_crossed(const Particle& p, std::vector& bins, } } + +//============================================================================== +// RegularMesh implementation +//============================================================================== + +RegularMesh::RegularMesh(pugi::xml_node node) + : StructuredMesh {node} +{ + // Determine number of dimensions for mesh + if (check_for_node(node, "dimension")) { + shape_ = get_node_xarray(node, "dimension"); + int n = n_dimension_ = shape_.size(); + if (n != 1 && n != 2 && n != 3) { + fatal_error("Mesh must be one, two, or three dimensions."); + } + + // Check that dimensions are all greater than zero + if (xt::any(shape_ <= 0)) { + fatal_error("All entries on the element for a tally " + "mesh must be positive."); + } + } + + // Check for lower-left coordinates + if (check_for_node(node, "lower_left")) { + // Read mesh lower-left corner location + lower_left_ = get_node_xarray(node, "lower_left"); + } else { + fatal_error("Must specify on a mesh."); + } + + if (check_for_node(node, "width")) { + // Make sure both upper-right or width were specified + if (check_for_node(node, "upper_right")) { + fatal_error("Cannot specify both and on a mesh."); + } + + width_ = get_node_xarray(node, "width"); + + // Check to ensure width has same dimensions + auto n = width_.size(); + if (n != lower_left_.size()) { + fatal_error("Number of entries on must be the same as " + "the number of entries on ."); + } + + // Check for negative widths + if (xt::any(width_ < 0.0)) { + fatal_error("Cannot have a negative on a tally mesh."); + } + + // Set width and upper right coordinate + upper_right_ = xt::eval(lower_left_ + shape_ * width_); + + } else if (check_for_node(node, "upper_right")) { + upper_right_ = get_node_xarray(node, "upper_right"); + + // Check to ensure width has same dimensions + auto n = upper_right_.size(); + if (n != lower_left_.size()) { + fatal_error("Number of entries on must be the " + "same as the number of entries on ."); + } + + // Check that upper-right is above lower-left + if (xt::any(upper_right_ < lower_left_)) { + fatal_error("The coordinates must be greater than " + "the coordinates on a tally mesh."); + } + + // Set width + if (shape_.size() > 0) { + width_ = xt::eval((upper_right_ - lower_left_) / shape_); + } + } else { + fatal_error("Must specify either and on a mesh."); + } + + // Make sure lower_left and dimension match + if (shape_.size() > 0) { + if (shape_.size() != lower_left_.size()) { + fatal_error("Number of entries on must be the same " + "as the number of entries on ."); + } + + // Set volume fraction + volume_frac_ = 1.0/xt::prod(shape_)(); + } +} + +int RegularMesh::get_index_in_direction(double r, int i) const +{ + return std::ceil((r - lower_left_[i]) / width_[i]); +} + +double RegularMesh::positive_grid_boundary(int* ijk, int i) const +{ + return lower_left_[i] + ijk[i] * width_[i]; +} + +double RegularMesh::negative_grid_boundary(int* ijk, int i) const +{ + return lower_left_[i] + (ijk[i] - 1) * width_[i]; +} + void RegularMesh::surface_bins_crossed(const Particle& p, std::vector& bins) const { @@ -640,9 +653,9 @@ void RegularMesh::surface_bins_crossed(const Particle& p, Position xyz_cross; for (int i = 0; i < n; ++i) { if (u[i] > 0.0) { - xyz_cross[i] = lower_left_[i] + ijk0[i] * width_[i]; + xyz_cross[i] = positive_grid_boundary(ijk0.data(), i); } else { - xyz_cross[i] = lower_left_[i] + (ijk0[i] - 1) * width_[i]; + xyz_cross[i] = negative_grid_boundary(ijk0.data(), i); } } @@ -887,109 +900,14 @@ RectilinearMesh::RectilinearMesh(pugi::xml_node node) upper_right_ = {grid_[0].back(), grid_[1].back(), grid_[2].back()}; } -void RectilinearMesh::bins_crossed(const Particle& p, std::vector& bins, - std::vector& lengths) const +double RectilinearMesh::positive_grid_boundary(int* ijk, int i) const { - // ======================================================================== - // Determine where the track intersects the mesh and if it intersects at all. + return grid_[i][ijk[i]]; +} - // Copy the starting and ending coordinates of the particle. - Position last_r {p.r_last_}; - Position r {p.r()}; - Direction u {p.u()}; - - // Compute the length of the entire track. - double total_distance = (r - last_r).norm(); - - // While determining if this track intersects the mesh, offset the starting - // and ending coords by a bit. This avoid finite-precision errors that can - // occur when the mesh surfaces coincide with lattice or geometric surfaces. - Position r0 = last_r + TINY_BIT*u; - Position r1 = r - TINY_BIT*u; - - // Determine the mesh indices for the starting and ending coords. - int ijk0[3], ijk1[3]; - bool start_in_mesh; - get_indices(r0, ijk0, &start_in_mesh); - bool end_in_mesh; - get_indices(r1, ijk1, &end_in_mesh); - - // Reset coordinates and check for a mesh intersection if necessary. - if (start_in_mesh) { - // The initial coords lie in the mesh, use those coords for tallying. - r0 = last_r; - } else { - // The initial coords do not lie in the mesh. Check to see if the particle - // eventually intersects the mesh and compute the relevant coords and - // indices. - if (!intersects(r0, r1, ijk0)) return; - } - r1 = r; - - // The TINY_BIT offsets above mean that the preceding logic cannot always find - // the correct ijk0 and ijk1 indices. For tracks shorter than 2*TINY_BIT, just - // assume the track lies in only one mesh bin. These tracks are very short so - // any error caused by this assumption will be small. It is important that - // ijk0 values are used rather than ijk1 because the previous logic guarantees - // ijk0 is a valid mesh bin. - if (total_distance < 2*TINY_BIT) { - for (int i = 0; i < 3; ++i) ijk1[i] = ijk0[i]; - } - - // ======================================================================== - // Find which mesh cells are traversed and the length of each traversal. - - while (true) { - if (std::equal(ijk0, ijk0+3, ijk1)) { - // The track ends in this cell. Use the particle end location rather - // than the mesh surface and stop iterating. - double distance = (r1 - r0).norm(); - bins.push_back(get_bin_from_indices(ijk0)); - lengths.push_back(distance / total_distance); - break; - } - - // The track exits this cell. Determine the distance to each mesh surface. - double d[3]; - for (int k = 0; k < 3; ++k) { - if (std::fabs(u[k]) < FP_PRECISION) { - d[k] = INFTY; - } else if (u[k] > 0) { - double xyz_cross = grid_[k][ijk0[k]]; - d[k] = (xyz_cross - r0[k]) / u[k]; - } else { - double xyz_cross = grid_[k][ijk0[k] - 1]; - d[k] = (xyz_cross - r0[k]) / u[k]; - } - } - - // Pick the closest mesh surface and append this traversal to the output. - auto j = std::min_element(d, d+3) - d; - double distance = d[j]; - bins.push_back(get_bin_from_indices(ijk0)); - lengths.push_back(distance / total_distance); - - // Translate to the oncoming mesh surface. - r0 += distance * u; - - // Increment the indices into the next mesh cell. - if (u[j] > 0.0) { - ++ijk0[j]; - } else { - --ijk0[j]; - } - - // If the next indices are invalid, then the track has left the mesh and - // we are done. - bool in_mesh = true; - for (int i = 0; i < 3; ++i) { - if (ijk0[i] < 1 || ijk0[i] > shape_[i]) { - in_mesh = false; - break; - } - } - if (!in_mesh) break; - } +double RectilinearMesh::negative_grid_boundary(int* ijk, int i) const +{ + return grid_[i][ijk[i] - 1]; } void RectilinearMesh::surface_bins_crossed(const Particle& p, @@ -1086,9 +1004,9 @@ void RectilinearMesh::surface_bins_crossed(const Particle& p, Position xyz_cross; for (int i = 0; i < 3; ++i) { if (u[i] > 0.0) { - xyz_cross[i] = grid_[i][ijk0[i]]; + xyz_cross[i] = positive_grid_boundary(ijk0, i); } else { - xyz_cross[i] = grid_[i][ijk0[i] - 1]; + xyz_cross[i] = negative_grid_boundary(ijk0, i); } } From 87c22dd4d498b6c28621c690b12d75da37fd1665 Mon Sep 17 00:00:00 2001 From: aprilnovak Date: Mon, 19 Oct 2020 16:19:28 -0500 Subject: [PATCH 32/79] Use arrays for ijk0, ijk1, and d in bins_crossed for slightly better performance. Refs #1695 --- src/mesh.cpp | 30 ++++++++++++++++++------------ 1 file changed, 18 insertions(+), 12 deletions(-) diff --git a/src/mesh.cpp b/src/mesh.cpp index d3b671263a..53279cc57a 100644 --- a/src/mesh.cpp +++ b/src/mesh.cpp @@ -406,6 +406,7 @@ bool StructuredMesh::intersects_3d(Position& r0, Position r1, int* ijk) const } void StructuredMesh::bins_crossed(const Particle& p, std::vector& bins, + std::vector& lengths) const { // ======================================================================== // Determine where the track intersects the mesh and if it intersects at all. @@ -424,13 +425,18 @@ void StructuredMesh::bins_crossed(const Particle& p, std::vector& bins, Position r0 = last_r + TINY_BIT*u; Position r1 = r - TINY_BIT*u; - // Determine the mesh indices for the starting and ending coords. + // Determine the mesh indices for the starting and ending coords. Here, we + // use arrays for ijk0 and ijk1 instead of std::vector because we obtain a + // small performance improvement by forcing this data to live on the stack, + // rather than on the heap. We know the maximum length is 3, and by + // ensuring that all loops are only indexed up to n_dimension, we will not + // access any non-initialized values. The same concept is used throughout. int n = n_dimension_; - std::vector ijk0(n), ijk1(n); + int ijk0[3], ijk1[3]; bool start_in_mesh; - get_indices(r0, ijk0.data(), &start_in_mesh); + get_indices(r0, ijk0, &start_in_mesh); bool end_in_mesh; - get_indices(r1, ijk1.data(), &end_in_mesh); + get_indices(r1, ijk1, &end_in_mesh); // Reset coordinates and check for a mesh intersection if necessary. if (start_in_mesh) { @@ -440,7 +446,7 @@ void StructuredMesh::bins_crossed(const Particle& p, std::vector& bins, // The initial coords do not lie in the mesh. Check to see if the particle // eventually intersects the mesh and compute the relevant coords and // indices. - if (!intersects(r0, r1, ijk0.data())) return; + if (!intersects(r0, r1, ijk0)) return; } r1 = r; @@ -458,33 +464,33 @@ void StructuredMesh::bins_crossed(const Particle& p, std::vector& bins, // Find which mesh cells are traversed and the length of each traversal. while (true) { - if (ijk0 == ijk1) { + if (std::equal(ijk0, ijk0 + n, ijk1)) { // The track ends in this cell. Use the particle end location rather // than the mesh surface and stop iterating. double distance = (r1 - r0).norm(); - bins.push_back(get_bin_from_indices(ijk0.data())); + bins.push_back(get_bin_from_indices(ijk0)); lengths.push_back(distance / total_distance); break; } // The track exits this cell. Determine the distance to each mesh surface. - std::vector d(n); + double d[3]; for (int k = 0; k < n; ++k) { if (std::fabs(u[k]) < FP_PRECISION) { d[k] = INFTY; } else if (u[k] > 0) { - double xyz_cross = positive_grid_boundary(ijk0.data(), k); + double xyz_cross = positive_grid_boundary(ijk0, k); d[k] = (xyz_cross - r0[k]) / u[k]; } else { - double xyz_cross = negative_grid_boundary(ijk0.data(), k); + double xyz_cross = negative_grid_boundary(ijk0, k); d[k] = (xyz_cross - r0[k]) / u[k]; } } // Pick the closest mesh surface and append this traversal to the output. - auto j = std::min_element(d.begin(), d.end()) - d.begin(); + auto j = std::min_element(d, d + n) - d; double distance = d[j]; - bins.push_back(get_bin_from_indices(ijk0.data())); + bins.push_back(get_bin_from_indices(ijk0)); lengths.push_back(distance / total_distance); // Translate to the oncoming mesh surface. From 7a6b5fc62ea00fc72ae43b0cb8e9284abecb44d9 Mon Sep 17 00:00:00 2001 From: Jonathan Shimwell Date: Mon, 19 Oct 2020 22:56:55 +0100 Subject: [PATCH 33/79] added dockerhub action for release --- .../workflows/dockerhub-publish-release.yml | 35 +++++++++++++++++++ 1 file changed, 35 insertions(+) create mode 100644 .github/workflows/dockerhub-publish-release.yml diff --git a/.github/workflows/dockerhub-publish-release.yml b/.github/workflows/dockerhub-publish-release.yml new file mode 100644 index 0000000000..d8de72618d --- /dev/null +++ b/.github/workflows/dockerhub-publish-release.yml @@ -0,0 +1,35 @@ +name: dockerhub-publish-release + +on: + push: + tags: 'v*.*.*' + +jobs: + main: + runs-on: ubuntu-latest + steps: + - uses: actions/checkout@v2 + - name: Set env + run: echo "RELEASE_VERSION=${GITHUB_REF#refs/*/}" >> $GITHUB_ENV + - + name: Set up QEMU + uses: docker/setup-qemu-action@v1 + - + name: Set up Docker Buildx + uses: docker/setup-buildx-action@v1 + - + name: Login to DockerHub + uses: docker/login-action@v1 + with: + username: ${{ secrets.DOCKERHUB_USERNAME }} + password: ${{ secrets.DOCKERHUB_TOKEN }} + - + name: Build and push + id: docker_build + uses: docker/build-push-action@v2 + with: + push: true + tags: openmc/openmc:${{ env.RELEASE_VERSION }} + - + name: Image digest + run: echo ${{ steps.docker_build.outputs.digest }} From a6bb97cf43df9d142e3479a49f75a175878d29bf Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 20 Oct 2020 07:25:35 -0500 Subject: [PATCH 34/79] Add missing symlinks in docs/source/examples directory --- docs/source/examples/cad-based-geometry.ipynb | 1 + docs/source/examples/candu.ipynb | 1 + docs/source/examples/expansion-filters.ipynb | 1 + docs/source/examples/hexagonal-lattice.ipynb | 1 + docs/source/examples/mdgxs-part-i.ipynb | 1 + docs/source/examples/mdgxs-part-ii.ipynb | 1 + docs/source/examples/mg-mode-part-i.ipynb | 1 + docs/source/examples/mg-mode-part-ii.ipynb | 1 + docs/source/examples/mg-mode-part-iii.ipynb | 1 + docs/source/examples/mgxs-part-i.ipynb | 1 + docs/source/examples/mgxs-part-ii.ipynb | 1 + docs/source/examples/mgxs-part-iii.ipynb | 1 + docs/source/examples/nuclear-data-resonance-covariance.ipynb | 1 + docs/source/examples/nuclear-data.ipynb | 1 + docs/source/examples/pandas-dataframes.ipynb | 1 + docs/source/examples/pincell.ipynb | 1 + docs/source/examples/pincell_depletion.ipynb | 1 + docs/source/examples/post-processing.ipynb | 1 + docs/source/examples/search.ipynb | 1 + docs/source/examples/tally-arithmetic.ipynb | 1 + docs/source/examples/triso.ipynb | 1 + docs/source/examples/unstructured-mesh-part-i.ipynb | 1 + docs/source/examples/unstructured-mesh-part-ii.ipynb | 1 + 23 files changed, 23 insertions(+) create mode 120000 docs/source/examples/cad-based-geometry.ipynb create mode 120000 docs/source/examples/candu.ipynb create mode 120000 docs/source/examples/expansion-filters.ipynb create mode 120000 docs/source/examples/hexagonal-lattice.ipynb create mode 120000 docs/source/examples/mdgxs-part-i.ipynb create mode 120000 docs/source/examples/mdgxs-part-ii.ipynb create mode 120000 docs/source/examples/mg-mode-part-i.ipynb create mode 120000 docs/source/examples/mg-mode-part-ii.ipynb create mode 120000 docs/source/examples/mg-mode-part-iii.ipynb create mode 120000 docs/source/examples/mgxs-part-i.ipynb create mode 120000 docs/source/examples/mgxs-part-ii.ipynb create mode 120000 docs/source/examples/mgxs-part-iii.ipynb create mode 120000 docs/source/examples/nuclear-data-resonance-covariance.ipynb create mode 120000 docs/source/examples/nuclear-data.ipynb create mode 120000 docs/source/examples/pandas-dataframes.ipynb create mode 120000 docs/source/examples/pincell.ipynb create mode 120000 docs/source/examples/pincell_depletion.ipynb create mode 120000 docs/source/examples/post-processing.ipynb create mode 120000 docs/source/examples/search.ipynb create mode 120000 docs/source/examples/tally-arithmetic.ipynb create mode 120000 docs/source/examples/triso.ipynb create mode 120000 docs/source/examples/unstructured-mesh-part-i.ipynb create mode 120000 docs/source/examples/unstructured-mesh-part-ii.ipynb diff --git a/docs/source/examples/cad-based-geometry.ipynb b/docs/source/examples/cad-based-geometry.ipynb new file mode 120000 index 0000000000..ee3727e672 --- /dev/null +++ b/docs/source/examples/cad-based-geometry.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/cad-based-geometry.ipynb \ No newline at end of file diff --git a/docs/source/examples/candu.ipynb b/docs/source/examples/candu.ipynb new file mode 120000 index 0000000000..480d99fb16 --- /dev/null +++ b/docs/source/examples/candu.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/candu.ipynb \ No newline at end of file diff --git a/docs/source/examples/expansion-filters.ipynb b/docs/source/examples/expansion-filters.ipynb new file mode 120000 index 0000000000..e757341359 --- /dev/null +++ b/docs/source/examples/expansion-filters.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/expansion-filters.ipynb \ No newline at end of file diff --git a/docs/source/examples/hexagonal-lattice.ipynb b/docs/source/examples/hexagonal-lattice.ipynb new file mode 120000 index 0000000000..e2b63d2437 --- /dev/null +++ b/docs/source/examples/hexagonal-lattice.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/hexagonal-lattice.ipynb \ No newline at end of file diff --git a/docs/source/examples/mdgxs-part-i.ipynb b/docs/source/examples/mdgxs-part-i.ipynb new file mode 120000 index 0000000000..01eb1172d4 --- /dev/null +++ b/docs/source/examples/mdgxs-part-i.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/mdgxs-part-i.ipynb \ No newline at end of file diff --git a/docs/source/examples/mdgxs-part-ii.ipynb b/docs/source/examples/mdgxs-part-ii.ipynb new file mode 120000 index 0000000000..2d9d339074 --- /dev/null +++ b/docs/source/examples/mdgxs-part-ii.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/mdgxs-part-ii.ipynb \ No newline at end of file diff --git a/docs/source/examples/mg-mode-part-i.ipynb b/docs/source/examples/mg-mode-part-i.ipynb new file mode 120000 index 0000000000..d1577f7000 --- /dev/null +++ b/docs/source/examples/mg-mode-part-i.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/mg-mode-part-i.ipynb \ No newline at end of file diff --git a/docs/source/examples/mg-mode-part-ii.ipynb b/docs/source/examples/mg-mode-part-ii.ipynb new file mode 120000 index 0000000000..a093063761 --- /dev/null +++ b/docs/source/examples/mg-mode-part-ii.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/mg-mode-part-ii.ipynb \ No newline at end of file diff --git a/docs/source/examples/mg-mode-part-iii.ipynb b/docs/source/examples/mg-mode-part-iii.ipynb new file mode 120000 index 0000000000..6fa0d180e4 --- /dev/null +++ b/docs/source/examples/mg-mode-part-iii.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/mg-mode-part-iii.ipynb \ No newline at end of file diff --git a/docs/source/examples/mgxs-part-i.ipynb b/docs/source/examples/mgxs-part-i.ipynb new file mode 120000 index 0000000000..a04b1da895 --- /dev/null +++ b/docs/source/examples/mgxs-part-i.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/mgxs-part-i.ipynb \ No newline at end of file diff --git a/docs/source/examples/mgxs-part-ii.ipynb b/docs/source/examples/mgxs-part-ii.ipynb new file mode 120000 index 0000000000..dd8af3c438 --- /dev/null +++ b/docs/source/examples/mgxs-part-ii.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/mgxs-part-ii.ipynb \ No newline at end of file diff --git a/docs/source/examples/mgxs-part-iii.ipynb b/docs/source/examples/mgxs-part-iii.ipynb new file mode 120000 index 0000000000..d6acc76baf --- /dev/null +++ b/docs/source/examples/mgxs-part-iii.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/mgxs-part-iii.ipynb \ No newline at end of file diff --git a/docs/source/examples/nuclear-data-resonance-covariance.ipynb b/docs/source/examples/nuclear-data-resonance-covariance.ipynb new file mode 120000 index 0000000000..0ab0dd62b5 --- /dev/null +++ b/docs/source/examples/nuclear-data-resonance-covariance.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/nuclear-data-resonance-covariance.ipynb \ No newline at end of file diff --git a/docs/source/examples/nuclear-data.ipynb b/docs/source/examples/nuclear-data.ipynb new file mode 120000 index 0000000000..59721abdc9 --- /dev/null +++ b/docs/source/examples/nuclear-data.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/nuclear-data.ipynb \ No newline at end of file diff --git a/docs/source/examples/pandas-dataframes.ipynb b/docs/source/examples/pandas-dataframes.ipynb new file mode 120000 index 0000000000..f41f570beb --- /dev/null +++ b/docs/source/examples/pandas-dataframes.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/pandas-dataframes.ipynb \ No newline at end of file diff --git a/docs/source/examples/pincell.ipynb b/docs/source/examples/pincell.ipynb new file mode 120000 index 0000000000..edbbb8de24 --- /dev/null +++ b/docs/source/examples/pincell.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/pincell.ipynb \ No newline at end of file diff --git a/docs/source/examples/pincell_depletion.ipynb b/docs/source/examples/pincell_depletion.ipynb new file mode 120000 index 0000000000..1f25930fcb --- /dev/null +++ b/docs/source/examples/pincell_depletion.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/pincell_depletion.ipynb \ No newline at end of file diff --git a/docs/source/examples/post-processing.ipynb b/docs/source/examples/post-processing.ipynb new file mode 120000 index 0000000000..1f3f4cd713 --- /dev/null +++ b/docs/source/examples/post-processing.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/post-processing.ipynb \ No newline at end of file diff --git a/docs/source/examples/search.ipynb b/docs/source/examples/search.ipynb new file mode 120000 index 0000000000..fbfb67bc60 --- /dev/null +++ b/docs/source/examples/search.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/search.ipynb \ No newline at end of file diff --git a/docs/source/examples/tally-arithmetic.ipynb b/docs/source/examples/tally-arithmetic.ipynb new file mode 120000 index 0000000000..7ffe194626 --- /dev/null +++ b/docs/source/examples/tally-arithmetic.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/tally-arithmetic.ipynb \ No newline at end of file diff --git a/docs/source/examples/triso.ipynb b/docs/source/examples/triso.ipynb new file mode 120000 index 0000000000..0e51d8add9 --- /dev/null +++ b/docs/source/examples/triso.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/triso.ipynb \ No newline at end of file diff --git a/docs/source/examples/unstructured-mesh-part-i.ipynb b/docs/source/examples/unstructured-mesh-part-i.ipynb new file mode 120000 index 0000000000..b1358788ba --- /dev/null +++ b/docs/source/examples/unstructured-mesh-part-i.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/unstructured-mesh-part-i.ipynb \ No newline at end of file diff --git a/docs/source/examples/unstructured-mesh-part-ii.ipynb b/docs/source/examples/unstructured-mesh-part-ii.ipynb new file mode 120000 index 0000000000..9074811b70 --- /dev/null +++ b/docs/source/examples/unstructured-mesh-part-ii.ipynb @@ -0,0 +1 @@ +../../../examples/jupyter/unstructured-mesh-part-ii.ipynb \ No newline at end of file From 490eadd86463d471e4453f938aaa0a102f0c3995 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 20 Oct 2020 14:07:45 -0500 Subject: [PATCH 35/79] Make sure write_source_file creates filetype attribute --- openmc/source.py | 2 ++ tests/unit_tests/test_source_file.py | 7 +++++++ 2 files changed, 9 insertions(+) diff --git a/openmc/source.py b/openmc/source.py index 3863bb826a..b5b53167c5 100644 --- a/openmc/source.py +++ b/openmc/source.py @@ -308,9 +308,11 @@ def write_source_file(source_particles, filename, **kwargs): ]) # Create array of source particles + cv.check_iterable_type("source particles", source_particles, SourceParticle) arr = np.array([s.to_tuple() for s in source_particles], dtype=source_dtype) # Write array to file kwargs.setdefault('mode', 'w') with h5py.File(filename, **kwargs) as fh: + fh.attrs['filetype'] = np.string_("source") fh.create_dataset('source_bank', data=arr, dtype=source_dtype) diff --git a/tests/unit_tests/test_source_file.py b/tests/unit_tests/test_source_file.py index e9bcebc92e..ae6eff97f7 100644 --- a/tests/unit_tests/test_source_file.py +++ b/tests/unit_tests/test_source_file.py @@ -3,9 +3,14 @@ from random import random import h5py import numpy as np import openmc +import pytest def test_source_file(run_in_tmpdir): + # write_source_file shouldn't accept non-SourceParticle items + with pytest.raises(TypeError): + openmc.write_source_file([1, 2, 3], 'test_source.h5') + # Create source particles source = [] n = 1000 @@ -21,9 +26,11 @@ def test_source_file(run_in_tmpdir): # Get array of source particles from file with h5py.File('test_source.h5', 'r') as fh: + filetype = fh.attrs['filetype'] arr = fh['source_bank'][...] # Ensure data is consistent + assert filetype == b'source' r = arr['r'] assert np.all((r['x'] > 0.0) & (r['x'] < 1.0)) assert np.all(r['y'] == np.arange(1000)) From b74c0cc18f26255cfd16c40e95cc1d1c19c7f5b8 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Tue, 20 Oct 2020 16:50:35 -0500 Subject: [PATCH 36/79] Storing state --- openmc/mgxs/mgxs.py | 135 +++++++++++++++++++++++++++++++++++++++++++- 1 file changed, 133 insertions(+), 2 deletions(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 0fc6716f35..bbcfef576e 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -8,6 +8,7 @@ import h5py import numpy as np import openmc +from openmc.data import REACTION_MT import openmc.checkvalue as cv from ..tallies import ESTIMATOR_TYPES from . import EnergyGroups @@ -698,7 +699,7 @@ class MGXS: Parameters ---------- - mgxs_type : {'total', 'transport', 'nu-transport', 'absorption', 'capture', 'fission', 'nu-fission', 'kappa-fission', 'scatter', 'nu-scatter', 'scatter matrix', 'nu-scatter matrix', 'multiplicity matrix', 'nu-fission matrix', 'chi', 'chi-prompt', 'inverse-velocity', 'prompt-nu-fission', 'prompt-nu-fission matrix', 'current', 'diffusion-coefficient', 'nu-diffusion-coefficient'} + mgxs_type : {'total', 'transport', 'nu-transport', 'absorption', 'capture', 'fission', 'nu-fission', 'kappa-fission', 'scatter', 'nu-scatter', 'scatter matrix', 'nu-scatter matrix', 'multiplicity matrix', 'nu-fission matrix', 'chi', 'chi-prompt', 'inverse-velocity', 'prompt-nu-fission', 'prompt-nu-fission matrix', 'current', 'diffusion-coefficient', 'nu-diffusion-coefficient', mt} The type of multi-group cross section object to return domain : openmc.Material or openmc.Cell or openmc.Universe or openmc.RegularMesh The domain for spatial homogenization @@ -782,7 +783,18 @@ class MGXS: mgxs = DiffusionCoefficient(domain, domain_type, energy_groups) elif mgxs_type == 'nu-diffusion-coefficient': mgxs = DiffusionCoefficient(domain, domain_type, energy_groups, nu=True) - + else: + if mgxs_type in REACTION_MT.keys() + REACTION_MT.values(): + # Then it is a reaction not covered by the above that is + # supported by the ArbitraryMTXS Class + mgxs = ArbitraryMTXS(mgxs_type, domain, domain_type, + energy_groups) + else: + # This is an invalid type so let the user know. + msg = 'Unable to set "{0}" to "{1}"'.format("mgxs_type", + mgxs_type) + \ + " as it is not an accepted MGXS type." + raise ValueError(msg) mgxs.by_nuclide = by_nuclide mgxs.name = name mgxs.num_polar = num_polar @@ -3850,6 +3862,125 @@ class ScatterXS(MGXS): self._valid_estimators = ['analog'] + +class ArbitraryMTXS(MGXS): + r"""A multi-group cross section for an arbitrary reaction type. + + This class can be used for both OpenMC input generation and tally data + post-processing to compute spatially-homogenized and energy-integrated + multi-group total cross sections for multi-group neutronics calculations. At + a minimum, one needs to set the :attr:`TotalXS.energy_groups` and + :attr:`TotalXS.domain` properties. Tallies for the flux and appropriate + reaction rates over the specified domain are generated automatically via the + :attr:`TotalXS.tallies` property, which can then be appended to a + :class:`openmc.Tallies` instance. + + For post-processing, the :meth:`MGXS.load_from_statepoint` will pull in the + necessary data to compute multi-group cross sections from a + :class:`openmc.StatePoint` instance. The derived multi-group cross section + can then be obtained from the :attr:`TotalXS.xs_tally` property. + + For a spatial domain :math:`V` and energy group :math:`[E_g,E_{g-1}]`, the + total cross section is calculated as: + + .. math:: + + \frac{\int_{r \in V} dr \int_{4\pi} d\Omega \int_{E_g}^{E_{g-1}} dE \; + \sigma_t (r, E) \psi (r, E, \Omega)}{\int_{r \in V} dr \int_{4\pi} + d\Omega \int_{E_g}^{E_{g-1}} dE \; \psi (r, E, \Omega)}. + + Parameters + ---------- + domain : openmc.Material or openmc.Cell or openmc.Universe or openmc.RegularMesh + The domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe', 'mesh'} + The domain type for spatial homogenization + groups : openmc.mgxs.EnergyGroups + The energy group structure for energy condensation + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + name : str, optional + Name of the multi-group cross section. Used as a label to identify + tallies in OpenMC 'tallies.xml' file. + num_polar : Integral, optional + Number of equi-width polar angle bins for angle discretization; + defaults to one bin + num_azimuthal : Integral, optional + Number of equi-width azimuthal angle bins for angle discretization; + defaults to one bin + + Attributes + ---------- + name : str, optional + Name of the multi-group cross section + rxn_type : str + Reaction type (e.g., 'total', 'nu-fission', etc.) + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + domain : openmc.Material or openmc.Cell or openmc.Universe or openmc.RegularMesh + Domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe', 'mesh'} + Domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + Energy group structure for energy condensation + num_polar : Integral + Number of equi-width polar angle bins for angle discretization + num_azimuthal : Integral + Number of equi-width azimuthal angle bins for angle discretization + tally_trigger : openmc.Trigger + An (optional) tally precision trigger given to each tally used to + compute the cross section + scores : list of str + The scores in each tally used to compute the multi-group cross section + filters : list of openmc.Filter + The filters in each tally used to compute the multi-group cross section + tally_keys : list of str + The keys into the tallies dictionary for each tally used to compute + the multi-group cross section + estimator : {'tracklength', 'collision', 'analog'} + The tally estimator used to compute the multi-group cross section + tallies : collections.OrderedDict + OpenMC tallies needed to compute the multi-group cross section. The keys + are strings listed in the :attr:`TotalXS.tally_keys` property and values + are instances of :class:`openmc.Tally`. + rxn_rate_tally : openmc.Tally + Derived tally for the reaction rate tally used in the numerator to + compute the multi-group cross section. This attribute is None + unless the multi-group cross section has been computed. + xs_tally : openmc.Tally + Derived tally for the multi-group cross section. This attribute + is None unless the multi-group cross section has been computed. + num_subdomains : int + The number of subdomains is unity for 'material', 'cell' and 'universe' + domain types. This is equal to the number of cell instances + for 'distribcell' domain types (it is equal to unity prior to loading + tally data from a statepoint file). + num_nuclides : int + The number of nuclides for which the multi-group cross section is + being tracked. This is unity if the by_nuclide attribute is False. + nuclides : Iterable of str or 'sum' + The optional user-specified nuclides for which to compute cross + sections (e.g., 'U238', 'O16'). If by_nuclide is True but nuclides + are not specified by the user, all nuclides in the spatial domain + are included. This attribute is 'sum' if by_nuclide is false. + sparse : bool + Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format + for compressed data storage + loaded_sp : bool + Whether or not a statepoint file has been loaded with tally data + derived : bool + Whether or not the MGXS is merged from one or more other MGXS + hdf5_key : str + The key used to index multi-group cross sections in an HDF5 data store + + """ + + def __init__(self, rxn_type, domain=None, domain_type=None, groups=None, + by_nuclide=False, name='', num_polar=1, num_azimuthal=1): + super().__init__(domain, domain_type, groups, by_nuclide, name, + num_polar, num_azimuthal) + self._rxn_type = rxn_type + class ScatterMatrixXS(MatrixMGXS): r"""A scattering matrix multi-group cross section with the cosine of the change-in-angle represented as one or more Legendre moments or a histogram. From 6f4da065803008a18740e65218b116ee0a1114fa Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Thu, 22 Oct 2020 09:51:14 -0500 Subject: [PATCH 37/79] Added ability to handle ArbitraryMatrixXS types (i.e., we can now create (n,3n) energy transition matrices). This is in addition to the previous commit's incorporation of the same for vector MGXS with the ArbitraryXS type. Also gave the user the ability to request that a domain's macroscopic Chi values be used for all isotopes in a domain. This is important because some codes do not create macroscopic Chi's with flux-weighting of the group-wise fission source, they instead assume a constant group-wise flux. This leads to errors downstream with microscopic MGXS in codes like OpenMC's MG mode and even heavily used production codes like DIF3D. --- openmc/mgxs/library.py | 67 ++++++++++-- openmc/mgxs/mgxs.py | 225 +++++++++++++++++++++++++++++++++++++---- 2 files changed, 263 insertions(+), 29 deletions(-) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index e2ba0bc6a1..2b8b71e02d 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -612,8 +612,10 @@ class Library: ---------- domain : openmc.Material or openmc.Cell or openmc.Universe or openmc.RegularMesh or Integral The material, cell, or universe object of interest (or its ID) - mgxs_type : {'total', 'transport', 'nu-transport', 'absorption', 'capture', 'fission', 'nu-fission', 'kappa-fission', 'scatter', 'nu-scatter', 'scatter matrix', 'nu-scatter matrix', 'multiplicity matrix', 'nu-fission matrix', chi', 'chi-prompt', 'inverse-velocity', 'prompt-nu-fission', 'prompt-nu-fission matrix', 'delayed-nu-fission', 'delayed-nu-fission matrix', 'chi-delayed', 'beta'} - The type of multi-group cross section object to return + mgxs_type : str + The type of multi-group cross section object to return; allowable + values are those MGXS to the Library and present in the + mgxs_types attribute. Returns ------- @@ -912,7 +914,7 @@ class Library: return pickle.load(f) def get_xsdata(self, domain, xsdata_name, nuclide='total', xs_type='macro', - subdomain=None): + subdomain=None, apply_domain_chi=False): """Generates an openmc.XSdata object describing a multi-group cross section dataset for writing to an openmc.MGXSLibrary object. @@ -939,6 +941,15 @@ class Library: mesh cell of interest in the openmc.RegularMesh object. Note: this parameter currently only supports subdomains within a mesh, and not the subdomains of a distribcell. + apply_domain_chi : bool + This parameter sets whether (True) or not (False) the + domain-averaged values of chi, chi-prompt, and chi-delayed are to + be applied to each of the nuclidic fission energy spectra of a + domain. In effect, if this is True, then every nuclide in the + domain receives the same flux-weighted Chi. This is useful for + downstream multigroup solvers that pre-compute a material-specific + chi before the transport solve provides group-wise fluxes. Defaults + to False. Returns ------- @@ -1046,18 +1057,30 @@ class Library: if 'chi' in self.mgxs_types: mymgxs = self.get_mgxs(domain, 'chi') - xsdata.set_chi_mgxs(mymgxs, xs_type=xs_type, nuclide=[nuclide], + if apply_domain_chi and nuclide != "total": + nuc = "sum" + else: + nuc = nuclide + xsdata.set_chi_mgxs(mymgxs, xs_type=xs_type, nuclide=[nuc], subdomain=subdomain) if 'chi-prompt' in self.mgxs_types: mymgxs = self.get_mgxs(domain, 'chi-prompt') + if apply_domain_chi and nuclide != "total": + nuc = "sum" + else: + nuc = nuclide xsdata.set_chi_prompt_mgxs(mymgxs, xs_type=xs_type, - nuclide=[nuclide], subdomain=subdomain) + nuclide=[nuc], subdomain=subdomain) if 'chi-delayed' in self.mgxs_types: mymgxs = self.get_mgxs(domain, 'chi-delayed') + if apply_domain_chi and nuclide != "total": + nuc = "sum" + else: + nuc = nuclide xsdata.set_chi_delayed_mgxs(mymgxs, xs_type=xs_type, - nuclide=[nuclide], subdomain=subdomain) + nuclide=[nuc], subdomain=subdomain) if 'nu-fission' in self.mgxs_types: mymgxs = self.get_mgxs(domain, 'nu-fission') @@ -1196,7 +1219,8 @@ class Library: return xsdata - def create_mg_library(self, xs_type='macro', xsdata_names=None): + def create_mg_library(self, xs_type='macro', xsdata_names=None, + apply_domain_chi=False): """Creates an openmc.MGXSLibrary object to contain the MGXS data for the Multi-Group mode of OpenMC. @@ -1213,6 +1237,15 @@ class Library: xsdata_names : Iterable of str List of names to apply to the "xsdata" entries in the resultant mgxs data file. Defaults to 'set1', 'set2', ... + apply_domain_chi : bool + This parameter sets whether (True) or not (False) the + domain-averaged values of chi, chi-prompt, and chi-delayed are to + be applied to each of the nuclidic fission energy spectra of a + domain. In effect, if this is True, then every nuclide in the + domain receives the same flux-weighted Chi. This is useful for + downstream multigroup solvers that pre-compute a material-specific + chi before the transport solve provides group-wise fluxes. Defaults + to False. Returns ------- @@ -1284,13 +1317,15 @@ class Library: xsdata_name = xsdata_names[i] xsdata = self.get_xsdata(domain, xsdata_name, - nuclide=nuclide, xs_type=xs_type) + nuclide=nuclide, xs_type=xs_type, + apply_domain_chi=apply_domain_chi) mgxs_file.add_xsdata(xsdata) return mgxs_file - def create_mg_mode(self, xsdata_names=None, bc=['reflective'] * 6): + def create_mg_mode(self, xsdata_names=None, bc=['reflective'] * 6, + apply_domain_chi=False): """Creates an openmc.MGXSLibrary object to contain the MGXS data for the Multi-Group mode of OpenMC as well as the associated openmc.Materials and openmc.Geometry objects. @@ -1314,6 +1349,15 @@ class Library: (if applying to a 3D mesh) provided in the following order: [x min, x max, y min, y max, z min, z max]. 2-D cells do not contain the z min and z max entries. + apply_domain_chi : bool + This parameter sets whether (True) or not (False) the + domain-averaged values of chi, chi-prompt, and chi-delayed are to + be applied to each of the nuclidic fission energy spectra of a + domain. In effect, if this is True, then every nuclide in the + domain receives the same flux-weighted Chi. This is useful for + downstream multigroup solvers that pre-compute a material-specific + chi before the transport solve provides group-wise fluxes. Defaults + to False. Returns ------- @@ -1354,7 +1398,8 @@ class Library: cv.check_length("domains", self.domains, 1, 1) # Get the MGXS File Data - mgxs_file = self.create_mg_library('macro', xsdata_names) + mgxs_file = self.create_mg_library('macro', xsdata_names, + apply_domain_chi=apply_domain_chi) # Now move on the creating the geometry and assigning materials if self.domain_type == 'mesh': @@ -1415,7 +1460,7 @@ class Library: if not isinstance(cell.fill, openmc.Material): warn('If the library domain includes a lattice or universe cell ' 'in conjunction with a consituent cell of that lattice/universe, ' - 'the multi-group simulation will fail') + 'the multi-group simulation will fail') if cell.id == domain.id: cell.fill = material diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index bbcfef576e..6cd3b4f4df 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -699,8 +699,13 @@ class MGXS: Parameters ---------- - mgxs_type : {'total', 'transport', 'nu-transport', 'absorption', 'capture', 'fission', 'nu-fission', 'kappa-fission', 'scatter', 'nu-scatter', 'scatter matrix', 'nu-scatter matrix', 'multiplicity matrix', 'nu-fission matrix', 'chi', 'chi-prompt', 'inverse-velocity', 'prompt-nu-fission', 'prompt-nu-fission matrix', 'current', 'diffusion-coefficient', 'nu-diffusion-coefficient', mt} - The type of multi-group cross section object to return + mgxs_type : str or Integral + The type of multi-group cross section object to return; valid + values are members of MGXS_TYPES, or the reaction types that are + the keys of REACTION_MT. Note that if a reaction type from + REACTION_MT is used, it can be appended with ' matrix' to obtain + a multigroup matrix (from incoming to outgoing energy groups) for + reactions with a neutron in an outgoing channel. domain : openmc.Material or openmc.Cell or openmc.Universe or openmc.RegularMesh The domain for spatial homogenization domain_type : {'material', 'cell', 'distribcell', 'universe', 'mesh'} @@ -728,8 +733,6 @@ class MGXS: """ - cv.check_value('mgxs_type', mgxs_type, MGXS_TYPES) - if mgxs_type == 'total': mgxs = TotalXS(domain, domain_type, energy_groups) elif mgxs_type == 'transport': @@ -784,11 +787,28 @@ class MGXS: elif mgxs_type == 'nu-diffusion-coefficient': mgxs = DiffusionCoefficient(domain, domain_type, energy_groups, nu=True) else: - if mgxs_type in REACTION_MT.keys() + REACTION_MT.values(): + # Now parse the REACTION_MT options, or raise an error + if mgxs_type in REACTION_MT.keys(): # Then it is a reaction not covered by the above that is - # supported by the ArbitraryMTXS Class - mgxs = ArbitraryMTXS(mgxs_type, domain, domain_type, + # supported by the ArbitraryXS Class + mgxs = ArbitraryXS(mgxs_type, domain, domain_type, energy_groups) + elif mgxs_type.endswith("matrix"): + # Then we should see if it is a valid REACTION_MT type + # To do that, split it into words + split_mgxs_types = mgxs_type.split(" ") + rxn = split_mgxs_types[0] + + # Check for correctness + if rxn not in REACTION_MT.keys(): + # This is an invalid type so let the user know. + msg = 'Unable to set "{0}" to "{1}"'.format("mgxs_type", + mgxs_type) + \ + " as it is not an accepted MGXS type." + raise ValueError(msg) + + mgxs = ArbitraryMatrixXS(mgxs_type, domain, domain_type, + energy_groups) else: # This is an invalid type so let the user know. msg = 'Unable to set "{0}" to "{1}"'.format("mgxs_type", @@ -3862,35 +3882,38 @@ class ScatterXS(MGXS): self._valid_estimators = ['analog'] - -class ArbitraryMTXS(MGXS): +class ArbitraryXS(MGXS): r"""A multi-group cross section for an arbitrary reaction type. This class can be used for both OpenMC input generation and tally data post-processing to compute spatially-homogenized and energy-integrated - multi-group total cross sections for multi-group neutronics calculations. At - a minimum, one needs to set the :attr:`TotalXS.energy_groups` and - :attr:`TotalXS.domain` properties. Tallies for the flux and appropriate + multi-group total cross sections for multi-group neutronics calculations. + At a minimum, one needs to set the :attr:`ArbitraryXS.energy_groups` and + :attr:`ArbitraryXS.domain` properties. Tallies for the flux and appropriate reaction rates over the specified domain are generated automatically via the - :attr:`TotalXS.tallies` property, which can then be appended to a + :attr:`ArbitraryXS.tallies` property, which can then be appended to a :class:`openmc.Tallies` instance. For post-processing, the :meth:`MGXS.load_from_statepoint` will pull in the necessary data to compute multi-group cross sections from a :class:`openmc.StatePoint` instance. The derived multi-group cross section - can then be obtained from the :attr:`TotalXS.xs_tally` property. + can then be obtained from the :attr:`ArbitraryXS.xs_tally` property. For a spatial domain :math:`V` and energy group :math:`[E_g,E_{g-1}]`, the - total cross section is calculated as: + requested cross section is calculated as: .. math:: \frac{\int_{r \in V} dr \int_{4\pi} d\Omega \int_{E_g}^{E_{g-1}} dE \; - \sigma_t (r, E) \psi (r, E, \Omega)}{\int_{r \in V} dr \int_{4\pi} - d\Omega \int_{E_g}^{E_{g-1}} dE \; \psi (r, E, \Omega)}. + \sigma_X (r, E) \psi (r, E, \Omega)}{\int_{r \in V} dr \int_{4\pi} + d\Omega \int_{E_g}^{E_{g-1}} dE \; \psi (r, E, \Omega)} + + where :math:`_\sigma_X` is the requested reaction type of interest. Parameters ---------- + rxn_type : str + Reaction type (e.g., '(n,2n)', '(n,Xt)', etc.) domain : openmc.Material or openmc.Cell or openmc.Universe or openmc.RegularMesh The domain for spatial homogenization domain_type : {'material', 'cell', 'distribcell', 'universe', 'mesh'} @@ -3914,7 +3937,7 @@ class ArbitraryMTXS(MGXS): name : str, optional Name of the multi-group cross section rxn_type : str - Reaction type (e.g., 'total', 'nu-fission', etc.) + Reaction type (e.g., '(n,2n)', '(n,Xt)', etc.) by_nuclide : bool If true, computes cross sections for each nuclide in domain domain : openmc.Material or openmc.Cell or openmc.Universe or openmc.RegularMesh @@ -3981,6 +4004,172 @@ class ArbitraryMTXS(MGXS): num_polar, num_azimuthal) self._rxn_type = rxn_type + +class ArbitraryMatrixXS(MatrixMGXS): + r"""A multi-group matrix cross section for an arbitrary reaction type. + + This class can be used for both OpenMC input generation and tally data + post-processing to compute spatially-homogenized and energy-integrated + multi-group cross sections for multi-group neutronics calculations. At a + minimum, one needs to set the :attr:`ArbitraryMatrixXS.energy_groups` and + :attr:`ArbitraryMatrixXS.domain` properties. Tallies for the flux and + appropriate reaction rates over the specified domain are generated + automatically via the :attr:`ArbitraryMatrixXS.tallies` property, which can + then be appended to a :class:`openmc.Tallies` instance. + + For post-processing, the :meth:`MGXS.load_from_statepoint` will pull in the + necessary data to compute multi-group cross sections from a + :class:`openmc.StatePoint` instance. The derived multi-group cross section + can then be obtained from the :attr:`ArbitraryMatrixXS.xs_tally` property. + + For a spatial domain :math:`V`, incoming energy group + :math:`[E_{g'},E_{g'-1}]`, and outgoing energy group :math:`[E_g,E_{g-1}]`, + the fission production is calculated as: + + .. math:: + + \begin{aligned} + \langle \sigma_{X,g'\rightarrow g} \phi \rangle &= \int_{r \in V} dr + \int_{4\pi} d\Omega' \int_{E_{g'}}^{E_{g'-1}} dE' \int_{E_g}^{E_{g-1}} dE + \; \chi(E) \sigma_X (r, E') \psi(r, E', \Omega')\\ + \langle \phi \rangle &= \int_{r \in V} dr \int_{4\pi} d\Omega + \int_{E_g}^{E_{g-1}} dE \; \psi (r, E, \Omega) \\ + \sigma_{X,g'\rightarrow g} &= \frac{\langle \sigma_{X,g'\rightarrow + g} \phi \rangle}{\langle \phi \rangle} + \end{aligned} + + where :math:`_\sigma_X` is the requested reaction type of interest. + + Parameters + ---------- + rxn_type : str + Reaction type (e.g., '(n,2n)', '(n,nta)', etc.). Valid names have + neutrons as a product. + domain : openmc.Material or openmc.Cell or openmc.Universe or openmc.RegularMesh + The domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe', 'mesh'} + The domain type for spatial homogenization + groups : openmc.mgxs.EnergyGroups + The energy group structure for energy condensation + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + name : str, optional + Name of the multi-group cross section. Used as a label to identify + tallies in OpenMC 'tallies.xml' file. + num_polar : Integral, optional + Number of equi-width polar angle bins for angle discretization; + defaults to one bin + num_azimuthal : Integral, optional + Number of equi-width azimuthal angle bins for angle discretization; + defaults to one bin + prompt : bool + If true, computes cross sections which only includes prompt neutrons; + defaults to False which includes prompt and delayed in total + + Attributes + ---------- + name : str, optional + Name of the multi-group cross section + rxn_type : str + Reaction type (e.g., 'total', 'nu-fission', etc.) + prompt : bool + If true, computes cross sections which only includes prompt neutrons + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + domain : openmc.Material or openmc.Cell or openmc.Universe or openmc.RegularMesh + Domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe', 'mesh'} + Domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + Energy group structure for energy condensation + num_polar : Integral + Number of equi-width polar angle bins for angle discretization + num_azimuthal : Integral + Number of equi-width azimuthal angle bins for angle discretization + tally_trigger : openmc.Trigger + An (optional) tally precision trigger given to each tally used to + compute the cross section + scores : list of str + The scores in each tally used to compute the multi-group cross section + filters : list of openmc.Filter + The filters in each tally used to compute the multi-group cross section + tally_keys : list of str + The keys into the tallies dictionary for each tally used to compute + the multi-group cross section + estimator : 'analog' + The tally estimator used to compute the multi-group cross section + tallies : collections.OrderedDict + OpenMC tallies needed to compute the multi-group cross section. The keys + are strings listed in the :attr:`NuFissionMatrixXS.tally_keys` + property and values are instances of :class:`openmc.Tally`. + rxn_rate_tally : openmc.Tally + Derived tally for the reaction rate tally used in the numerator to + compute the multi-group cross section. This attribute is None + unless the multi-group cross section has been computed. + xs_tally : openmc.Tally + Derived tally for the multi-group cross section. This attribute + is None unless the multi-group cross section has been computed. + num_subdomains : int + The number of subdomains is unity for 'material', 'cell' and 'universe' + domain types. This is equal to the number of cell instances + for 'distribcell' domain types (it is equal to unity prior to loading + tally data from a statepoint file). + num_nuclides : int + The number of nuclides for which the multi-group cross section is + being tracked. This is unity if the by_nuclide attribute is False. + nuclides : Iterable of str or 'sum' + The optional user-specified nuclides for which to compute cross + sections (e.g., 'U238', 'O16'). If by_nuclide is True but nuclides + are not specified by the user, all nuclides in the spatial domain + are included. This attribute is 'sum' if by_nuclide is false. + sparse : bool + Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format + for compressed data storage + loaded_sp : bool + Whether or not a statepoint file has been loaded with tally data + derived : bool + Whether or not the MGXS is merged from one or more other MGXS + hdf5_key : str + The key used to index multi-group cross sections in an HDF5 data store + + """ + + def __init__(self, domain=None, domain_type=None, groups=None, + by_nuclide=False, name='', num_polar=1, + num_azimuthal=1, prompt=False): + super().__init__(domain, domain_type, groups, by_nuclide, name, + num_polar, num_azimuthal) + # Do that with the error variable just because PEP8 puts us in + # a hard place for multi-line if conditionals + # First we see if there are more words than there should be, + # then we make sure its a valid reaction, then we dont allow + # non (n,...) type reactions like 'heating-local' as they cant + # be matrices + split_rxn_type = rxn_type.split(" ") + error = len(split_rxn_type) > 2 or rxn not in REACTION_MT.keys() or \ + not rxn.startswith("(") + if error: + # This is an invalid type so let the user know. + msg = 'Unable to set "{0}" to "{1}"'.format("rxns_type", + rxn_type) + \ + " as it is not an accepted ArbitraryMatrixXS type." + raise ValueError(msg) + + # See if the rxn can be a matrix type; we've already made sure its + # an (X,Y) type of reaction, get the product (Y) + _, product = rxn.strip("()").split(',', maxsplit=2) + if "n" not in product: + msg = 'Unable to set "{0}" to "{1}"'.format("rxns_type", + rxn_type) + \ + " as it is not an accepted ArbitraryMatrixXS type." + raise ValueError(msg) + + # If we made it here, then we are good to go + self._rxn_type = rxn_type + self._estimator = 'analog' + self._valid_estimators = ['analog'] + + class ScatterMatrixXS(MatrixMGXS): r"""A scattering matrix multi-group cross section with the cosine of the change-in-angle represented as one or more Legendre moments or a histogram. From d2c00b4f1b2eec125316998e2d418255acd49d58 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Thu, 22 Oct 2020 14:13:32 -0500 Subject: [PATCH 38/79] Added tests and fixed code accordingly --- docs/source/pythonapi/mgxs.rst | 5 + include/openmc/constants.h | 2 +- openmc/data/reaction.py | 2 +- openmc/mgxs/library.py | 4 +- openmc/mgxs/mgxs.py | 94 +- src/reaction.cpp | 2 +- .../mgxs_library_no_nuclides/inputs_true.dat | 19616 +++++++++++++++- .../mgxs_library_no_nuclides/results_true.dat | 7101 ++++++ .../mgxs_library_no_nuclides/test.py | 5 +- .../mgxs_library_nuclides/inputs_true.dat | 19612 ++++++++++++++- .../mgxs_library_nuclides/results_true.dat | 2 +- .../mgxs_library_nuclides/test.py | 2 + 12 files changed, 45629 insertions(+), 818 deletions(-) diff --git a/docs/source/pythonapi/mgxs.rst b/docs/source/pythonapi/mgxs.rst index a25a89c09c..bf5a845992 100644 --- a/docs/source/pythonapi/mgxs.rst +++ b/docs/source/pythonapi/mgxs.rst @@ -30,6 +30,7 @@ Multi-group Cross Sections :template: myclassinherit.rst openmc.mgxs.MGXS + openmc.mgxs.MatrixMGXS openmc.mgxs.AbsorptionXS openmc.mgxs.CaptureXS openmc.mgxs.Chi @@ -45,6 +46,9 @@ Multi-group Cross Sections openmc.mgxs.ScatterProbabilityMatrix openmc.mgxs.TotalXS openmc.mgxs.TransportXS + openmc.mgxs.ArbitraryXS + openmc.mgxs.ArbitraryMatrixXS + openmc.mgxs.MeshSurfaceMGXS Multi-delayed-group Cross Sections ---------------------------------- @@ -55,6 +59,7 @@ Multi-delayed-group Cross Sections :template: myclassinherit.rst openmc.mgxs.MDGXS + openmc.mgxs.MatrixMDGXS openmc.mgxs.ChiDelayed openmc.mgxs.DelayedNuFissionXS openmc.mgxs.DelayedNuFissionMatrixXS diff --git a/include/openmc/constants.h b/include/openmc/constants.h index e75d8c03ca..24d60b92c4 100644 --- a/include/openmc/constants.h +++ b/include/openmc/constants.h @@ -199,7 +199,7 @@ enum ReactionType { N_3N3HE = 177, N_4N3HE = 178, N_3N2P = 179, - N_3N3A = 180, + N_3N2A = 180, N_3NPA = 181, N_DT = 182, N_NPD = 183, diff --git a/openmc/data/reaction.py b/openmc/data/reaction.py index 276218df06..474967167e 100644 --- a/openmc/data/reaction.py +++ b/openmc/data/reaction.py @@ -56,7 +56,7 @@ REACTION_NAME = {1: '(n,total)', 2: '(n,elastic)', 4: '(n,level)', 301: 'heating', 444: 'damage-energy', 649: '(n,pc)', 699: '(n,dc)', 749: '(n,tc)', 799: '(n,3Hec)', 849: '(n,ac)', 891: '(n,2nc)', 901: 'heating-local'} -REACTION_NAME.update({i: '(n,n{})'.format(i - 50) for i in range(50, 91)}) +REACTION_NAME.update({i: '(n,n{})'.format(i - 50) for i in range(51, 91)}) REACTION_NAME.update({i: '(n,p{})'.format(i - 600) for i in range(600, 649)}) REACTION_NAME.update({i: '(n,d{})'.format(i - 650) for i in range(650, 699)}) REACTION_NAME.update({i: '(n,t{})'.format(i - 700) for i in range(700, 749)}) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 2b8b71e02d..0d8373592b 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -277,7 +277,9 @@ class Library: @mgxs_types.setter def mgxs_types(self, mgxs_types): - all_mgxs_types = openmc.mgxs.MGXS_TYPES + openmc.mgxs.MDGXS_TYPES + all_mgxs_types = openmc.mgxs.MGXS_TYPES + openmc.mgxs.MDGXS_TYPES + \ + openmc.mgxs.ARBITRARY_VECTOR_TYPES + \ + openmc.mgxs.ARBITRARY_MATRIX_TYPES if mgxs_types == 'all': self._mgxs_types = all_mgxs_types else: diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 6cd3b4f4df..a300344ede 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -8,7 +8,7 @@ import h5py import numpy as np import openmc -from openmc.data import REACTION_MT +from openmc.data import REACTION_MT, REACTION_NAME, FISSION_MTS import openmc.checkvalue as cv from ..tallies import ESTIMATOR_TYPES from . import EnergyGroups @@ -43,6 +43,22 @@ MGXS_TYPES = ( 'nu-diffusion-coefficient' ) +# Some scores from REACTION_MT are not supported, or are simply overkill to +# support and test (like inelastic levels), remoev those from consideration +_BAD_SCORES = ["(n,misc)", "(n,absorption)", "(n,total)", "fission"] +_BAD_SCORES += [REACTION_NAME[mt] for mt in FISSION_MTS] +ARBITRARY_VECTOR_TYPES = [k for k in REACTION_MT.keys() if k not in _BAD_SCORES] +ARBITRARY_VECTOR_TYPES = tuple(ARBITRARY_VECTOR_TYPES) +ARBITRARY_MATRIX_TYPES = [] +for rxn in ARBITRARY_VECTOR_TYPES: + # Preclude the fission channels from being treated as a matrix + if rxn not in [REACTION_NAME[mt] for mt in FISSION_MTS]: + split_rxn = rxn.strip("()").split(",") + if len(split_rxn) > 1 and "n" in split_rxn[1]: + # Then there is a neutron product, so it can also be a matrix + ARBITRARY_MATRIX_TYPES.append(rxn + " matrix") +ARBITRARY_MATRIX_TYPES = tuple(ARBITRARY_MATRIX_TYPES) + # Supported domain types DOMAIN_TYPES = ( 'cell', @@ -733,6 +749,10 @@ class MGXS: """ + cv.check_value( + "mgxs_type", mgxs_type, + MGXS_TYPES + ARBITRARY_VECTOR_TYPES + ARBITRARY_MATRIX_TYPES) + if mgxs_type == 'total': mgxs = TotalXS(domain, domain_type, energy_groups) elif mgxs_type == 'transport': @@ -786,35 +806,14 @@ class MGXS: mgxs = DiffusionCoefficient(domain, domain_type, energy_groups) elif mgxs_type == 'nu-diffusion-coefficient': mgxs = DiffusionCoefficient(domain, domain_type, energy_groups, nu=True) - else: - # Now parse the REACTION_MT options, or raise an error - if mgxs_type in REACTION_MT.keys(): - # Then it is a reaction not covered by the above that is - # supported by the ArbitraryXS Class - mgxs = ArbitraryXS(mgxs_type, domain, domain_type, + elif mgxs_type in ARBITRARY_VECTOR_TYPES: + # Then it is a reaction not covered by the above that is + # supported by the ArbitraryXS Class + mgxs = ArbitraryXS(mgxs_type, domain, domain_type, energy_groups) + elif mgxs_type in ARBITRARY_MATRIX_TYPES: + mgxs = ArbitraryMatrixXS(mgxs_type, domain, domain_type, energy_groups) - elif mgxs_type.endswith("matrix"): - # Then we should see if it is a valid REACTION_MT type - # To do that, split it into words - split_mgxs_types = mgxs_type.split(" ") - rxn = split_mgxs_types[0] - # Check for correctness - if rxn not in REACTION_MT.keys(): - # This is an invalid type so let the user know. - msg = 'Unable to set "{0}" to "{1}"'.format("mgxs_type", - mgxs_type) + \ - " as it is not an accepted MGXS type." - raise ValueError(msg) - - mgxs = ArbitraryMatrixXS(mgxs_type, domain, domain_type, - energy_groups) - else: - # This is an invalid type so let the user know. - msg = 'Unable to set "{0}" to "{1}"'.format("mgxs_type", - mgxs_type) + \ - " as it is not an accepted MGXS type." - raise ValueError(msg) mgxs.by_nuclide = by_nuclide mgxs.name = name mgxs.num_polar = num_polar @@ -4000,6 +3999,7 @@ class ArbitraryXS(MGXS): def __init__(self, rxn_type, domain=None, domain_type=None, groups=None, by_nuclide=False, name='', num_polar=1, num_azimuthal=1): + cv.check_value("rxn_type", rxn_type, ARBITRARY_VECTOR_TYPES) super().__init__(domain, domain_type, groups, by_nuclide, name, num_polar, num_azimuthal) self._rxn_type = rxn_type @@ -4062,9 +4062,6 @@ class ArbitraryMatrixXS(MatrixMGXS): num_azimuthal : Integral, optional Number of equi-width azimuthal angle bins for angle discretization; defaults to one bin - prompt : bool - If true, computes cross sections which only includes prompt neutrons; - defaults to False which includes prompt and delayed in total Attributes ---------- @@ -4072,8 +4069,6 @@ class ArbitraryMatrixXS(MatrixMGXS): Name of the multi-group cross section rxn_type : str Reaction type (e.g., 'total', 'nu-fission', etc.) - prompt : bool - If true, computes cross sections which only includes prompt neutrons by_nuclide : bool If true, computes cross sections for each nuclide in domain domain : openmc.Material or openmc.Cell or openmc.Universe or openmc.RegularMesh @@ -4134,38 +4129,13 @@ class ArbitraryMatrixXS(MatrixMGXS): """ - def __init__(self, domain=None, domain_type=None, groups=None, + def __init__(self, rxn_type, domain=None, domain_type=None, groups=None, by_nuclide=False, name='', num_polar=1, - num_azimuthal=1, prompt=False): + num_azimuthal=1): + cv.check_value("rxn_type", rxn_type, ARBITRARY_MATRIX_TYPES) super().__init__(domain, domain_type, groups, by_nuclide, name, num_polar, num_azimuthal) - # Do that with the error variable just because PEP8 puts us in - # a hard place for multi-line if conditionals - # First we see if there are more words than there should be, - # then we make sure its a valid reaction, then we dont allow - # non (n,...) type reactions like 'heating-local' as they cant - # be matrices - split_rxn_type = rxn_type.split(" ") - error = len(split_rxn_type) > 2 or rxn not in REACTION_MT.keys() or \ - not rxn.startswith("(") - if error: - # This is an invalid type so let the user know. - msg = 'Unable to set "{0}" to "{1}"'.format("rxns_type", - rxn_type) + \ - " as it is not an accepted ArbitraryMatrixXS type." - raise ValueError(msg) - - # See if the rxn can be a matrix type; we've already made sure its - # an (X,Y) type of reaction, get the product (Y) - _, product = rxn.strip("()").split(',', maxsplit=2) - if "n" not in product: - msg = 'Unable to set "{0}" to "{1}"'.format("rxns_type", - rxn_type) + \ - " as it is not an accepted ArbitraryMatrixXS type." - raise ValueError(msg) - - # If we made it here, then we are good to go - self._rxn_type = rxn_type + self._rxn_type = rxn_type.split(" ")[0] self._estimator = 'analog' self._valid_estimators = ['analog'] diff --git a/src/reaction.cpp b/src/reaction.cpp index a5406fdb4a..3e4d3b9818 100644 --- a/src/reaction.cpp +++ b/src/reaction.cpp @@ -243,7 +243,7 @@ std::unordered_map REACTION_NAME_MAP { {N_3N3HE, "(n,3n3He)"}, {N_4N3HE, "(n,4n3He)"}, {N_3N2P, "(n,3n2p)"}, - {N_3N3A, "(n,3n3a)"}, + {N_3N2A, "(n,3n2a)"}, {N_3NPA, "(n,3npa)"}, {N_DT, "(n,dt)"}, {N_NPD, "(n,npd)"}, diff --git a/tests/regression_tests/mgxs_library_no_nuclides/inputs_true.dat b/tests/regression_tests/mgxs_library_no_nuclides/inputs_true.dat index e629fa115e..4da22946bf 100644 --- a/tests/regression_tests/mgxs_library_no_nuclides/inputs_true.dat +++ b/tests/regression_tests/mgxs_library_no_nuclides/inputs_true.dat @@ -68,13 +68,13 @@ 0.0 20000000.0 - + 1 2 3 4 5 6 - + 2 - + 3 @@ -438,883 +438,19747 @@ tracklength - 1 73 2 + 1 2 total - delayed-nu-fission + (n,elastic) tracklength - 1 73 52 + 1 2 total - delayed-nu-fission - analog + flux + tracklength - 1 73 5 + 1 2 total - delayed-nu-fission - analog + (n,level) + tracklength 1 2 total - nu-fission + flux tracklength - 1 73 2 + 1 2 total - delayed-nu-fission + (n,2nd) tracklength - 1 73 + 1 2 total - delayed-nu-fission + flux tracklength - 1 73 + 1 2 total - decay-rate + (n,2n) tracklength 1 2 total flux - analog + tracklength - 1 73 2 5 + 1 2 total - delayed-nu-fission - analog + (n,3n) + tracklength - 87 2 + 1 2 total flux tracklength - 87 2 + 1 2 total - total + (n,na) tracklength - 87 2 + 1 2 total flux tracklength - 87 2 + 1 2 total - total + (n,n3a) tracklength - 87 2 + 1 2 total flux - analog + tracklength - 87 5 6 + 1 2 total - scatter - analog + (n,2na) + tracklength - 87 2 + 1 2 total flux tracklength - 87 2 + 1 2 total - total + (n,3na) tracklength - 87 2 + 1 2 total flux - analog + tracklength - 87 5 6 + 1 2 total - nu-scatter - analog + (n,np) + tracklength - 87 2 + 1 2 total flux tracklength - 87 2 + 1 2 total - absorption + (n,n2a) tracklength - 87 2 + 1 2 total flux tracklength - 87 2 + 1 2 total - absorption + (n,2n2a) tracklength - 87 2 + 1 2 total - fission + flux tracklength - 87 2 + 1 2 total - flux + (n,nd) tracklength - 87 2 + 1 2 total - fission + flux tracklength - 87 2 + 1 2 total - flux + (n,nt) tracklength - 87 2 + 1 2 total - nu-fission + flux tracklength - 87 2 + 1 2 total - flux + (n,n3He) tracklength - 87 2 + 1 2 total - kappa-fission + flux tracklength - 87 2 + 1 2 total - flux + (n,nd2a) tracklength - 87 2 + 1 2 total - scatter + flux tracklength - 87 2 + 1 2 total - flux - analog + (n,nt2a) + tracklength - 87 2 + 1 2 total - nu-scatter - analog + flux + tracklength - 87 2 + 1 2 total - flux - analog + (n,4n) + tracklength - 87 2 5 28 + 1 2 total - scatter - analog + flux + tracklength - 87 2 + 1 2 total - flux - analog + (n,2np) + tracklength - 87 2 5 28 - total - nu-scatter - analog - - - 87 2 5 - total - nu-scatter - analog - - - 87 2 5 - total - scatter - analog - - - 87 2 + 1 2 total flux - analog + tracklength + + + 1 2 + total + (n,3np) + tracklength + + + 1 2 + total + flux + tracklength + + + 1 2 + total + (n,n2p) + tracklength - 87 2 5 + 1 2 total - nu-fission - analog + flux + tracklength - 87 2 5 + 1 2 total - scatter - analog + (n,npa) + tracklength - 87 2 + 1 2 total flux tracklength - 87 2 + 1 2 total - scatter + (n,nc) tracklength - 87 2 5 28 - total - scatter - analog - - - 87 2 + 1 2 total flux tracklength + + 1 2 + total + (n,disappear) + tracklength + - 87 2 + 1 2 total - scatter + flux tracklength - 87 2 5 28 + 1 2 total - scatter - analog + (n,gamma) + tracklength - 87 2 5 - total - nu-scatter - analog - - - 87 52 - total - nu-fission - analog - - - 87 5 - total - nu-fission - analog - - - 87 52 - total - prompt-nu-fission - analog - - - 87 5 - total - prompt-nu-fission - analog - - - 87 2 + 1 2 total flux tracklength + + 1 2 + total + (n,p) + tracklength + + + 1 2 + total + flux + tracklength + + + 1 2 + total + (n,d) + tracklength + + + 1 2 + total + flux + tracklength + + + 1 2 + total + (n,t) + tracklength + - 87 2 + 1 2 total - inverse-velocity + flux tracklength - 87 2 + 1 2 total - flux + (n,3He) tracklength - 87 2 + 1 2 total - prompt-nu-fission + flux tracklength - 87 2 + 1 2 total - flux - analog + (n,a) + tracklength - 87 2 5 - total - prompt-nu-fission - analog - - - 87 2 + 1 2 total flux tracklength + + 1 2 + total + (n,2a) + tracklength + - 87 2 + 1 2 total - total + flux tracklength - 87 2 + 1 2 total - flux - analog + (n,3a) + tracklength - 87 5 6 - total - scatter - analog - - - 87 2 + 1 2 total flux tracklength + + 1 2 + total + (n,2p) + tracklength + - 87 2 + 1 2 total - total + flux tracklength - 87 2 + 1 2 total - flux - analog + (n,pa) + tracklength - 87 5 6 - total - nu-scatter - analog - - - 87 2 + 1 2 total flux tracklength + + 1 2 + total + (n,t2a) + tracklength + - 87 73 2 + 1 2 total - delayed-nu-fission + flux tracklength - 87 73 52 + 1 2 total - delayed-nu-fission - analog + (n,d2a) + tracklength - 87 73 5 + 1 2 total - delayed-nu-fission - analog + flux + tracklength - 87 2 + 1 2 total - nu-fission + (n,pd) tracklength - 87 73 2 + 1 2 total - delayed-nu-fission + flux tracklength - 87 73 + 1 2 total - delayed-nu-fission + (n,pt) tracklength - 87 73 + 1 2 total - decay-rate + flux tracklength - 87 2 + 1 2 total - flux - analog + (n,da) + tracklength - 87 73 2 5 - total - delayed-nu-fission - analog - - - 173 2 + 1 2 total flux tracklength + + 1 2 + total + (n,5n) + tracklength + - 173 2 + 1 2 total - total + flux tracklength - 173 2 + 1 2 total - flux + (n,6n) tracklength - 173 2 + 1 2 total - total + flux tracklength - 173 2 + 1 2 total - flux - analog + (n,2nt) + tracklength - 173 5 6 - total - scatter - 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analog + (n,7np) + tracklength - 173 2 + 1 2 total flux - analog + tracklength - 173 2 5 28 + 1 2 total - scatter - analog + (n,4na) + tracklength - 173 2 + 1 2 total flux - analog + tracklength - 173 2 5 28 + 1 2 total - nu-scatter - analog + (n,5na) + tracklength - 173 2 5 + 1 2 total - nu-scatter - analog + flux + tracklength - 173 2 5 + 1 2 total - scatter - analog + (n,6na) + tracklength - 173 2 + 1 2 total flux - analog + tracklength - 173 2 5 + 1 2 total - nu-fission - analog + (n,7na) + tracklength - 173 2 5 - total - scatter - analog - - - 173 2 + 1 2 total flux tracklength + + 1 2 + total + (n,4nd) + tracklength + - 173 2 + 1 2 total - scatter + flux tracklength - 173 2 5 28 + 1 2 total - scatter - analog + (n,5nd) + tracklength - 173 2 + 1 2 total flux tracklength - 173 2 + 1 2 total - scatter + (n,6nd) tracklength - 173 2 5 28 + 1 2 total - scatter - analog + flux + tracklength - 173 2 5 + 1 2 total - nu-scatter - analog + (n,3nt) + tracklength - 173 52 + 1 2 total - 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total + delayed-nu-fission + analog + + + 2511 2 + total + nu-fission + tracklength + + + 2511 1242 2 + total + delayed-nu-fission + tracklength + + + 2511 1242 + total + delayed-nu-fission + tracklength + + + 2511 1242 + total + decay-rate + tracklength + + + 2511 2 + total + flux + analog + + + 2511 1242 2 5 total delayed-nu-fission analog diff --git a/tests/regression_tests/mgxs_library_no_nuclides/results_true.dat b/tests/regression_tests/mgxs_library_no_nuclides/results_true.dat index 4dfb7f68a4..603a1a97fd 100644 --- a/tests/regression_tests/mgxs_library_no_nuclides/results_true.dat +++ b/tests/regression_tests/mgxs_library_no_nuclides/results_true.dat @@ -1,33 +1,44 @@ +total material group in nuclide mean std. dev. 1 1 1 total 0.414825 0.022793 0 1 2 total 0.660170 0.047519 +transport material group in nuclide mean std. dev. 1 1 1 total 0.363092 0.023838 0 1 2 total 0.644851 0.047675 +nu-transport material group in nuclide mean std. dev. 1 1 1 total 0.363092 0.023838 0 1 2 total 0.644851 0.047675 +absorption material group in nuclide mean std. dev. 1 1 1 total 0.027408 0.002692 0 1 2 total 0.264511 0.023367 +capture material group in nuclide mean std. dev. 1 1 1 total 0.019845 0.002643 0 1 2 total 0.071719 0.025208 +fission material group in nuclide mean std. dev. 1 1 1 total 0.007563 0.000508 0 1 2 total 0.192791 0.017106 +nu-fission material group in nuclide mean std. dev. 1 1 1 total 0.019432 0.001323 0 1 2 total 0.469775 0.041682 +kappa-fission material group in nuclide mean std. dev. 1 1 1 total 1.474570e+06 9.923536e+04 0 1 2 total 3.728689e+07 3.308375e+06 +scatter material group in nuclide mean std. dev. 1 1 1 total 0.387418 0.020626 0 1 2 total 0.395659 0.025125 +nu-scatter material group in nuclide mean std. dev. 1 1 1 total 0.385188 0.026946 0 1 2 total 0.412389 0.015425 +scatter matrix material group in group out legendre nuclide mean std. dev. 12 1 1 1 P0 total 0.384199 0.027001 13 1 1 1 P1 total 0.051870 0.006983 @@ -45,6 +56,7 @@ 1 1 2 2 P1 total 0.016482 0.004502 2 1 2 2 P2 total 0.006371 0.010551 3 1 2 2 P3 total -0.010499 0.010438 +nu-scatter matrix material group in group out legendre nuclide mean std. dev. 12 1 1 1 P0 total 0.384199 0.027001 13 1 1 1 P1 total 0.051870 0.006983 @@ -62,21 +74,25 @@ 1 1 2 2 P1 total 0.016482 0.004502 2 1 2 2 P2 total 0.006371 0.010551 3 1 2 2 P3 total -0.010499 0.010438 +multiplicity matrix material group in group out nuclide mean std. dev. 3 1 1 1 total 1.0 0.078516 2 1 1 2 total 1.0 0.687184 1 1 2 1 total 1.0 1.414214 0 1 2 2 total 1.0 0.041130 +nu-fission matrix material group in group out nuclide mean std. dev. 3 1 1 1 total 0.020142 0.003149 2 1 1 2 total 0.000000 0.000000 1 1 2 1 total 0.454366 0.027426 0 1 2 2 total 0.000000 0.000000 +scatter probability matrix material group in group out nuclide mean std. dev. 3 1 1 1 total 0.997433 0.078224 2 1 1 2 total 0.002567 0.001256 1 1 2 1 total 0.002242 0.002243 0 1 2 2 total 0.997758 0.041053 +consistent scatter matrix material 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group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,n34) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,n35) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,n36) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,n37) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,n38) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,n39) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,n40) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,2n0) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,2n1) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,2n2) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,2n3) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,2n4) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,2n5) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,2n6) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,2n7) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,2n8) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,2n9) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,2n10) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,2n11) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,2n12) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,2n13) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,2n14) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +(n,2n15) matrix + material group in group out nuclide mean std. dev. +3 1 1 1 total 0.0 0.0 +2 1 1 2 total 0.0 0.0 +1 1 2 1 total 0.0 0.0 +0 1 2 2 total 0.0 0.0 +delayed-nu-fission material delayedgroup group in nuclide mean std. dev. 1 1 1 1 total 0.000004 2.897486e-07 3 1 2 1 total 0.000027 1.850037e-06 @@ -151,6 +2514,7 @@ 6 1 4 2 total 0.001182 1.048679e-04 8 1 5 2 total 0.000485 4.299445e-05 10 1 6 2 total 0.000203 1.801022e-05 +chi-delayed material delayedgroup group out nuclide mean std. dev. 1 1 1 1 total 0.0 0.000000 3 1 2 1 total 1.0 0.869128 @@ -164,6 +2528,7 @@ 6 1 4 2 total 0.0 0.000000 8 1 5 2 total 0.0 0.000000 10 1 6 2 total 0.0 0.000000 +beta material delayedgroup group in nuclide mean std. dev. 1 1 1 1 total 0.000222 0.000018 3 1 2 1 total 0.001388 0.000115 @@ -177,6 +2542,7 @@ 6 1 4 2 total 0.002516 0.000273 8 1 5 2 total 0.001031 0.000112 10 1 6 2 total 0.000432 0.000047 +decay-rate material delayedgroup nuclide mean std. dev. 0 1 1 total 0.013355 0.001272 1 1 2 total 0.032600 0.003048 @@ -184,6 +2550,7 @@ 3 1 4 total 0.305910 0.027728 4 1 5 total 0.861934 0.075425 5 1 6 total 2.895065 0.253942 +delayed-nu-fission matrix material delayedgroup group in group out nuclide mean std. dev. 3 1 1 1 1 total 0.000000 0.000000 7 1 2 1 1 total 0.000000 0.000000 @@ -209,36 +2576,47 @@ 12 1 4 2 2 total 0.000000 0.000000 16 1 5 2 2 total 0.000000 0.000000 20 1 6 2 2 total 0.000000 0.000000 +total material group in nuclide mean std. dev. 1 2 1 total 0.313738 0.015582 0 2 2 total 0.300821 0.028052 +transport material group in nuclide mean std. dev. 1 2 1 total 0.275508 0.017742 0 2 2 total 0.312035 0.032384 +nu-transport material group in nuclide mean std. dev. 1 2 1 total 0.275508 0.017742 0 2 2 total 0.312035 0.032384 +absorption material group in nuclide mean std. dev. 1 2 1 total 0.001575 0.000323 0 2 2 total 0.005400 0.000618 +capture material group in nuclide mean std. dev. 1 2 1 total 0.001575 0.000323 0 2 2 total 0.005400 0.000618 +fission material group in nuclide mean std. dev. 1 2 1 total 0.0 0.0 0 2 2 total 0.0 0.0 +nu-fission material group in nuclide mean std. dev. 1 2 1 total 0.0 0.0 0 2 2 total 0.0 0.0 +kappa-fission material group in nuclide mean std. dev. 1 2 1 total 0.0 0.0 0 2 2 total 0.0 0.0 +scatter material group in nuclide mean std. dev. 1 2 1 total 0.312163 0.015322 0 2 2 total 0.295421 0.027446 +nu-scatter material group in nuclide mean std. dev. 1 2 1 total 0.310121 0.033788 0 2 2 total 0.296264 0.043792 +scatter matrix material group in group out legendre nuclide mean std. dev. 12 2 1 1 P0 total 0.310121 0.033788 13 2 1 1 P1 total 0.038230 0.008484 @@ -256,6 +2634,7 @@ 1 2 2 2 P1 total -0.011214 0.016180 2 2 2 2 P2 total 0.008837 0.011504 3 2 2 2 P3 total -0.003270 0.007329 +nu-scatter matrix material group in group out legendre nuclide mean std. dev. 12 2 1 1 P0 total 0.310121 0.033788 13 2 1 1 P1 total 0.038230 0.008484 @@ -273,21 +2652,25 @@ 1 2 2 2 P1 total -0.011214 0.016180 2 2 2 2 P2 total 0.008837 0.011504 3 2 2 2 P3 total -0.003270 0.007329 +multiplicity matrix material group in group out nuclide mean std. dev. 3 2 1 1 total 1.0 0.108779 2 2 1 2 total 0.0 0.000000 1 2 2 1 total 0.0 0.000000 0 2 2 2 total 1.0 0.142427 +nu-fission matrix material group in group out nuclide mean std. dev. 3 2 1 1 total 0.0 0.0 2 2 1 2 total 0.0 0.0 1 2 2 1 total 0.0 0.0 0 2 2 2 total 0.0 0.0 +scatter probability matrix material group in group out nuclide mean std. dev. 3 2 1 1 total 1.0 0.108779 2 2 1 2 total 0.0 0.000000 1 2 2 1 total 0.0 0.000000 0 2 2 2 total 1.0 0.142427 +consistent scatter matrix material group in group out legendre nuclide mean std. dev. 12 2 1 1 P0 total 0.312163 0.037253 13 2 1 1 P1 total 0.038481 0.008743 @@ -305,6 +2688,7 @@ 1 2 2 2 P1 total -0.011182 0.016162 2 2 2 2 P2 total 0.008811 0.011495 3 2 2 2 P3 total -0.003261 0.007313 +consistent nu-scatter matrix material group in group out legendre nuclide mean std. dev. 12 2 1 1 P0 total 0.312163 0.050407 13 2 1 1 P1 total 0.038481 0.009693 @@ -322,33 +2706,2379 @@ 1 2 2 2 P1 total -0.011182 0.016240 2 2 2 2 P2 total 0.008811 0.011563 3 2 2 2 P3 total -0.003261 0.007328 +chi material group out nuclide mean std. dev. 1 2 1 total 0.0 0.0 0 2 2 total 0.0 0.0 +chi-prompt material group out nuclide mean std. dev. 1 2 1 total 0.0 0.0 0 2 2 total 0.0 0.0 +inverse-velocity material group in nuclide mean std. dev. 1 2 1 total 5.995979e-08 4.553085e-09 0 2 2 total 2.985490e-06 3.417020e-07 +prompt-nu-fission material group in nuclide mean std. dev. 1 2 1 total 0.0 0.0 0 2 2 total 0.0 0.0 +prompt-nu-fission matrix material group in group out nuclide mean std. dev. 3 2 1 1 total 0.0 0.0 2 2 1 2 total 0.0 0.0 1 2 2 1 total 0.0 0.0 0 2 2 2 total 0.0 0.0 +diffusion-coefficient material group in legendre nuclide mean std. dev. 2 2 1 P0 total 92.158584 948.055013 3 2 1 P1 total 1.209886 0.097583 0 2 2 P0 total 73.145434 834.775399 1 2 2 P1 total 1.068256 0.148711 +nu-diffusion-coefficient material group in legendre nuclide mean std. dev. 2 2 1 P0 total 92.158584 948.055013 3 2 1 P1 total 1.209886 0.097583 0 2 2 P0 total 73.145434 834.775399 1 2 2 P1 total 1.068256 0.148711 +(n,elastic) + material group in nuclide mean std. dev. +1 2 1 total 0.301031 0.014977 +0 2 2 total 0.295421 0.027446 +(n,level) + material group in nuclide mean 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nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,nd) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,nt) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n3He) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,nd2a) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,nt2a) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,4n) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2np) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,3np) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n2p) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,npa) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,nc) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.001782 0.000845 +2 2 1 2 total 0.000000 0.000000 +1 2 2 1 total 0.000000 0.000000 +0 2 2 2 total 0.000000 0.000000 +(n,5n) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,6n) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2nt) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,4np) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,3nd) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,nda) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2npa) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,7n) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,8n) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,5np) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,6np) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,7np) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,4na) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,5na) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,6na) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,7na) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,4nd) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,5nd) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,6nd) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,3nt) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,4nt) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,5nt) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,6nt) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n3He) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,3n3He) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,4n3He) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,3n2p) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,3n2a) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,3npa) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,npd) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,npt) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,ndt) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,np3He) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,nd3He) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,nt3He) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,nta) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n2p) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,4n2p) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,4n2a) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,4npa) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n3p) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,3n2pa) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,5n2p) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2nc) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n1) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.002228 0.000725 +2 2 1 2 total 0.000000 0.000000 +1 2 2 1 total 0.000000 0.000000 +0 2 2 2 total 0.000000 0.000000 +(n,n2) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.002673 0.000859 +2 2 1 2 total 0.000000 0.000000 +1 2 2 1 total 0.000000 0.000000 +0 2 2 2 total 0.000000 0.000000 +(n,n3) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.000891 0.00055 +2 2 1 2 total 0.000000 0.00000 +1 2 2 1 total 0.000000 0.00000 +0 2 2 2 total 0.000000 0.00000 +(n,n4) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n5) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n6) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n7) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.000446 0.000447 +2 2 1 2 total 0.000000 0.000000 +1 2 2 1 total 0.000000 0.000000 +0 2 2 2 total 0.000000 0.000000 +(n,n8) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n9) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n10) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n11) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n12) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n13) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n14) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n15) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n16) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n17) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n18) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n19) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n20) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n21) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n22) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n23) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n24) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n25) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n26) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n27) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n28) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n29) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n30) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n31) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n32) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n33) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n34) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n35) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n36) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n37) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n38) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n39) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,n40) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n0) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n1) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n2) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n3) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n4) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n5) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n6) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n7) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n8) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n9) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n10) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n11) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n12) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n13) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n14) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +(n,2n15) matrix + material group in group out nuclide mean std. dev. +3 2 1 1 total 0.0 0.0 +2 2 1 2 total 0.0 0.0 +1 2 2 1 total 0.0 0.0 +0 2 2 2 total 0.0 0.0 +delayed-nu-fission material delayedgroup group in nuclide mean std. dev. 1 2 1 1 total 0.0 0.0 3 2 2 1 total 0.0 0.0 @@ -362,6 +5092,7 @@ 6 2 4 2 total 0.0 0.0 8 2 5 2 total 0.0 0.0 10 2 6 2 total 0.0 0.0 +chi-delayed material delayedgroup group out nuclide mean std. dev. 1 2 1 1 total 0.0 0.0 3 2 2 1 total 0.0 0.0 @@ -375,6 +5106,7 @@ 6 2 4 2 total 0.0 0.0 8 2 5 2 total 0.0 0.0 10 2 6 2 total 0.0 0.0 +beta material delayedgroup group in nuclide mean std. dev. 1 2 1 1 total 0.0 0.0 3 2 2 1 total 0.0 0.0 @@ -388,6 +5120,7 @@ 6 2 4 2 total 0.0 0.0 8 2 5 2 total 0.0 0.0 10 2 6 2 total 0.0 0.0 +decay-rate material delayedgroup nuclide mean std. dev. 0 2 1 total 0.0 0.0 1 2 2 total 0.0 0.0 @@ -395,6 +5128,7 @@ 3 2 4 total 0.0 0.0 4 2 5 total 0.0 0.0 5 2 6 total 0.0 0.0 +delayed-nu-fission matrix material delayedgroup group in group out nuclide mean std. dev. 3 2 1 1 1 total 0.0 0.0 7 2 2 1 1 total 0.0 0.0 @@ -420,36 +5154,47 @@ 12 2 4 2 2 total 0.0 0.0 16 2 5 2 2 total 0.0 0.0 20 2 6 2 2 total 0.0 0.0 +total material group in nuclide mean std. dev. 1 3 1 total 0.664572 0.031215 0 3 2 total 2.052384 0.224343 +transport material group in nuclide mean std. dev. 1 3 1 total 0.283323 0.035206 0 3 2 total 1.499740 0.230902 +nu-transport material group in nuclide mean std. dev. 1 3 1 total 0.283323 0.035206 0 3 2 total 1.499740 0.230902 +absorption material group in nuclide mean std. dev. 1 3 1 total 0.000690 0.000044 0 3 2 total 0.031687 0.003747 +capture material group in nuclide mean std. dev. 1 3 1 total 0.000690 0.000044 0 3 2 total 0.031687 0.003747 +fission material group in nuclide mean std. dev. 1 3 1 total 0.0 0.0 0 3 2 total 0.0 0.0 +nu-fission material group in nuclide mean std. dev. 1 3 1 total 0.0 0.0 0 3 2 total 0.0 0.0 +kappa-fission material group in nuclide mean std. dev. 1 3 1 total 0.0 0.0 0 3 2 total 0.0 0.0 +scatter material group in nuclide mean std. dev. 1 3 1 total 0.663882 0.031173 0 3 2 total 2.020697 0.220604 +nu-scatter material group in nuclide mean std. dev. 1 3 1 total 0.671269 0.026186 0 3 2 total 2.035388 0.258060 +scatter matrix material group in group out legendre nuclide mean std. dev. 12 3 1 1 P0 total 0.639901 0.024709 13 3 1 1 P1 total 0.381167 0.016243 @@ -467,6 +5212,7 @@ 1 3 2 2 P1 total 0.509940 0.051236 2 3 2 2 P2 total 0.111175 0.013020 3 3 2 2 P3 total 0.024988 0.008312 +nu-scatter matrix material group in group out legendre nuclide mean std. dev. 12 3 1 1 P0 total 0.639901 0.024709 13 3 1 1 P1 total 0.381167 0.016243 @@ -484,21 +5230,25 @@ 1 3 2 2 P1 total 0.509940 0.051236 2 3 2 2 P2 total 0.111175 0.013020 3 3 2 2 P3 total 0.024988 0.008312 +multiplicity matrix material group in group out nuclide mean std. dev. 3 3 1 1 total 1.0 0.038609 2 3 1 2 total 1.0 0.067667 1 3 2 1 total 1.0 1.414214 0 3 2 2 total 1.0 0.135929 +nu-fission matrix material group in group out nuclide mean std. dev. 3 3 1 1 total 0.0 0.0 2 3 1 2 total 0.0 0.0 1 3 2 1 total 0.0 0.0 0 3 2 2 total 0.0 0.0 +scatter probability matrix material group in group out nuclide mean std. dev. 3 3 1 1 total 0.953271 0.036018 2 3 1 2 total 0.046729 0.002547 1 3 2 1 total 0.000218 0.000219 0 3 2 2 total 0.999782 0.135885 +consistent scatter matrix material group in group out legendre nuclide mean std. dev. 12 3 1 1 P0 total 0.632859 0.038142 13 3 1 1 P1 total 0.376973 0.023715 @@ -516,6 +5266,7 @@ 1 3 2 2 P1 total 0.506260 0.079140 2 3 2 2 P2 total 0.110372 0.018488 3 3 2 2 P3 total 0.024808 0.008771 +consistent nu-scatter matrix material group in group out legendre nuclide mean std. dev. 12 3 1 1 P0 total 0.632859 0.045297 13 3 1 1 P1 total 0.376973 0.027825 @@ -533,33 +5284,2379 @@ 1 3 2 2 P1 total 0.506260 0.104875 2 3 2 2 P2 total 0.110372 0.023809 3 3 2 2 P3 total 0.024808 0.009397 +chi material group out nuclide mean std. dev. 1 3 1 total 0.0 0.0 0 3 2 total 0.0 0.0 +chi-prompt material group out nuclide mean std. dev. 1 3 1 total 0.0 0.0 0 3 2 total 0.0 0.0 +inverse-velocity material group in nuclide mean std. dev. 1 3 1 total 6.022078e-08 3.780437e-09 0 3 2 total 3.044955e-06 3.600077e-07 +prompt-nu-fission material group in nuclide mean std. dev. 1 3 1 total 0.0 0.0 0 3 2 total 0.0 0.0 +prompt-nu-fission matrix material group in group out nuclide mean std. dev. 3 3 1 1 total 0.0 0.0 2 3 1 2 total 0.0 0.0 1 3 2 1 total 0.0 0.0 0 3 2 2 total 0.0 0.0 +diffusion-coefficient material group in legendre nuclide mean std. dev. 2 3 1 P0 total 13.561252 21.988396 3 3 1 P1 total 1.176515 0.154807 0 3 2 P0 total -2.459765 6.393743 1 3 2 P1 total 0.222261 0.040518 +nu-diffusion-coefficient material group in legendre nuclide mean std. dev. 2 3 1 P0 total 13.561252 21.988396 3 3 1 P1 total 1.176515 0.154807 0 3 2 P0 total -2.459765 6.393743 1 3 2 P1 total 0.222261 0.040518 +(n,elastic) + material group in nuclide mean std. dev. +1 3 1 total 0.663837 0.031175 +0 3 2 total 2.020697 0.220604 +(n,level) + material group in nuclide mean std. dev. +1 3 1 total 0.000045 0.000027 +0 3 2 total 0.000000 0.000000 +(n,2nd) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,2n) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,3n) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,na) + material group in nuclide mean std. dev. +1 3 1 total 6.743945e-11 6.604830e-11 +0 3 2 total 0.000000e+00 0.000000e+00 +(n,n3a) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,2na) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,3na) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,np) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,n2a) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,2n2a) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,nd) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,nt) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,n3He) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,nd2a) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,nt2a) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,4n) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,2np) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,3np) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,n2p) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,npa) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,nc) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,disappear) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,gamma) + material group in nuclide mean std. dev. +1 3 1 total 0.000219 0.000014 +0 3 2 total 0.011034 0.001305 +(n,p) + material group in nuclide mean std. dev. +1 3 1 total 3.105883e-08 2.515704e-09 +0 3 2 total 3.042510e-09 3.597211e-10 +(n,d) + material group in nuclide mean std. dev. +1 3 1 total 3.501368e-09 9.905391e-10 +0 3 2 total 0.000000e+00 0.000000e+00 +(n,t) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,3He) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,a) + material group in nuclide mean std. dev. +1 3 1 total 0.000471 0.000031 +0 3 2 total 0.020653 0.002442 +(n,2a) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,3a) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,2p) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,pa) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,t2a) + material group in nuclide mean std. dev. +1 3 1 total 1.307412e-07 1.166081e-08 +0 3 2 total 3.762551e-08 4.448547e-09 +(n,d2a) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,pd) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,pt) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,da) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,5n) + material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 +(n,6n) + material group in 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0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n2p) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,npa) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,nc) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,5n) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,6n) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2nt) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,4np) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,3nd) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,nda) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2npa) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,7n) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,8n) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,5np) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,6np) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,7np) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,4na) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,5na) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,6na) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,7na) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,4nd) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,5nd) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,6nd) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,3nt) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,4nt) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,5nt) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,6nt) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n3He) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,3n3He) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,4n3He) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,3n2p) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,3n2a) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,3npa) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,npd) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,npt) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,ndt) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,np3He) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,nd3He) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,nt3He) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,nta) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n2p) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,4n2p) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,4n2a) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,4npa) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n3p) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,3n2pa) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,5n2p) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2nc) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n1) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n2) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n3) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n4) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n5) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n6) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n7) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n8) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n9) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n10) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n11) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n12) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n13) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n14) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n15) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n16) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n17) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n18) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n19) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n20) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n21) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n22) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n23) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n24) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n25) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n26) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n27) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n28) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n29) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n30) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n31) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n32) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n33) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n34) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n35) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n36) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n37) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n38) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n39) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,n40) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n0) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n1) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n2) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n3) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n4) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n5) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n6) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n7) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n8) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n9) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n10) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n11) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n12) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n13) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n14) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +(n,2n15) matrix + material group in group out nuclide mean std. dev. +3 3 1 1 total 0.0 0.0 +2 3 1 2 total 0.0 0.0 +1 3 2 1 total 0.0 0.0 +0 3 2 2 total 0.0 0.0 +delayed-nu-fission material delayedgroup group in nuclide mean std. dev. 1 3 1 1 total 0.0 0.0 3 3 2 1 total 0.0 0.0 @@ -573,6 +7670,7 @@ 6 3 4 2 total 0.0 0.0 8 3 5 2 total 0.0 0.0 10 3 6 2 total 0.0 0.0 +chi-delayed material delayedgroup group out nuclide mean std. dev. 1 3 1 1 total 0.0 0.0 3 3 2 1 total 0.0 0.0 @@ -586,6 +7684,7 @@ 6 3 4 2 total 0.0 0.0 8 3 5 2 total 0.0 0.0 10 3 6 2 total 0.0 0.0 +beta material delayedgroup group in nuclide mean std. dev. 1 3 1 1 total 0.0 0.0 3 3 2 1 total 0.0 0.0 @@ -599,6 +7698,7 @@ 6 3 4 2 total 0.0 0.0 8 3 5 2 total 0.0 0.0 10 3 6 2 total 0.0 0.0 +decay-rate material delayedgroup nuclide mean std. dev. 0 3 1 total 0.0 0.0 1 3 2 total 0.0 0.0 @@ -606,6 +7706,7 @@ 3 3 4 total 0.0 0.0 4 3 5 total 0.0 0.0 5 3 6 total 0.0 0.0 +delayed-nu-fission matrix material delayedgroup group in group out nuclide mean std. dev. 3 3 1 1 1 total 0.0 0.0 7 3 2 1 1 total 0.0 0.0 diff --git a/tests/regression_tests/mgxs_library_no_nuclides/test.py b/tests/regression_tests/mgxs_library_no_nuclides/test.py index f005c095ec..fdde8ca982 100644 --- a/tests/regression_tests/mgxs_library_no_nuclides/test.py +++ b/tests/regression_tests/mgxs_library_no_nuclides/test.py @@ -2,6 +2,7 @@ import hashlib import openmc import openmc.mgxs +from openmc.data import REACTION_MT from openmc.examples import pwr_pin_cell from tests.testing_harness import PyAPITestHarness @@ -22,6 +23,8 @@ class MGXSTestHarness(PyAPITestHarness): # Test all relevant MGXS types relevant_MGXS_TYPES = [item for item in openmc.mgxs.MGXS_TYPES if item != 'current'] + relevant_MGXS_TYPES += openmc.mgxs.ARBITRARY_VECTOR_TYPES + relevant_MGXS_TYPES += openmc.mgxs.ARBITRARY_MATRIX_TYPES self.mgxs_lib.mgxs_types = tuple(relevant_MGXS_TYPES) + \ openmc.mgxs.MDGXS_TYPES self.mgxs_lib.energy_groups = energy_groups @@ -48,7 +51,7 @@ class MGXSTestHarness(PyAPITestHarness): for mgxs_type in self.mgxs_lib.mgxs_types: mgxs = self.mgxs_lib.get_mgxs(domain, mgxs_type) df = mgxs.get_pandas_dataframe() - outstr += df.to_string() + '\n' + outstr += mgxs_type + '\n' + df.to_string() + '\n' # Hash the results if necessary if hash_output: diff --git a/tests/regression_tests/mgxs_library_nuclides/inputs_true.dat b/tests/regression_tests/mgxs_library_nuclides/inputs_true.dat index dc63ef0cbf..045b0ab8e2 100644 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B11 + (n,3n2a) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,3npa) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,npd) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,npt) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,ndt) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,np3He) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,nd3He) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,nt3He) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,nta) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2n2p) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,4n2p) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,4n2a) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,4npa) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n3p) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,3n2pa) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,5n2p) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2nc) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n1) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n2) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n3) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n4) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n5) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n6) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n7) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n8) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n9) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n10) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n11) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n12) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n13) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n14) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n15) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n16) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n17) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n18) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n19) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n20) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n21) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n22) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n23) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n24) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n25) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n26) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n27) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n28) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n29) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n30) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n31) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n32) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n33) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n34) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n35) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n36) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n37) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n38) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n39) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,n40) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2n0) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2n1) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2n2) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2n3) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2n4) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2n5) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2n6) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2n7) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2n8) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2n9) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2n10) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2n11) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2n12) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2n13) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2n14) + analog + + + 2479 2 + total + flux + analog + + + 2479 2 5 + H1 O16 B10 B11 + (n,2n15) + analog + diff --git a/tests/regression_tests/mgxs_library_nuclides/results_true.dat b/tests/regression_tests/mgxs_library_nuclides/results_true.dat index 1a93a03188..0b0349aacc 100644 --- a/tests/regression_tests/mgxs_library_nuclides/results_true.dat +++ b/tests/regression_tests/mgxs_library_nuclides/results_true.dat @@ -1 +1 @@ -14f7fb2e399a4ad124b25b88dda5104d43cca9192aa1c17261da40bcc0e4394e56781f42f79c90107d0ff6b3e901f034bed09b037670e60b9ac4009b3805e17d \ No newline at end of file +7462fdc05825053847d93b9238b57d47ab5eb9244542279489a23b2a87423e7e58d22efa9b6db7db74ab9628b73ff37750af3de60102da5ad05f69700a1b3b8d \ No newline at end of file diff --git a/tests/regression_tests/mgxs_library_nuclides/test.py b/tests/regression_tests/mgxs_library_nuclides/test.py index 87a65723c5..0305e00793 100644 --- a/tests/regression_tests/mgxs_library_nuclides/test.py +++ b/tests/regression_tests/mgxs_library_nuclides/test.py @@ -21,6 +21,8 @@ class MGXSTestHarness(PyAPITestHarness): # Test relevant all MGXS types relevant_MGXS_TYPES = [item for item in openmc.mgxs.MGXS_TYPES if item != 'current'] + relevant_MGXS_TYPES += openmc.mgxs.ARBITRARY_VECTOR_TYPES + relevant_MGXS_TYPES += openmc.mgxs.ARBITRARY_MATRIX_TYPES self.mgxs_lib.mgxs_types = tuple(relevant_MGXS_TYPES) self.mgxs_lib.energy_groups = energy_groups self.mgxs_lib.legendre_order = 3 From 8f71ed2a1dc488f0f99ce4a0aebe8a624ae1ea1f Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Thu, 15 Oct 2020 16:41:13 -0500 Subject: [PATCH 39/79] Store sites from source file in SourceDistribution --- include/openmc/settings.h | 1 - include/openmc/source.h | 1 + include/openmc/state_point.h | 4 +- src/settings.cpp | 1 - src/source.cpp | 76 +++++++++++++++++++----------------- src/state_point.cpp | 24 +++++++----- 6 files changed, 58 insertions(+), 49 deletions(-) diff --git a/include/openmc/settings.h b/include/openmc/settings.h index 85ef1c71ea..c743cf7210 100644 --- a/include/openmc/settings.h +++ b/include/openmc/settings.h @@ -59,7 +59,6 @@ extern std::string path_cross_sections; //!< path to cross_sections.xml extern std::string path_input; //!< directory where main .xml files resides extern std::string path_output; //!< directory where output files are written extern std::string path_particle_restart; //!< path to a particle restart file -extern std::string path_source; extern std::string path_source_library; //!< path to the source shared object extern std::string path_sourcepoint; //!< path to a source file extern "C" std::string path_statepoint; //!< path to a statepoint file diff --git a/include/openmc/source.h b/include/openmc/source.h index 529cb1836e..e47c918516 100644 --- a/include/openmc/source.h +++ b/include/openmc/source.h @@ -57,6 +57,7 @@ private: UPtrSpace space_; //!< Spatial distribution UPtrAngle angle_; //!< Angular distribution UPtrDist energy_; //!< Energy distribution + std::vector sites_; //!< Source sites from a file }; class CustomSource { diff --git a/include/openmc/state_point.h b/include/openmc/state_point.h index 4a901ac2a2..31dffc9ee9 100644 --- a/include/openmc/state_point.h +++ b/include/openmc/state_point.h @@ -2,17 +2,19 @@ #define OPENMC_STATE_POINT_H #include +#include #include "hdf5.h" #include "openmc/capi.h" +#include "openmc/particle.h" namespace openmc { void load_state_point(); void write_source_point(const char* filename); void write_source_bank(hid_t group_id); -void read_source_bank(hid_t group_id); +void read_source_bank(hid_t group_id, std::vector& sites); void write_tally_results_nr(hid_t file_id); void restart_set_keff(); diff --git a/src/settings.cpp b/src/settings.cpp index 8e402b7110..cab7c6c11b 100644 --- a/src/settings.cpp +++ b/src/settings.cpp @@ -73,7 +73,6 @@ std::string path_cross_sections; std::string path_input; std::string path_output; std::string path_particle_restart; -std::string path_source; std::string path_source_library; std::string path_sourcepoint; std::string path_statepoint; diff --git a/src/source.cpp b/src/source.cpp index 4f4ad117bb..91a5f78cc3 100644 --- a/src/source.cpp +++ b/src/source.cpp @@ -82,13 +82,35 @@ SourceDistribution::SourceDistribution(pugi::xml_node node) // Check for external source file if (check_for_node(node, "file")) { // Copy path of source file - settings::path_source = get_node_value(node, "file", false, true); + auto path_source = get_node_value(node, "file", false, true); // Check if source file exists - if (!file_exists(settings::path_source)) { - fatal_error(fmt::format("Source file '{}' does not exist.", - settings::path_source)); + if (!file_exists(path_source)) { + fatal_error(fmt::format("Source file '{}' does not exist.", path_source)); } + + // Read the source from a binary file instead of sampling from some + // assumed source distribution + write_message(6, "Reading source file from {}...", path_source); + + // Open the binary file + hid_t file_id = file_open(path_source, 'r', true); + + // Read the file type + std::string filetype; + read_attribute(file_id, "filetype", filetype); + + // Check to make sure this is a source file + if (filetype != "source" && filetype != "statepoint") { + fatal_error("Specified starting source file not a source file type."); + } + + // Read in the source bank + read_source_bank(file_id, sites_); + + // Close file + file_close(file_id); + } else if (check_for_node(node, "library")) { settings::path_source_library = get_node_value(node, "library", false, true); if (!file_exists(settings::path_source_library)) { @@ -180,15 +202,20 @@ Particle::Bank SourceDistribution::sample(uint64_t* seed) const int n_reject = 0; static int n_accept = 0; while (!found) { - // Set particle type - site.particle = particle_; + if (!sites_.empty()) { + size_t i_site = sites_.size()*prn(seed); + site = sites_[i_site]; + } else { + // Set particle type + site.particle = particle_; - // Sample spatial distribution - site.r = space_->sample(seed); - double xyz[] {site.r.x, site.r.y, site.r.z}; + // Sample spatial distribution + site.r = space_->sample(seed); + } // Now search to see if location exists in geometry int32_t cell_index, instance; + double xyz[] {site.r.x, site.r.y, site.r.z}; int err = openmc_find_cell(xyz, &cell_index, &instance); found = (err != OPENMC_E_GEOMETRY); @@ -225,6 +252,8 @@ Particle::Bank SourceDistribution::sample(uint64_t* seed) const // Increment number of accepted samples ++n_accept; + if (!sites_.empty()) return site; + // Sample angle site.u = angle_->sample(seed); @@ -264,33 +293,8 @@ void initialize_source() { write_message("Initializing source particles...", 5); - if (!settings::path_source.empty()) { - // Read the source from a binary file instead of sampling from some - // assumed source distribution - - write_message(6, "Reading source file from {}...", settings::path_source); - - // Open the binary file - hid_t file_id = file_open(settings::path_source, 'r', true); - - // Read the file type - std::string filetype; - read_attribute(file_id, "filetype", filetype); - - // Check to make sure this is a source file - if (filetype != "source" && filetype != "statepoint") { - fatal_error("Specified starting source file not a source file type."); - } - - // Read in the source bank - read_source_bank(file_id); - - // Close file - file_close(file_id); - } else if (!settings::path_source_library.empty()) { - - write_message(6, "Sampling library source {}...", settings::path_source); - + if (!settings::path_source_library.empty()) { + write_message(6, "Sampling library source {}...", settings::path_source_library); fill_source_bank_custom_source(); } else { diff --git a/src/state_point.cpp b/src/state_point.cpp index e3484d1a25..873d32a410 100644 --- a/src/state_point.cpp +++ b/src/state_point.cpp @@ -485,11 +485,11 @@ void load_state_point() + "...", 5); // Open source file - file_id = file_open(settings::path_source.c_str(), 'r', true); + file_id = file_open(settings::path_sourcepoint.c_str(), 'r', true); } // Read source - read_source_bank(file_id); + read_source_bank(file_id, simulation::source_bank); } @@ -653,7 +653,7 @@ write_source_bank(hid_t group_id) } -void read_source_bank(hid_t group_id) +void read_source_bank(hid_t group_id, std::vector& sites) { hid_t banktype = h5banktype(); @@ -666,11 +666,15 @@ void read_source_bank(hid_t group_id) // Make sure source bank is big enough hid_t dspace = H5Dget_space(dset); - hsize_t dims_all[1]; - H5Sget_simple_extent_dims(dspace, dims_all, nullptr); - if (simulation::work_index[mpi::n_procs] > dims_all[0]) { - fatal_error("Number of source sites in source file is less " - "than number of source particles per generation."); + hsize_t dims_all; + H5Sget_simple_extent_dims(dspace, &dims_all, nullptr); + if (&sites == &simulation::source_bank) { + if (simulation::work_index[mpi::n_procs] > dims_all) { + fatal_error("Number of source sites in source file is less " + "than number of source particles per generation."); + } + } else { + sites.resize(dims_all); } // Select hyperslab for each process @@ -681,10 +685,10 @@ void read_source_bank(hid_t group_id) // Read data in parallel hid_t plist = H5Pcreate(H5P_DATASET_XFER); H5Pset_dxpl_mpio(plist, H5FD_MPIO_COLLECTIVE); - H5Dread(dset, banktype, memspace, dspace, plist, simulation::source_bank.data()); + H5Dread(dset, banktype, memspace, dspace, plist, sites.data()); H5Pclose(plist); #else - H5Dread(dset, banktype, memspace, dspace, H5P_DEFAULT, simulation::source_bank.data()); + H5Dread(dset, banktype, memspace, dspace, H5P_DEFAULT, sites.data()); #endif // Close all ids From 713469bf59143e9b8fae7dfb3e4bf4f1e86b3769 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Thu, 22 Oct 2020 15:05:43 -0500 Subject: [PATCH 40/79] Make regular source distributions obey the same interface as custom sources --- examples/custom_source/source_ring.cpp | 2 +- .../parameterized_source_ring.cpp | 3 +- include/openmc/source.h | 30 +++++++++++-------- src/settings.cpp | 7 ++--- src/source.cpp | 22 +++++++------- src/tallies/tally.cpp | 2 +- .../source_dlopen/source_sampling.cpp | 6 ++-- .../parameterized_source_sampling.cpp | 2 +- 8 files changed, 38 insertions(+), 36 deletions(-) diff --git a/examples/custom_source/source_ring.cpp b/examples/custom_source/source_ring.cpp index bc8a8a7f8d..a23250db12 100644 --- a/examples/custom_source/source_ring.cpp +++ b/examples/custom_source/source_ring.cpp @@ -5,7 +5,7 @@ #include "openmc/source.h" #include "openmc/particle.h" -class Source : public openmc::CustomSource +class Source : public openmc::SourceDistribution { openmc::Particle::Bank sample(uint64_t* seed) { diff --git a/examples/parameterized_custom_source/parameterized_source_ring.cpp b/examples/parameterized_custom_source/parameterized_source_ring.cpp index c88333e15b..8668fd426d 100644 --- a/examples/parameterized_custom_source/parameterized_source_ring.cpp +++ b/examples/parameterized_custom_source/parameterized_source_ring.cpp @@ -6,8 +6,7 @@ #include "openmc/source.h" #include "openmc/particle.h" -class Source : public openmc::CustomSource -{ +class Source : public openmc::SourceDistribution { public: Source(double radius, double energy) : radius_(radius), energy_(energy) { } diff --git a/include/openmc/source.h b/include/openmc/source.h index e47c918516..f1fe40a391 100644 --- a/include/openmc/source.h +++ b/include/openmc/source.h @@ -23,7 +23,7 @@ class SourceDistribution; namespace model { -extern std::vector external_sources; +extern std::vector> external_sources; } // namespace model @@ -32,19 +32,30 @@ extern std::vector external_sources; //============================================================================== class SourceDistribution { +public: + virtual ~SourceDistribution() = default; + + // Methods that must be implemented + virtual Particle::Bank sample(uint64_t* seed) = 0; + + // Methods that can be overridden + virtual double strength() const { return 1.0; } +}; + +class IndependentSourceDistribution : public SourceDistribution { public: // Constructors - SourceDistribution(UPtrSpace space, UPtrAngle angle, UPtrDist energy); - explicit SourceDistribution(pugi::xml_node node); + IndependentSourceDistribution(UPtrSpace space, UPtrAngle angle, UPtrDist energy); + explicit IndependentSourceDistribution(pugi::xml_node node); //! Sample from the external source distribution //! \param[inout] seed Pseudorandom seed pointer //! \return Sampled site - Particle::Bank sample(uint64_t* seed) const; + Particle::Bank sample(uint64_t* seed) override; // Properties Particle::Type particle_type() const { return particle_; } - double strength() const { return strength_; } + double strength() const override { return strength_; } // Make observing pointers available SpatialDistribution* space() const { return space_.get(); } @@ -60,14 +71,7 @@ private: std::vector sites_; //!< Source sites from a file }; -class CustomSource { - public: - virtual ~CustomSource() {} - - virtual Particle::Bank sample(uint64_t* seed) = 0; -}; - -typedef std::unique_ptr create_custom_source_t(std::string parameters); +typedef std::unique_ptr create_custom_source_t(std::string parameters); //============================================================================== // Functions diff --git a/src/settings.cpp b/src/settings.cpp index cab7c6c11b..8b0cd53008 100644 --- a/src/settings.cpp +++ b/src/settings.cpp @@ -420,17 +420,16 @@ void read_settings_xml() // Get point to list of elements and make sure there is at least one for (pugi::xml_node node : root.children("source")) { - model::external_sources.emplace_back(node); + model::external_sources.push_back(std::make_unique(node)); } // If no source specified, default to isotropic point source at origin with Watt spectrum if (model::external_sources.empty()) { - SourceDistribution source { + model::external_sources.push_back(std::make_unique( UPtrSpace{new SpatialPoint({0.0, 0.0, 0.0})}, UPtrAngle{new Isotropic()}, UPtrDist{new Watt(0.988e6, 2.249e-6)} - }; - model::external_sources.push_back(std::move(source)); + )); } // Check if we want to write out source diff --git a/src/source.cpp b/src/source.cpp index 91a5f78cc3..dc75a0c818 100644 --- a/src/source.cpp +++ b/src/source.cpp @@ -39,7 +39,7 @@ namespace openmc { namespace model { -std::vector external_sources; +std::vector> external_sources; } @@ -47,7 +47,7 @@ namespace { void* custom_source_library; std::string custom_source_parameters; -std::unique_ptr custom_source; +std::unique_ptr custom_source; } @@ -56,10 +56,10 @@ std::unique_ptr custom_source; // SourceDistribution implementation //============================================================================== -SourceDistribution::SourceDistribution(UPtrSpace space, UPtrAngle angle, UPtrDist energy) +IndependentSourceDistribution::IndependentSourceDistribution(UPtrSpace space, UPtrAngle angle, UPtrDist energy) : space_{std::move(space)}, angle_{std::move(angle)}, energy_{std::move(energy)} { } -SourceDistribution::SourceDistribution(pugi::xml_node node) +IndependentSourceDistribution::IndependentSourceDistribution(pugi::xml_node node) { // Check for particle type if (check_for_node(node, "particle")) { @@ -190,7 +190,7 @@ SourceDistribution::SourceDistribution(pugi::xml_node node) } -Particle::Bank SourceDistribution::sample(uint64_t* seed) const +Particle::Bank IndependentSourceDistribution::sample(uint64_t* seed) { Particle::Bank site; @@ -331,7 +331,7 @@ Particle::Bank sample_external_source(uint64_t* seed) // Determine total source strength double total_strength = 0.0; for (auto& s : model::external_sources) - total_strength += s.strength(); + total_strength += s->strength(); // Sample from among multiple source distributions int i = 0; @@ -339,13 +339,13 @@ Particle::Bank sample_external_source(uint64_t* seed) double xi = prn(seed)*total_strength; double c = 0.0; for (; i < model::external_sources.size(); ++i) { - c += model::external_sources[i].strength(); + c += model::external_sources[i]->strength(); if (xi < c) break; } } // Sample source site from i-th source distribution - Particle::Bank site {model::external_sources[i].sample(seed)}; + Particle::Bank site {model::external_sources[i]->sample(seed)}; // If running in MG, convert site.E to group if (!settings::run_CE) { @@ -375,7 +375,7 @@ void load_custom_source_library() // reset errors dlerror(); - // get the function to create the CustomSource from the library + // get the function to create the custom source from the library auto create_custom_source = reinterpret_cast( dlsym(custom_source_library, "openmc_create_source")); @@ -387,7 +387,7 @@ void load_custom_source_library() fatal_error(error_msg); } - // create a pointer to an instance of the CustomSource + // create a pointer to an instance of the custom source custom_source = create_custom_source(custom_source_parameters); #else @@ -413,7 +413,7 @@ void close_custom_source_library() Particle::Bank sample_custom_source_library(uint64_t* seed) { - // sample from the instance of the CustomSource + // sample from the instance of the custom source return custom_source->sample(seed); } diff --git a/src/tallies/tally.cpp b/src/tallies/tally.cpp index d5cc7dfb6f..038bcec649 100644 --- a/src/tallies/tally.cpp +++ b/src/tallies/tally.cpp @@ -632,7 +632,7 @@ void Tally::accumulate() double total_source = 0.0; if (settings::run_mode == RunMode::FIXED_SOURCE) { for (const auto& s : model::external_sources) { - total_source += s.strength(); + total_source += s->strength(); } } else { total_source = 1.0; diff --git a/tests/regression_tests/source_dlopen/source_sampling.cpp b/tests/regression_tests/source_dlopen/source_sampling.cpp index ea74afdd97..4425af5a9d 100644 --- a/tests/regression_tests/source_dlopen/source_sampling.cpp +++ b/tests/regression_tests/source_dlopen/source_sampling.cpp @@ -5,7 +5,7 @@ #include "openmc/source.h" #include "openmc/particle.h" -class Source : openmc::CustomSource +class Source : public openmc::SourceDistribution { openmc::Particle::Bank sample(uint64_t *seed) { @@ -14,7 +14,7 @@ class Source : openmc::CustomSource particle.particle = openmc::Particle::Type::neutron; particle.wgt = 1.0; // position - + particle.r.x = 0.; particle.r.y = 0.; particle.r.z = 0.; @@ -22,7 +22,7 @@ class Source : openmc::CustomSource particle.u = {1.0, 0.0, 0.0}; particle.E = 14.08e6; particle.delayed_group = 0; - return particle; + return particle; } }; diff --git a/tests/regression_tests/source_parameterized_dlopen/parameterized_source_sampling.cpp b/tests/regression_tests/source_parameterized_dlopen/parameterized_source_sampling.cpp index 3b0875bb03..3f9e876398 100644 --- a/tests/regression_tests/source_parameterized_dlopen/parameterized_source_sampling.cpp +++ b/tests/regression_tests/source_parameterized_dlopen/parameterized_source_sampling.cpp @@ -1,7 +1,7 @@ #include "openmc/source.h" #include "openmc/particle.h" -class Source : public openmc::CustomSource { +class Source : public openmc::SourceDistribution { public: Source(double energy) : energy_(energy) { } From 3f62fab56558dc1f2fbe135841ccd6220bb78ee0 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Thu, 22 Oct 2020 15:50:30 -0500 Subject: [PATCH 41/79] Add wrapper class for custom sources --- include/openmc/source.h | 34 +++++--- src/settings.cpp | 14 +++- src/simulation.cpp | 12 --- src/source.cpp | 177 ++++++++++++++-------------------------- 4 files changed, 95 insertions(+), 142 deletions(-) diff --git a/include/openmc/source.h b/include/openmc/source.h index f1fe40a391..59f1151f9e 100644 --- a/include/openmc/source.h +++ b/include/openmc/source.h @@ -71,6 +71,28 @@ private: std::vector sites_; //!< Source sites from a file }; +//============================================================================== +//! Wrapper for custom sources that manages opening/closing shared library +//============================================================================== + +class CustomSourceWrapper : public SourceDistribution { +public: + // Constructors, destructors + CustomSourceWrapper(std::string path, std::string parameters); + ~CustomSourceWrapper(); + + // Defer implementation to custom source library + Particle::Bank sample(uint64_t* seed) override + { + return custom_source_->sample(seed); + } + + double strength() const override { return custom_source_->strength(); } +private: + void* shared_library_; //!< library from dlopen + std::unique_ptr custom_source_; +}; + typedef std::unique_ptr create_custom_source_t(std::string parameters); //============================================================================== @@ -86,18 +108,6 @@ extern "C" void initialize_source(); //! \return Sampled source site Particle::Bank sample_external_source(uint64_t* seed); -//! Sample a site from custom source library -Particle::Bank sample_custom_source_library(uint64_t* seed); - -//! Load custom source library -void load_custom_source_library(); - -//! Release custom source library -void close_custom_source_library(); - -//! Fill source bank at the end of a generation for dlopen based source simulation -void fill_source_bank_custom_source(); - void free_memory_source(); } // namespace openmc diff --git a/src/settings.cpp b/src/settings.cpp index 8b0cd53008..55dc04aa69 100644 --- a/src/settings.cpp +++ b/src/settings.cpp @@ -420,7 +420,19 @@ void read_settings_xml() // Get point to list of elements and make sure there is at least one for (pugi::xml_node node : root.children("source")) { - model::external_sources.push_back(std::make_unique(node)); + if (check_for_node(node, "library")) { + // Get shared library path and parameters + auto path = get_node_value(node, "library", false, true); + std::string parameters; + if (check_for_node(node, "parameters")) { + parameters = get_node_value(node, "parameters", false, true); + } + + // Create custom source + model::external_sources.push_back(std::make_unique(path, parameters)); + } else { + model::external_sources.push_back(std::make_unique(node)); + } } // If no source specified, default to isotropic point source at origin with Watt spectrum diff --git a/src/simulation.cpp b/src/simulation.cpp index c95c0386c0..1e35adeeea 100644 --- a/src/simulation.cpp +++ b/src/simulation.cpp @@ -121,12 +121,6 @@ int openmc_simulation_init() } } - // If fixed source and using custom source library then need to load - if (settings::run_mode == RunMode::FIXED_SOURCE && - !settings::path_source_library.empty()) { - load_custom_source_library(); - } - // Display header if (mpi::master) { if (settings::run_mode == RunMode::FIXED_SOURCE) { @@ -173,12 +167,6 @@ int openmc_simulation_finalize() t->active_ = false; } - // If fixed source and using custom source library then need to close - if (settings::run_mode == RunMode::FIXED_SOURCE && - !settings::path_source_library.empty()) { - close_custom_source_library(); - } - // Stop timers and show timing statistics simulation::time_finalize.stop(); simulation::time_total.stop(); diff --git a/src/source.cpp b/src/source.cpp index dc75a0c818..e19ccc832c 100644 --- a/src/source.cpp +++ b/src/source.cpp @@ -43,17 +43,8 @@ std::vector> external_sources; } -namespace { - -void* custom_source_library; -std::string custom_source_parameters; -std::unique_ptr custom_source; - -} - - //============================================================================== -// SourceDistribution implementation +// IndependentSourceDistribution implementation //============================================================================== IndependentSourceDistribution::IndependentSourceDistribution(UPtrSpace space, UPtrAngle angle, UPtrDist energy) @@ -111,16 +102,6 @@ IndependentSourceDistribution::IndependentSourceDistribution(pugi::xml_node node // Close file file_close(file_id); - } else if (check_for_node(node, "library")) { - settings::path_source_library = get_node_value(node, "library", false, true); - if (!file_exists(settings::path_source_library)) { - fatal_error(fmt::format("Source library '{}' does not exist.", - settings::path_source_library)); - } - - if (check_for_node(node, "parameters")) { - custom_source_parameters = get_node_value(node, "parameters", false, true); - } } else { // Spatial distribution for external source @@ -189,7 +170,6 @@ IndependentSourceDistribution::IndependentSourceDistribution(pugi::xml_node node } } - Particle::Bank IndependentSourceDistribution::sample(uint64_t* seed) { Particle::Bank site; @@ -285,6 +265,56 @@ Particle::Bank IndependentSourceDistribution::sample(uint64_t* seed) return site; } +//============================================================================== +// CustomSourceWrapper implementation +//============================================================================== + +CustomSourceWrapper::CustomSourceWrapper(std::string path, std::string parameters) +{ +#ifdef HAS_DYNAMIC_LINKING + // Open the library + shared_library_ = dlopen(path.c_str(), RTLD_LAZY); + if (!shared_library_) { + fatal_error("Couldn't open source library " + path); + } + + // reset errors + dlerror(); + + // get the function to create the custom source from the library + auto create_custom_source = reinterpret_cast( + dlsym(shared_library_, "openmc_create_source")); + + // check for any dlsym errors + auto dlsym_error = dlerror(); + if (dlsym_error) { + std::string error_msg = fmt::format("Couldn't open the openmc_create_source symbol: {}", dlsym_error); + dlclose(shared_library_); + fatal_error(error_msg); + } + + // create a pointer to an instance of the custom source + custom_source_ = create_custom_source(parameters); + +#else + fatal_error("Custom source libraries have not yet been implemented for " + "non-POSIX systems"); +#endif +} + +CustomSourceWrapper::~CustomSourceWrapper() +{ + // Make sure custom source is cleared before closing shared library + if (custom_source_.get()) custom_source_.reset(); + +#ifdef HAS_DYNAMIC_LINKING + dlclose(shared_library_); +#else + fatal_error("Custom source libraries have not yet been implemented for " + "non-POSIX systems"); +#endif +} + //============================================================================== // Non-member functions //============================================================================== @@ -293,22 +323,16 @@ void initialize_source() { write_message("Initializing source particles...", 5); - if (!settings::path_source_library.empty()) { - write_message(6, "Sampling library source {}...", settings::path_source_library); - fill_source_bank_custom_source(); + // Generation source sites from specified distribution in user input + #pragma omp parallel for + for (int64_t i = 0; i < simulation::work_per_rank; ++i) { + // initialize random number seed + int64_t id = simulation::total_gen*settings::n_particles + + simulation::work_index[mpi::rank] + i + 1; + uint64_t seed = init_seed(id, STREAM_SOURCE); - } else { - // Generation source sites from specified distribution in user input - #pragma omp parallel for - for (int64_t i = 0; i < simulation::work_per_rank; ++i) { - // initialize random number seed - int64_t id = simulation::total_gen*settings::n_particles + - simulation::work_index[mpi::rank] + i + 1; - uint64_t seed = init_seed(id, STREAM_SOURCE); - - // sample external source distribution - simulation::source_bank[i] = sample_external_source(&seed); - } + // sample external source distribution + simulation::source_bank[i] = sample_external_source(&seed); } // Write out initial source @@ -323,11 +347,6 @@ void initialize_source() Particle::Bank sample_external_source(uint64_t* seed) { - // return values from custom source if using - if (!settings::path_source_library.empty()) { - return sample_custom_source_library(seed); - } - // Determine total source strength double total_strength = 0.0; for (auto& s : model::external_sources) @@ -362,80 +381,4 @@ void free_memory_source() model::external_sources.clear(); } -void load_custom_source_library() -{ -#ifdef HAS_DYNAMIC_LINKING - - // Open the library - custom_source_library = dlopen(settings::path_source_library.c_str(), RTLD_LAZY); - if (!custom_source_library) { - fatal_error("Couldn't open source library " + settings::path_source_library); - } - - // reset errors - dlerror(); - - // get the function to create the custom source from the library - auto create_custom_source = reinterpret_cast( - dlsym(custom_source_library, "openmc_create_source")); - - // check for any dlsym errors - auto dlsym_error = dlerror(); - if (dlsym_error) { - std::string error_msg = fmt::format("Couldn't open the openmc_create_source symbol: {}", dlsym_error); - dlclose(custom_source_library); - fatal_error(error_msg); - } - - // create a pointer to an instance of the custom source - custom_source = create_custom_source(custom_source_parameters); - -#else - fatal_error("Custom source libraries have not yet been implemented for " - "non-POSIX systems"); -#endif -} - -void close_custom_source_library() -{ - if (custom_source.get()) { - // Make sure the custom source is destroyed before we close it's libary. - custom_source.reset(); - } - -#ifdef HAS_DYNAMIC_LINKING - dlclose(custom_source_library); -#else - fatal_error("Custom source libraries have not yet been implemented for " - "non-POSIX systems"); -#endif -} - -Particle::Bank sample_custom_source_library(uint64_t* seed) -{ - // sample from the instance of the custom source - return custom_source->sample(seed); -} - -void fill_source_bank_custom_source() -{ - // Load the custom library - load_custom_source_library(); - - // Generation source sites from specified distribution in the - // library source - for (int64_t i = 0; i < simulation::work_per_rank; ++i) { - // initialize random number seed - int64_t id = (simulation::total_gen + overall_generation()) * - settings::n_particles + simulation::work_index[mpi::rank] + i + 1; - uint64_t seed = init_seed(id, STREAM_SOURCE); - - // sample custom library source - simulation::source_bank[i] = sample_custom_source_library(&seed); - } - - // release the library - close_custom_source_library(); -} - } // namespace openmc From 5a60133d5b2cdd0ad5c66642cdfaaac02d98c490 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Fri, 23 Oct 2020 06:56:14 -0500 Subject: [PATCH 42/79] Implement SourceFile derived from SourceDistribution --- include/openmc/source.h | 12 ++++++ src/settings.cpp | 5 ++- src/source.cpp | 82 +++++++++++++++++++++-------------------- 3 files changed, 58 insertions(+), 41 deletions(-) diff --git a/include/openmc/source.h b/include/openmc/source.h index 59f1151f9e..ff4b3e04fe 100644 --- a/include/openmc/source.h +++ b/include/openmc/source.h @@ -68,6 +68,18 @@ private: UPtrSpace space_; //!< Spatial distribution UPtrAngle angle_; //!< Angular distribution UPtrDist energy_; //!< Energy distribution +}; + + +class SourceFile : public SourceDistribution { +public: + // Constructors + explicit SourceFile(std::string path); + + // Methods + Particle::Bank sample(uint64_t* seed) override; + +private: std::vector sites_; //!< Source sites from a file }; diff --git a/src/settings.cpp b/src/settings.cpp index 55dc04aa69..b692274c64 100644 --- a/src/settings.cpp +++ b/src/settings.cpp @@ -420,7 +420,10 @@ void read_settings_xml() // Get point to list of elements and make sure there is at least one for (pugi::xml_node node : root.children("source")) { - if (check_for_node(node, "library")) { + if (check_for_node(node, "file")) { + auto path = get_node_value(node, "file", false, true); + model::external_sources.push_back(std::make_unique(path)); + } else if (check_for_node(node, "library")) { // Get shared library path and parameters auto path = get_node_value(node, "library", false, true); std::string parameters; diff --git a/src/source.cpp b/src/source.cpp index e19ccc832c..5c96adc20c 100644 --- a/src/source.cpp +++ b/src/source.cpp @@ -72,35 +72,6 @@ IndependentSourceDistribution::IndependentSourceDistribution(pugi::xml_node node // Check for external source file if (check_for_node(node, "file")) { - // Copy path of source file - auto path_source = get_node_value(node, "file", false, true); - - // Check if source file exists - if (!file_exists(path_source)) { - fatal_error(fmt::format("Source file '{}' does not exist.", path_source)); - } - - // Read the source from a binary file instead of sampling from some - // assumed source distribution - write_message(6, "Reading source file from {}...", path_source); - - // Open the binary file - hid_t file_id = file_open(path_source, 'r', true); - - // Read the file type - std::string filetype; - read_attribute(file_id, "filetype", filetype); - - // Check to make sure this is a source file - if (filetype != "source" && filetype != "statepoint") { - fatal_error("Specified starting source file not a source file type."); - } - - // Read in the source bank - read_source_bank(file_id, sites_); - - // Close file - file_close(file_id); } else { @@ -182,16 +153,11 @@ Particle::Bank IndependentSourceDistribution::sample(uint64_t* seed) int n_reject = 0; static int n_accept = 0; while (!found) { - if (!sites_.empty()) { - size_t i_site = sites_.size()*prn(seed); - site = sites_[i_site]; - } else { - // Set particle type - site.particle = particle_; + // Set particle type + site.particle = particle_; - // Sample spatial distribution - site.r = space_->sample(seed); - } + // Sample spatial distribution + site.r = space_->sample(seed); // Now search to see if location exists in geometry int32_t cell_index, instance; @@ -232,8 +198,6 @@ Particle::Bank IndependentSourceDistribution::sample(uint64_t* seed) // Increment number of accepted samples ++n_accept; - if (!sites_.empty()) return site; - // Sample angle site.u = angle_->sample(seed); @@ -265,6 +229,44 @@ Particle::Bank IndependentSourceDistribution::sample(uint64_t* seed) return site; } +//============================================================================== +// SourceFile implementation +//============================================================================== + +SourceFile::SourceFile(std::string path) +{ + // Check if source file exists + if (!file_exists(path)) { + fatal_error(fmt::format("Source file '{}' does not exist.", path)); + } + + // Read the source from a binary file instead of sampling from some + // assumed source distribution + write_message(6, "Reading source file from {}...", path); + + // Open the binary file + hid_t file_id = file_open(path, 'r', true); + + // Check to make sure this is a source file + std::string filetype; + read_attribute(file_id, "filetype", filetype); + if (filetype != "source" && filetype != "statepoint") { + fatal_error("Specified starting source file not a source file type."); + } + + // Read in the source bank + read_source_bank(file_id, sites_); + + // Close file + file_close(file_id); +} + +Particle::Bank SourceFile::sample(uint64_t* seed) +{ + size_t i_site = sites_.size()*prn(seed); + return sites_[i_site]; +} + //============================================================================== // CustomSourceWrapper implementation //============================================================================== From f2526ec4391a4dc1496d576a1b2db268f6831c22 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Fri, 23 Oct 2020 13:26:02 -0500 Subject: [PATCH 43/79] Generalize source bank reading (don't rely on work_index) --- src/state_point.cpp | 33 +++++++++---------- .../source_file/results_true.dat | 2 +- 2 files changed, 17 insertions(+), 18 deletions(-) diff --git a/src/state_point.cpp b/src/state_point.cpp index 873d32a410..6fcc900a64 100644 --- a/src/state_point.cpp +++ b/src/state_point.cpp @@ -659,27 +659,26 @@ void read_source_bank(hid_t group_id, std::vector& sites) // Open the dataset hid_t dset = H5Dopen(group_id, "source_bank", H5P_DEFAULT); - - // Create another data space but for each proc individually - hsize_t dims[] {static_cast(simulation::work_per_rank)}; - hid_t memspace = H5Screate_simple(1, dims, nullptr); + hid_t dspace = H5Dget_space(dset); + hsize_t n_sites; + H5Sget_simple_extent_dims(dspace, &n_sites, nullptr); // Make sure source bank is big enough - hid_t dspace = H5Dget_space(dset); - hsize_t dims_all; - H5Sget_simple_extent_dims(dspace, &dims_all, nullptr); - if (&sites == &simulation::source_bank) { - if (simulation::work_index[mpi::n_procs] > dims_all) { - fatal_error("Number of source sites in source file is less " - "than number of source particles per generation."); - } - } else { - sites.resize(dims_all); - } + sites.resize(n_sites); + + // Determine number of source particles to read from each rank and offset + hsize_t min_sites = n_sites / mpi::n_procs; + hsize_t remainder = n_sites % mpi::n_procs; + hsize_t n_sites_local = (mpi::rank < remainder) ? min_sites + 1 : min_sites; + hsize_t offset = (mpi::rank <= remainder) ? + mpi::rank*(min_sites + 1) : + remainder*(min_sites + 1) + (mpi::rank - remainder)*min_sites; + + // Create another data space but for each proc individually + hid_t memspace = H5Screate_simple(1, &n_sites_local, nullptr); // Select hyperslab for each process - hsize_t start[] {static_cast(simulation::work_index[mpi::rank])}; - H5Sselect_hyperslab(dspace, H5S_SELECT_SET, start, nullptr, dims, nullptr); + H5Sselect_hyperslab(dspace, H5S_SELECT_SET, &offset, nullptr, &n_sites_local, nullptr); #ifdef PHDF5 // Read data in parallel diff --git a/tests/regression_tests/source_file/results_true.dat b/tests/regression_tests/source_file/results_true.dat index 4ab7993d88..44c422eeff 100644 --- a/tests/regression_tests/source_file/results_true.dat +++ b/tests/regression_tests/source_file/results_true.dat @@ -1,2 +1,2 @@ k-combined: -2.939525E-01 6.311780E-03 +3.080726E-01 9.554124E-03 From 0bb39005bcf7f9aad4d333ede0715c249229094e Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Fri, 23 Oct 2020 13:45:28 -0500 Subject: [PATCH 44/79] Rename source classes --- examples/custom_source/source_ring.cpp | 6 ++-- .../parameterized_source_ring.cpp | 12 +++---- include/openmc/settings.h | 1 - include/openmc/source.h | 33 +++++++++++-------- src/settings.cpp | 7 ++-- src/source.cpp | 14 ++++---- .../source_dlopen/source_sampling.cpp | 6 ++-- .../parameterized_source_sampling.cpp | 8 ++--- 8 files changed, 46 insertions(+), 41 deletions(-) diff --git a/examples/custom_source/source_ring.cpp b/examples/custom_source/source_ring.cpp index a23250db12..7ff3b03b46 100644 --- a/examples/custom_source/source_ring.cpp +++ b/examples/custom_source/source_ring.cpp @@ -5,7 +5,7 @@ #include "openmc/source.h" #include "openmc/particle.h" -class Source : public openmc::SourceDistribution +class RingSource : public openmc::Source { openmc::Particle::Bank sample(uint64_t* seed) { @@ -30,7 +30,7 @@ class Source : public openmc::SourceDistribution // A function to create a unique pointer to an instance of this class when generated // via a plugin call using dlopen/dlsym. // You must have external C linkage here otherwise dlopen will not find the file -extern "C" std::unique_ptr openmc_create_source(std::string parameters) +extern "C" std::unique_ptr openmc_create_source(std::string parameters) { - return std::make_unique(); + return std::make_unique(); } diff --git a/examples/parameterized_custom_source/parameterized_source_ring.cpp b/examples/parameterized_custom_source/parameterized_source_ring.cpp index 8668fd426d..2176a073ae 100644 --- a/examples/parameterized_custom_source/parameterized_source_ring.cpp +++ b/examples/parameterized_custom_source/parameterized_source_ring.cpp @@ -6,13 +6,13 @@ #include "openmc/source.h" #include "openmc/particle.h" -class Source : public openmc::SourceDistribution { +class RingSource : public openmc::Source { public: - Source(double radius, double energy) : radius_(radius), energy_(energy) { } + RingSource(double radius, double energy) : radius_(radius), energy_(energy) { } // Defines a function that can create a unique pointer to a new instance of this class // by extracting the parameters from the provided string. - static std::unique_ptr from_string(std::string parameters) + static std::unique_ptr from_string(std::string parameters) { std::unordered_map parameter_mapping; @@ -27,7 +27,7 @@ class Source : public openmc::SourceDistribution { double radius = std::stod(parameter_mapping["radius"]); double energy = std::stod(parameter_mapping["energy"]); - return std::make_unique(radius, energy); + return std::make_unique(radius, energy); } // Samples from an instance of this class. @@ -59,7 +59,7 @@ class Source : public openmc::SourceDistribution { // A function to create a unique pointer to an instance of this class when generated // via a plugin call using dlopen/dlsym. // You must have external C linkage here otherwise dlopen will not find the file -extern "C" std::unique_ptr openmc_create_source(std::string parameters) +extern "C" std::unique_ptr openmc_create_source(std::string parameters) { - return Source::from_string(parameters); + return RingSource::from_string(parameters); } diff --git a/include/openmc/settings.h b/include/openmc/settings.h index c743cf7210..74cbbc1328 100644 --- a/include/openmc/settings.h +++ b/include/openmc/settings.h @@ -59,7 +59,6 @@ extern std::string path_cross_sections; //!< path to cross_sections.xml extern std::string path_input; //!< directory where main .xml files resides extern std::string path_output; //!< directory where output files are written extern std::string path_particle_restart; //!< path to a particle restart file -extern std::string path_source_library; //!< path to the source shared object extern std::string path_sourcepoint; //!< path to a source file extern "C" std::string path_statepoint; //!< path to a statepoint file diff --git a/include/openmc/source.h b/include/openmc/source.h index ff4b3e04fe..93e6bcf545 100644 --- a/include/openmc/source.h +++ b/include/openmc/source.h @@ -19,21 +19,21 @@ namespace openmc { // Global variables //============================================================================== -class SourceDistribution; +class Source; namespace model { -extern std::vector> external_sources; +extern std::vector> external_sources; } // namespace model //============================================================================== -//! External source distribution +//! Abstract source interface //============================================================================== -class SourceDistribution { +class Source { public: - virtual ~SourceDistribution() = default; + virtual ~Source() = default; // Methods that must be implemented virtual Particle::Bank sample(uint64_t* seed) = 0; @@ -42,11 +42,15 @@ public: virtual double strength() const { return 1.0; } }; -class IndependentSourceDistribution : public SourceDistribution { +//============================================================================== +//! Source composed of independent spatial, angle, and energy distributions +//============================================================================== + +class IndependentSource : public Source { public: // Constructors - IndependentSourceDistribution(UPtrSpace space, UPtrAngle angle, UPtrDist energy); - explicit IndependentSourceDistribution(pugi::xml_node node); + IndependentSource(UPtrSpace space, UPtrAngle angle, UPtrDist energy); + explicit IndependentSource(pugi::xml_node node); //! Sample from the external source distribution //! \param[inout] seed Pseudorandom seed pointer @@ -70,11 +74,14 @@ private: UPtrDist energy_; //!< Energy distribution }; +//============================================================================== +//! Source composed of particles read from a file +//============================================================================== -class SourceFile : public SourceDistribution { +class FileSource : public Source { public: // Constructors - explicit SourceFile(std::string path); + explicit FileSource(std::string path); // Methods Particle::Bank sample(uint64_t* seed) override; @@ -87,7 +94,7 @@ private: //! Wrapper for custom sources that manages opening/closing shared library //============================================================================== -class CustomSourceWrapper : public SourceDistribution { +class CustomSourceWrapper : public Source { public: // Constructors, destructors CustomSourceWrapper(std::string path, std::string parameters); @@ -102,10 +109,10 @@ public: double strength() const override { return custom_source_->strength(); } private: void* shared_library_; //!< library from dlopen - std::unique_ptr custom_source_; + std::unique_ptr custom_source_; }; -typedef std::unique_ptr create_custom_source_t(std::string parameters); +typedef std::unique_ptr create_custom_source_t(std::string parameters); //============================================================================== // Functions diff --git a/src/settings.cpp b/src/settings.cpp index b692274c64..5a868d445b 100644 --- a/src/settings.cpp +++ b/src/settings.cpp @@ -73,7 +73,6 @@ std::string path_cross_sections; std::string path_input; std::string path_output; std::string path_particle_restart; -std::string path_source_library; std::string path_sourcepoint; std::string path_statepoint; @@ -422,7 +421,7 @@ void read_settings_xml() for (pugi::xml_node node : root.children("source")) { if (check_for_node(node, "file")) { auto path = get_node_value(node, "file", false, true); - model::external_sources.push_back(std::make_unique(path)); + model::external_sources.push_back(std::make_unique(path)); } else if (check_for_node(node, "library")) { // Get shared library path and parameters auto path = get_node_value(node, "library", false, true); @@ -434,13 +433,13 @@ void read_settings_xml() // Create custom source model::external_sources.push_back(std::make_unique(path, parameters)); } else { - model::external_sources.push_back(std::make_unique(node)); + model::external_sources.push_back(std::make_unique(node)); } } // If no source specified, default to isotropic point source at origin with Watt spectrum if (model::external_sources.empty()) { - model::external_sources.push_back(std::make_unique( + model::external_sources.push_back(std::make_unique( UPtrSpace{new SpatialPoint({0.0, 0.0, 0.0})}, UPtrAngle{new Isotropic()}, UPtrDist{new Watt(0.988e6, 2.249e-6)} diff --git a/src/source.cpp b/src/source.cpp index 5c96adc20c..fd2d6cd8f5 100644 --- a/src/source.cpp +++ b/src/source.cpp @@ -39,18 +39,18 @@ namespace openmc { namespace model { -std::vector> external_sources; +std::vector> external_sources; } //============================================================================== -// IndependentSourceDistribution implementation +// IndependentSource implementation //============================================================================== -IndependentSourceDistribution::IndependentSourceDistribution(UPtrSpace space, UPtrAngle angle, UPtrDist energy) +IndependentSource::IndependentSource(UPtrSpace space, UPtrAngle angle, UPtrDist energy) : space_{std::move(space)}, angle_{std::move(angle)}, energy_{std::move(energy)} { } -IndependentSourceDistribution::IndependentSourceDistribution(pugi::xml_node node) +IndependentSource::IndependentSource(pugi::xml_node node) { // Check for particle type if (check_for_node(node, "particle")) { @@ -141,7 +141,7 @@ IndependentSourceDistribution::IndependentSourceDistribution(pugi::xml_node node } } -Particle::Bank IndependentSourceDistribution::sample(uint64_t* seed) +Particle::Bank IndependentSource::sample(uint64_t* seed) { Particle::Bank site; @@ -233,7 +233,7 @@ Particle::Bank IndependentSourceDistribution::sample(uint64_t* seed) // SourceFile implementation //============================================================================== -SourceFile::SourceFile(std::string path) +FileSource::FileSource(std::string path) { // Check if source file exists if (!file_exists(path)) { @@ -261,7 +261,7 @@ SourceFile::SourceFile(std::string path) file_close(file_id); } -Particle::Bank SourceFile::sample(uint64_t* seed) +Particle::Bank FileSource::sample(uint64_t* seed) { size_t i_site = sites_.size()*prn(seed); return sites_[i_site]; diff --git a/tests/regression_tests/source_dlopen/source_sampling.cpp b/tests/regression_tests/source_dlopen/source_sampling.cpp index 4425af5a9d..796b504f3c 100644 --- a/tests/regression_tests/source_dlopen/source_sampling.cpp +++ b/tests/regression_tests/source_dlopen/source_sampling.cpp @@ -5,7 +5,7 @@ #include "openmc/source.h" #include "openmc/particle.h" -class Source : public openmc::SourceDistribution +class CustomSource : public openmc::Source { openmc::Particle::Bank sample(uint64_t *seed) { @@ -29,7 +29,7 @@ class Source : public openmc::SourceDistribution // A function to create a unique pointer to an instance of this class when generated // via a plugin call using dlopen/dlsym. // You must have external C linkage here otherwise dlopen will not find the file -extern "C" std::unique_ptr openmc_create_source(std::string parameters) +extern "C" std::unique_ptr openmc_create_source(std::string parameters) { - return std::make_unique(); + return std::make_unique(); } diff --git a/tests/regression_tests/source_parameterized_dlopen/parameterized_source_sampling.cpp b/tests/regression_tests/source_parameterized_dlopen/parameterized_source_sampling.cpp index 3f9e876398..91c165dbc4 100644 --- a/tests/regression_tests/source_parameterized_dlopen/parameterized_source_sampling.cpp +++ b/tests/regression_tests/source_parameterized_dlopen/parameterized_source_sampling.cpp @@ -1,9 +1,9 @@ #include "openmc/source.h" #include "openmc/particle.h" -class Source : public openmc::SourceDistribution { +class CustomSource : public openmc::Source { public: - Source(double energy) : energy_(energy) { } + CustomSource(double energy) : energy_(energy) { } // Samples from an instance of this class. openmc::Particle::Bank sample(uint64_t* seed) @@ -31,8 +31,8 @@ class Source : public openmc::SourceDistribution { // A function to create a unique pointer to an instance of this class when generated // via a plugin call using dlopen/dlsym. // You must have external C linkage here otherwise dlopen will not find the file -extern "C" std::unique_ptr openmc_create_source(std::string parameter) +extern "C" std::unique_ptr openmc_create_source(std::string parameter) { double energy = std::stod(parameter); - return std::make_unique(energy); + return std::make_unique(energy); } From 33b7dcfe22a268ae22773888f50eddcc22ea0031 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Fri, 23 Oct 2020 13:46:57 -0500 Subject: [PATCH 45/79] Update documentation regarding custom sources --- docs/source/io_formats/settings.rst | 2 +- docs/source/usersguide/settings.rst | 16 ++++++++-------- 2 files changed, 9 insertions(+), 9 deletions(-) diff --git a/docs/source/io_formats/settings.rst b/docs/source/io_formats/settings.rst index 09d7db1236..588b58b478 100644 --- a/docs/source/io_formats/settings.rst +++ b/docs/source/io_formats/settings.rst @@ -465,7 +465,7 @@ attributes/sub-elements: as complex as is required to define the source for your problem. The library has a few basic requirements: - * It must contain a class that inherits from ``openmc::CustomSource``; + * It must contain a class that inherits from ``openmc::Source``; * The class must implement a function called ``sample()``; * There must be an ``openmc_create_source()`` function that creates the source as a unique pointer. This function can be used to pass parameters through to diff --git a/docs/source/usersguide/settings.rst b/docs/source/usersguide/settings.rst index 340d4af00c..1d14038749 100644 --- a/docs/source/usersguide/settings.rst +++ b/docs/source/usersguide/settings.rst @@ -194,7 +194,7 @@ below. #include "openmc/source.h" #include "openmc/particle.h" - class Source : public openmc::CustomSource + class CustomSource : public openmc::Source { openmc::Particle::Bank sample(uint64_t* seed) { @@ -216,16 +216,16 @@ below. } }; - extern "C" std::unique_ptr openmc_create_source(std::string parameters) + extern "C" std::unique_ptr openmc_create_source(std::string parameters) { - return std::make_unique(); + return std::make_unique(); } The above source creates monodirectional 14.08 MeV neutrons that are distributed in a ring with a 3 cm radius. This routine is not particularly complex, but should serve as an example upon which to build more complicated sources. - .. note:: The source class must inherit from ``openmc::CustomSource`` and + .. note:: The source class must inherit from ``openmc::Source`` and implement a ``sample()`` function. .. note:: The ``openmc_create_source()`` function signature must be declared @@ -266,9 +266,9 @@ the source class when it is created: #include "openmc/source.h" #include "openmc/particle.h" - class Source : public openmc::CustomSource { + class CustomSource : public openmc::Source { public: - Source(double energy) : energy_{energy} { } + CustomSource(double energy) : energy_{energy} { } // Samples from an instance of this class. openmc::Particle::Bank sample(uint64_t* seed) @@ -293,9 +293,9 @@ the source class when it is created: double energy_; }; - extern "C" std::unique_ptr openmc_create_source(std::string parameter) { + extern "C" std::unique_ptr openmc_create_source(std::string parameter) { double energy = std::stod(parameter); - return std::make_unique(energy); + return std::make_unique(energy); } As with the basic custom source functionality, the custom source library From b271399f638eef3919af1bef5024c9be6d016add Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Mon, 26 Oct 2020 16:54:40 -0500 Subject: [PATCH 46/79] Allow read_source_bank to be distributed or not --- include/openmc/state_point.h | 2 +- src/source.cpp | 4 ++-- src/state_point.cpp | 37 ++++++++++++++++++++---------------- 3 files changed, 24 insertions(+), 19 deletions(-) diff --git a/include/openmc/state_point.h b/include/openmc/state_point.h index 31dffc9ee9..c50ca355b8 100644 --- a/include/openmc/state_point.h +++ b/include/openmc/state_point.h @@ -14,7 +14,7 @@ namespace openmc { void load_state_point(); void write_source_point(const char* filename); void write_source_bank(hid_t group_id); -void read_source_bank(hid_t group_id, std::vector& sites); +void read_source_bank(hid_t group_id, std::vector& sites, bool distribute); void write_tally_results_nr(hid_t file_id); void restart_set_keff(); diff --git a/src/source.cpp b/src/source.cpp index fd2d6cd8f5..a7bb807478 100644 --- a/src/source.cpp +++ b/src/source.cpp @@ -254,8 +254,8 @@ FileSource::FileSource(std::string path) fatal_error("Specified starting source file not a source file type."); } - // Read in the source bank - read_source_bank(file_id, sites_); + // Read in the source particles + read_source_bank(file_id, sites_, false); // Close file file_close(file_id); diff --git a/src/state_point.cpp b/src/state_point.cpp index 6fcc900a64..66706a676f 100644 --- a/src/state_point.cpp +++ b/src/state_point.cpp @@ -489,7 +489,7 @@ void load_state_point() } // Read source - read_source_bank(file_id, simulation::source_bank); + read_source_bank(file_id, simulation::source_bank, true); } @@ -653,7 +653,7 @@ write_source_bank(hid_t group_id) } -void read_source_bank(hid_t group_id, std::vector& sites) +void read_source_bank(hid_t group_id, std::vector& sites, bool distribute) { hid_t banktype = h5banktype(); @@ -663,22 +663,27 @@ void read_source_bank(hid_t group_id, std::vector& sites) hsize_t n_sites; H5Sget_simple_extent_dims(dspace, &n_sites, nullptr); - // Make sure source bank is big enough - sites.resize(n_sites); + // Make sure vector is big enough in case where we're reading entire source on + // each process + if (!distribute) sites.resize(n_sites); - // Determine number of source particles to read from each rank and offset - hsize_t min_sites = n_sites / mpi::n_procs; - hsize_t remainder = n_sites % mpi::n_procs; - hsize_t n_sites_local = (mpi::rank < remainder) ? min_sites + 1 : min_sites; - hsize_t offset = (mpi::rank <= remainder) ? - mpi::rank*(min_sites + 1) : - remainder*(min_sites + 1) + (mpi::rank - remainder)*min_sites; + hid_t memspace; + if (distribute) { + if (simulation::work_index[mpi::n_procs] > n_sites) { + fatal_error("Number of source sites in source file is less " + "than number of source particles per generation."); + } - // Create another data space but for each proc individually - hid_t memspace = H5Screate_simple(1, &n_sites_local, nullptr); + // Create another data space but for each proc individually + hsize_t n_sites_local = simulation::work_per_rank; + memspace = H5Screate_simple(1, &n_sites_local, nullptr); - // Select hyperslab for each process - H5Sselect_hyperslab(dspace, H5S_SELECT_SET, &offset, nullptr, &n_sites_local, nullptr); + // Select hyperslab for each process + hsize_t offset = simulation::work_index[mpi::rank]; + H5Sselect_hyperslab(dspace, H5S_SELECT_SET, &offset, nullptr, &n_sites_local, nullptr); + } else { + memspace = H5S_ALL; + } #ifdef PHDF5 // Read data in parallel @@ -692,7 +697,7 @@ void read_source_bank(hid_t group_id, std::vector& sites) // Close all ids H5Sclose(dspace); - H5Sclose(memspace); + if (distribute) H5Sclose(memspace); H5Dclose(dset); H5Tclose(banktype); } From 9af5541e88764e639b2f6bc5d02b8d3f168bd1cd Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Mon, 26 Oct 2020 17:00:26 -0500 Subject: [PATCH 47/79] Make Source::sample() method const --- docs/source/usersguide/settings.rst | 4 ++-- examples/custom_source/source_ring.cpp | 2 +- .../parameterized_source_ring.cpp | 2 +- include/openmc/source.h | 8 ++++---- src/source.cpp | 4 ++-- tests/regression_tests/source_dlopen/source_sampling.cpp | 2 +- .../parameterized_source_sampling.cpp | 2 +- 7 files changed, 12 insertions(+), 12 deletions(-) diff --git a/docs/source/usersguide/settings.rst b/docs/source/usersguide/settings.rst index 1d14038749..df22328e3a 100644 --- a/docs/source/usersguide/settings.rst +++ b/docs/source/usersguide/settings.rst @@ -196,7 +196,7 @@ below. class CustomSource : public openmc::Source { - openmc::Particle::Bank sample(uint64_t* seed) + openmc::Particle::Bank sample(uint64_t* seed) const { openmc::Particle::Bank particle; // weight @@ -271,7 +271,7 @@ the source class when it is created: CustomSource(double energy) : energy_{energy} { } // Samples from an instance of this class. - openmc::Particle::Bank sample(uint64_t* seed) + openmc::Particle::Bank sample(uint64_t* seed) const { openmc::Particle::Bank particle; // weight diff --git a/examples/custom_source/source_ring.cpp b/examples/custom_source/source_ring.cpp index 7ff3b03b46..a752216dce 100644 --- a/examples/custom_source/source_ring.cpp +++ b/examples/custom_source/source_ring.cpp @@ -7,7 +7,7 @@ class RingSource : public openmc::Source { - openmc::Particle::Bank sample(uint64_t* seed) + openmc::Particle::Bank sample(uint64_t* seed) const { openmc::Particle::Bank particle; // wgt diff --git a/examples/parameterized_custom_source/parameterized_source_ring.cpp b/examples/parameterized_custom_source/parameterized_source_ring.cpp index 2176a073ae..9f913dfee3 100644 --- a/examples/parameterized_custom_source/parameterized_source_ring.cpp +++ b/examples/parameterized_custom_source/parameterized_source_ring.cpp @@ -31,7 +31,7 @@ class RingSource : public openmc::Source { } // Samples from an instance of this class. - openmc::Particle::Bank sample(uint64_t* seed) + openmc::Particle::Bank sample(uint64_t* seed) const { openmc::Particle::Bank particle; // wgt diff --git a/include/openmc/source.h b/include/openmc/source.h index 93e6bcf545..12e8156992 100644 --- a/include/openmc/source.h +++ b/include/openmc/source.h @@ -36,7 +36,7 @@ public: virtual ~Source() = default; // Methods that must be implemented - virtual Particle::Bank sample(uint64_t* seed) = 0; + virtual Particle::Bank sample(uint64_t* seed) const = 0; // Methods that can be overridden virtual double strength() const { return 1.0; } @@ -55,7 +55,7 @@ public: //! Sample from the external source distribution //! \param[inout] seed Pseudorandom seed pointer //! \return Sampled site - Particle::Bank sample(uint64_t* seed) override; + Particle::Bank sample(uint64_t* seed) const override; // Properties Particle::Type particle_type() const { return particle_; } @@ -84,7 +84,7 @@ public: explicit FileSource(std::string path); // Methods - Particle::Bank sample(uint64_t* seed) override; + Particle::Bank sample(uint64_t* seed) const override; private: std::vector sites_; //!< Source sites from a file @@ -101,7 +101,7 @@ public: ~CustomSourceWrapper(); // Defer implementation to custom source library - Particle::Bank sample(uint64_t* seed) override + Particle::Bank sample(uint64_t* seed) const override { return custom_source_->sample(seed); } diff --git a/src/source.cpp b/src/source.cpp index a7bb807478..ff83031472 100644 --- a/src/source.cpp +++ b/src/source.cpp @@ -141,7 +141,7 @@ IndependentSource::IndependentSource(pugi::xml_node node) } } -Particle::Bank IndependentSource::sample(uint64_t* seed) +Particle::Bank IndependentSource::sample(uint64_t* seed) const { Particle::Bank site; @@ -261,7 +261,7 @@ FileSource::FileSource(std::string path) file_close(file_id); } -Particle::Bank FileSource::sample(uint64_t* seed) +Particle::Bank FileSource::sample(uint64_t* seed) const { size_t i_site = sites_.size()*prn(seed); return sites_[i_site]; diff --git a/tests/regression_tests/source_dlopen/source_sampling.cpp b/tests/regression_tests/source_dlopen/source_sampling.cpp index 796b504f3c..8eaf6265cc 100644 --- a/tests/regression_tests/source_dlopen/source_sampling.cpp +++ b/tests/regression_tests/source_dlopen/source_sampling.cpp @@ -7,7 +7,7 @@ class CustomSource : public openmc::Source { - openmc::Particle::Bank sample(uint64_t *seed) + openmc::Particle::Bank sample(uint64_t *seed) const { openmc::Particle::Bank particle; // wgt diff --git a/tests/regression_tests/source_parameterized_dlopen/parameterized_source_sampling.cpp b/tests/regression_tests/source_parameterized_dlopen/parameterized_source_sampling.cpp index 91c165dbc4..da7d70e378 100644 --- a/tests/regression_tests/source_parameterized_dlopen/parameterized_source_sampling.cpp +++ b/tests/regression_tests/source_parameterized_dlopen/parameterized_source_sampling.cpp @@ -6,7 +6,7 @@ class CustomSource : public openmc::Source { CustomSource(double energy) : energy_(energy) { } // Samples from an instance of this class. - openmc::Particle::Bank sample(uint64_t* seed) + openmc::Particle::Bank sample(uint64_t* seed) const { openmc::Particle::Bank particle; // wgt From b57ee1f757fe37e80540a5a9537c73f24f32bd63 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 27 Oct 2020 16:03:11 -0500 Subject: [PATCH 48/79] Fix class name in comment in source.cpp Co-authored-by: DanShort12 <66615563+DanShort12@users.noreply.github.com> --- src/source.cpp | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/src/source.cpp b/src/source.cpp index ff83031472..87644f054d 100644 --- a/src/source.cpp +++ b/src/source.cpp @@ -230,7 +230,7 @@ Particle::Bank IndependentSource::sample(uint64_t* seed) const } //============================================================================== -// SourceFile implementation +// FileSource implementation //============================================================================== FileSource::FileSource(std::string path) From 86a6e63236ac235d87aa928ea73a647a2d5e7f8b Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Tue, 27 Oct 2020 21:11:52 -0500 Subject: [PATCH 49/79] Removing static library build of MOAB. Not required any longery by DAGMC (thank goodness). --- tools/ci/travis-install-dagmc.sh | 2 -- 1 file changed, 2 deletions(-) diff --git a/tools/ci/travis-install-dagmc.sh b/tools/ci/travis-install-dagmc.sh index 8c9cc61a46..cd2f07e6ca 100755 --- a/tools/ci/travis-install-dagmc.sh +++ b/tools/ci/travis-install-dagmc.sh @@ -21,8 +21,6 @@ git clone -b $MOAB_BRANCH $MOAB_REPO mkdir build && cd build cmake ../moab -DENABLE_HDF5=ON -DBUILD_SHARED_LIBS=ON -DCMAKE_INSTALL_PREFIX=$MOAB_INSTALL_DIR -DENABLE_BLASLAPACK=OFF make -j && make -j install -cmake ../moab -DBUILD_SHARED_LIBS=OFF -make -j install rm -rf $HOME/MOAB/moab $HOME/MOAB/build # DAGMC Install From c9a95f0ac831e625b1ba8080507d398a918d5d4d Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Wed, 28 Oct 2020 12:29:26 -0500 Subject: [PATCH 50/79] Indicate no build of static libraries for DAGMC. --- tools/ci/travis-install-dagmc.sh | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/tools/ci/travis-install-dagmc.sh b/tools/ci/travis-install-dagmc.sh index cd2f07e6ca..eabb9d3821 100755 --- a/tools/ci/travis-install-dagmc.sh +++ b/tools/ci/travis-install-dagmc.sh @@ -28,7 +28,7 @@ cd $HOME mkdir DAGMC && cd DAGMC git clone -b $DAGMC_BRANCH $DAGMC_REPO mkdir build && cd build -cmake ../dagmc -DBUILD_TALLY=ON -DCMAKE_INSTALL_PREFIX=$DAGMC_INSTALL_DIR -DMOAB_DIR=$MOAB_INSTALL_DIR +cmake ../dagmc -DBUILD_TALLY=ON -DCMAKE_INSTALL_PREFIX=$DAGMC_INSTALL_DIR -DBUILD_STATIC_LIBS=OFF -DMOAB_DIR=$MOAB_INSTALL_DIR make -j install rm -rf $HOME/DAGMC/dagmc $HOME/DAGMC/build From cf9ce60c89876752b37add53da1f4bc8e55962c6 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Wed, 28 Oct 2020 16:27:52 -0500 Subject: [PATCH 51/79] Added an MGXS.get_flux method to obtain the weighting flux for whatever post-processing the user may need to do --- openmc/mgxs/mgxs.py | 114 ++++++++++++++++++++++++++++++++++++++++++++ 1 file changed, 114 insertions(+) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index a300344ede..ef6c3de1c6 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -1170,6 +1170,120 @@ class MGXS: return xs + def get_flux(self, groups='all', subdomains='all', + order_groups='increasing', value='mean', + squeeze=True, **kwargs): + r"""Returns an array of the fluxes used to weight the MGXS. + + This method constructs a 2D NumPy array for the requested + weighting flux for one or more subdomains (1st dimension), and + energy groups (2nd dimension). + + Parameters + ---------- + groups : Iterable of Integral or 'all' + Energy groups of interest. Defaults to 'all'. + subdomains : Iterable of Integral or 'all' + Subdomain IDs of interest. Defaults to 'all'. + order_groups: {'increasing', 'decreasing'} + Return the cross section indexed according to increasing or + decreasing energy groups (decreasing or increasing energies). + Defaults to 'increasing'. + value : {'mean', 'std_dev', 'rel_err'} + A string for the type of value to return. Defaults to 'mean'. + squeeze : bool + A boolean representing whether to eliminate the extra dimensions + of the multi-dimensional array to be returned. Defaults to True. + + Returns + ------- + numpy.ndarray + A NumPy array of the flux indexed in the order + each group and subdomain is listed in the parameters. + + Raises + ------ + ValueError + When this method is called before the data is available from tally + data, or, when this is used on an MGXS type without a flux score. + + """ + + cv.check_value('value', value, ['mean', 'std_dev', 'rel_err']) + + filters = [] + filter_bins = [] + + # Construct a collection of the domain filter bins + if not isinstance(subdomains, str): + cv.check_iterable_type('subdomains', subdomains, Integral, + max_depth=3) + + filters.append(_DOMAIN_TO_FILTER[self.domain_type]) + subdomain_bins = [] + for subdomain in subdomains: + subdomain_bins.append(subdomain) + filter_bins.append(tuple(subdomain_bins)) + + # Construct list of energy group bounds tuples for all requested groups + if not isinstance(groups, str): + cv.check_iterable_type('groups', groups, Integral) + filters.append(openmc.EnergyFilter) + energy_bins = [] + for group in groups: + energy_bins.append( + (self.energy_groups.get_group_bounds(group),)) + filter_bins.append(tuple(energy_bins)) + + # Determine which flux to obtain + # Step through in order of usefulness + tally = None + for key in ['flux', 'flux (tracklength)', 'flux (analog)']: + if key in self.tally_keys: + tally = self.tallies[key] + break + if tally is None: + msg = "MGXS of Type {} do not have an explicit weighting flux!" + raise ValueError(msg.format(self.__name__)) + + flux = tally.get_values(filters=filters, filter_bins=filter_bins, + nuclides=['total'], value=value) + + # Eliminate the trivial score dimension + flux = np.squeeze(flux, axis=len(flux.shape) - 1) + # Eliminate the trivial nuclide dimension + flux = np.squeeze(flux, axis=len(flux.shape) - 1) + flux = np.nan_to_num(flux) + + if groups == 'all': + num_groups = self.num_groups + else: + num_groups = len(groups) + + # Reshape tally data array with separate axes for domain and energy + # Accomodate the polar and azimuthal bins if needed + num_subdomains = int(flux.shape[0] / (num_groups * self.num_polar * + self.num_azimuthal)) + if self.num_polar > 1 or self.num_azimuthal > 1: + new_shape = (self.num_polar, self.num_azimuthal, num_subdomains, + num_groups) + else: + new_shape = (num_subdomains, num_groups) + new_shape += flux.shape[1:] + flux = np.reshape(flux, new_shape) + + # Reverse data if user requested increasing energy groups since + # tally data is stored in order of increasing energies + if order_groups == 'increasing': + flux = flux[..., ::-1] + + if squeeze: + # We want to squeeze out everything but the polar, azimuthal, + # and energy group data. + flux = self._squeeze_xs(flux) + + return flux + def get_condensed_xs(self, coarse_groups): """Construct an energy-condensed version of this cross section. From a83e7fa0b7043858d4404a7521eea7198ac3b65b Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Fri, 30 Oct 2020 07:56:50 -0500 Subject: [PATCH 52/79] Reduced number of tested MGXS types in mgxs_library_no_nuclides and mgxs_library_nuclides in an effort to test the intended Python code but not over-do Travis' effort --- .../mgxs_library_no_nuclides/inputs_true.dat | 19310 +-------------- .../mgxs_library_no_nuclides/results_true.dat | 6822 +----- .../mgxs_library_no_nuclides/test.py | 13 +- .../mgxs_library_nuclides/inputs_true.dat | 19414 +--------------- .../mgxs_library_nuclides/results_true.dat | 2 +- .../mgxs_library_nuclides/test.py | 12 +- 6 files changed, 1060 insertions(+), 44513 deletions(-) diff --git a/tests/regression_tests/mgxs_library_no_nuclides/inputs_true.dat b/tests/regression_tests/mgxs_library_no_nuclides/inputs_true.dat index 4da22946bf..0d9dbf8215 100644 --- a/tests/regression_tests/mgxs_library_no_nuclides/inputs_true.dat +++ b/tests/regression_tests/mgxs_library_no_nuclides/inputs_true.dat @@ -68,13 +68,13 @@ 0.0 20000000.0 - + 1 2 3 4 5 6 - + 2 - + 3 @@ -464,7 +464,7 @@ 1 2 total - (n,2nd) + (n,2n) tracklength @@ -476,7 +476,7 @@ 1 2 total - (n,2n) + (n,na) tracklength @@ -488,7 +488,7 @@ 1 2 total - (n,3n) + (n,nc) tracklength @@ -500,7 +500,7 @@ 1 2 total - (n,na) + (n,gamma) tracklength @@ -512,7 +512,7 @@ 1 2 total - (n,n3a) + (n,a) tracklength @@ -524,7 +524,7 @@ 1 2 total - (n,2na) + (n,Xa) tracklength @@ -536,7 +536,7 @@ 1 2 total - (n,3na) + heating tracklength @@ -548,7 +548,7 @@ 1 2 total - (n,np) + damage-energy tracklength @@ -560,7 +560,7 @@ 1 2 total - (n,n2a) + (n,n1) tracklength @@ -572,44 +572,44 @@ 1 2 total - (n,2n2a) + (n,a0) tracklength 1 2 total flux - tracklength + analog - 1 2 + 1 2 5 total - (n,nd) - tracklength + (n,nc) + analog 1 2 total flux - tracklength + analog - 1 2 + 1 2 5 total - (n,nt) - tracklength + (n,n1) + analog 1 2 total flux - tracklength + analog - 1 2 + 1 2 5 total - (n,n3He) - tracklength + (n,2n) + analog 1 2 @@ -618,19567 +618,1243 @@ tracklength - 1 2 + 1 106 2 total - (n,nd2a) + delayed-nu-fission tracklength - 1 2 + 1 106 52 total - flux - tracklength + delayed-nu-fission + analog - 1 2 + 1 106 5 total - (n,nt2a) - tracklength + delayed-nu-fission + analog 1 2 total - flux + nu-fission tracklength - 1 2 + 1 106 2 total - (n,4n) + delayed-nu-fission tracklength - 1 2 + 1 106 total - flux + delayed-nu-fission tracklength - 1 2 + 1 106 total - (n,2np) + decay-rate tracklength 1 2 total flux - tracklength + analog - 1 2 + 1 106 2 5 total - (n,3np) - tracklength + delayed-nu-fission + analog - 1 2 + 120 2 total flux tracklength - 1 2 + 120 2 total - (n,n2p) + total tracklength - 1 2 + 120 2 total flux tracklength - 1 2 + 120 2 total - (n,npa) + total tracklength - 1 2 + 120 2 total flux - tracklength + analog - 1 2 + 120 5 6 total - (n,nc) - tracklength + scatter + analog - 1 2 + 120 2 total flux tracklength - 1 2 + 120 2 total - (n,disappear) + total tracklength - 1 2 + 120 2 total flux - tracklength + analog - 1 2 + 120 5 6 total - (n,gamma) - tracklength + nu-scatter + analog - 1 2 + 120 2 total flux tracklength - 1 2 + 120 2 total - (n,p) + absorption tracklength - 1 2 + 120 2 total flux tracklength - 1 2 + 120 2 total - (n,d) + absorption tracklength - 1 2 + 120 2 total - flux + fission tracklength - 1 2 + 120 2 total - (n,t) + flux tracklength - 1 2 + 120 2 total - flux + fission tracklength - 1 2 + 120 2 total - (n,3He) + flux tracklength - 1 2 + 120 2 total - flux + nu-fission tracklength - 1 2 + 120 2 total - (n,a) + flux tracklength - 1 2 + 120 2 total - flux + kappa-fission tracklength - 1 2 + 120 2 total - (n,2a) + flux tracklength - 1 2 + 120 2 total - flux + scatter tracklength - 1 2 + 120 2 total - (n,3a) - tracklength + flux + analog - 1 2 + 120 2 total - flux - tracklength + nu-scatter + analog - 1 2 + 120 2 total - (n,2p) - tracklength + flux + analog - 1 2 + 120 2 5 28 total - flux - tracklength + scatter + analog - 1 2 + 120 2 total - (n,pa) - tracklength + flux + analog - 1 2 + 120 2 5 28 total - flux - tracklength + nu-scatter + analog - 1 2 + 120 2 5 total - (n,t2a) - tracklength + nu-scatter + analog - 1 2 + 120 2 5 total - flux - tracklength + scatter + analog - 1 2 - total - (n,d2a) - tracklength - - - 1 2 + 120 2 total flux - tracklength + analog + + + 120 2 5 + total + nu-fission + analog - 1 2 + 120 2 5 total - (n,pd) - tracklength + scatter + analog - 1 2 + 120 2 total flux tracklength - 1 2 + 120 2 total - (n,pt) + scatter tracklength - 1 2 + 120 2 5 28 total - flux - tracklength + scatter + analog - 1 2 + 120 2 total - (n,da) + flux tracklength - 1 2 + 120 2 total - flux + scatter tracklength - 1 2 + 120 2 5 28 total - (n,5n) - tracklength + scatter + analog - 1 2 + 120 2 5 total - flux - tracklength + nu-scatter + analog - 1 2 + 120 52 total - (n,6n) - tracklength + nu-fission + analog - 1 2 + 120 5 total - flux - tracklength + nu-fission + analog - 1 2 + 120 52 total - (n,2nt) - tracklength + prompt-nu-fission + analog - 1 2 + 120 5 total - flux - tracklength + prompt-nu-fission + analog - 1 2 + 120 2 total - (n,ta) + flux tracklength - 1 2 + 120 2 total - flux + inverse-velocity tracklength - 1 2 + 120 2 total - (n,4np) + flux tracklength - 1 2 + 120 2 total - flux + prompt-nu-fission tracklength - 1 2 - total - (n,3nd) - tracklength - - - 1 2 + 120 2 total flux - tracklength + analog + + + 120 2 5 + total + prompt-nu-fission + analog - 1 2 + 120 2 total - (n,nda) + flux tracklength - 1 2 + 120 2 total - flux + total tracklength - 1 2 - total - (n,2npa) - tracklength - - - 1 2 + 120 2 total flux - tracklength + analog + + + 120 5 6 + total + scatter + analog - 1 2 + 120 2 total - (n,7n) + flux tracklength - 1 2 + 120 2 total - flux + total tracklength - 1 2 - total - (n,8n) - tracklength - - - 1 2 + 120 2 total flux - tracklength + analog + + + 120 5 6 + total + nu-scatter + analog - 1 2 + 120 2 total - (n,5np) + flux tracklength - 1 2 + 120 2 total - flux + (n,elastic) tracklength - 1 2 + 120 2 total - (n,6np) + flux tracklength - 1 2 + 120 2 total - flux + (n,level) tracklength - 1 2 + 120 2 total - (n,7np) + flux tracklength - 1 2 + 120 2 total - flux + (n,2n) tracklength - 1 2 + 120 2 total - (n,4na) + flux tracklength - 1 2 + 120 2 total - flux + (n,na) tracklength - 1 2 + 120 2 total - (n,5na) + flux tracklength - 1 2 + 120 2 total - flux + (n,nc) tracklength - 1 2 + 120 2 total - (n,6na) + flux tracklength - 1 2 + 120 2 total - flux + (n,gamma) tracklength - 1 2 + 120 2 total - (n,7na) + flux tracklength - 1 2 + 120 2 total - flux + (n,a) tracklength - 1 2 + 120 2 total - (n,4nd) + flux tracklength - 1 2 + 120 2 total - flux + (n,Xa) tracklength - 1 2 + 120 2 total - (n,5nd) + flux tracklength - 1 2 + 120 2 total - flux + heating tracklength - 1 2 + 120 2 total - (n,6nd) + flux tracklength - 1 2 + 120 2 total - flux + damage-energy tracklength - 1 2 + 120 2 total - (n,3nt) + flux tracklength - 1 2 + 120 2 total - flux + (n,n1) tracklength - 1 2 + 120 2 total - (n,4nt) + flux tracklength - 1 2 + 120 2 total - flux + (n,a0) tracklength - 1 2 + 120 2 total - (n,5nt) - tracklength + flux + analog - 1 2 + 120 2 5 total - 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2511 2 - total - (n,a36) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,a37) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,a38) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,a39) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,a40) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,a41) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,a42) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,a43) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,a44) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,a45) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,a46) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,a47) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,a48) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,2n0) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,2n1) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,2n2) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,2n3) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,2n4) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,2n5) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,2n6) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,2n7) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,2n8) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,2n9) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,2n10) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,2n11) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,2n12) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,2n13) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,2n14) - tracklength - - - 2511 2 - total - flux - tracklength - - - 2511 2 - total - (n,2n15) - tracklength - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2nd) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,3n) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,na) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n3a) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2na) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,3na) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,np) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n2a) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n2a) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,nd) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,nt) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n3He) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,nd2a) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,nt2a) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,4n) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2np) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,3np) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n2p) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,npa) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,nc) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,5n) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,6n) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2nt) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,4np) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,3nd) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,nda) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2npa) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,7n) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,8n) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,5np) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,6np) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,7np) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,4na) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,5na) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,6na) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,7na) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,4nd) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,5nd) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,6nd) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,3nt) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,4nt) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,5nt) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,6nt) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n3He) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,3n3He) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,4n3He) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,3n2p) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,3n2a) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,3npa) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,npd) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,npt) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,ndt) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,np3He) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,nd3He) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,nt3He) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,nta) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n2p) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,4n2p) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,4n2a) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,4npa) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n3p) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,3n2pa) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,5n2p) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2nc) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n1) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n2) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n3) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n4) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n5) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n6) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n7) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n8) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n9) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n10) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n11) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n12) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n13) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n14) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n15) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n16) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n17) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n18) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n19) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n20) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n21) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n22) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n23) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n24) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n25) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n26) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n27) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n28) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n29) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n30) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n31) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n32) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n33) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n34) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n35) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n36) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n37) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n38) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n39) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,n40) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n0) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n1) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n2) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n3) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n4) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n5) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n6) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n7) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n8) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n9) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n10) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n11) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n12) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n13) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n14) - analog - - - 2511 2 - total - flux - analog - - - 2511 2 5 - total - (n,2n15) - analog - - - 2511 2 - total - flux - tracklength - - - 2511 1242 2 - total - delayed-nu-fission - tracklength - - - 2511 1242 52 - total - delayed-nu-fission - analog - - - 2511 1242 5 - total - delayed-nu-fission - analog - - - 2511 2 - total - nu-fission - tracklength - - - 2511 1242 2 - total - delayed-nu-fission - tracklength - - - 2511 1242 - total - delayed-nu-fission - tracklength - - - 2511 1242 - total - decay-rate - tracklength - - - 2511 2 - total - flux - analog - - - 2511 1242 2 5 + 239 106 2 5 total delayed-nu-fission analog diff --git a/tests/regression_tests/mgxs_library_no_nuclides/results_true.dat b/tests/regression_tests/mgxs_library_no_nuclides/results_true.dat index 603a1a97fd..398c3e783d 100644 --- a/tests/regression_tests/mgxs_library_no_nuclides/results_true.dat +++ b/tests/regression_tests/mgxs_library_no_nuclides/results_true.dat @@ -170,366 +170,26 @@ nu-diffusion-coefficient material group in nuclide mean std. dev. 1 1 1 total 0.000619 0.000049 0 1 2 total 0.000000 0.000000 -(n,2nd) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 (n,2n) material group in nuclide mean std. dev. 1 1 1 total 0.000121 0.000054 0 1 2 total 0.000000 0.000000 -(n,3n) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 (n,na) material group in nuclide mean std. dev. 1 1 1 total 9.209364e-11 9.154237e-11 0 1 2 total 0.000000e+00 0.000000e+00 -(n,n3a) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2na) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3na) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,np) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,n2a) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n2a) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,nd) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,nt) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,n3He) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,nd2a) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,nt2a) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,4n) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2np) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3np) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,n2p) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,npa) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 (n,nc) material group in nuclide mean std. dev. 1 1 1 total 0.009458 0.000768 0 1 2 total 0.000000 0.000000 -(n,disappear) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 (n,gamma) material group in nuclide mean std. dev. 1 1 1 total 0.019727 0.002262 0 1 2 total 0.071719 0.006262 -(n,p) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 (n,a) material group in nuclide mean std. dev. 1 1 1 total 0.000124 0.000023 0 1 2 total 0.000000 0.000000 -(n,2a) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3a) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2p) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,pa) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t2a) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d2a) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,pd) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,pt) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,da) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,5n) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,6n) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2nt) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,ta) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,4np) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3nd) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,nda) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2npa) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,7n) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,8n) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,5np) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,6np) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,7np) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,4na) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,5na) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,6na) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,7na) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,4nd) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,5nd) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,6nd) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3nt) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,4nt) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,5nt) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,6nt) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n3He) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3n3He) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,4n3He) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3n2p) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3n2a) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3npa) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,dt) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,npd) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,npt) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,ndt) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,np3He) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,nd3He) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,nt3He) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,nta) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n2p) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p3He) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d3He) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3Hea) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,4n2p) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,4n2a) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,4npa) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3p) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,n3p) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3n2pa) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,5n2p) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,Xp) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,Xd) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,Xt) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,X3He) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 (n,Xa) material group in nuclide mean std. dev. 1 1 1 total 0.000124 0.000023 @@ -542,1959 +202,27 @@ damage-energy material group in nuclide mean std. dev. 1 1 1 total 2471.829371 114.012620 0 1 2 total 1357.269536 120.427363 -(n,pc) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,dc) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,tc) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3Hec) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,ac) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2nc) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -heating-local - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 (n,n1) material group in nuclide mean std. dev. 1 1 1 total 0.011877 0.000507 0 1 2 total 0.000000 0.000000 -(n,n2) - material group in nuclide mean std. dev. -1 1 1 total 0.002505 0.000116 -0 1 2 total 0.000000 0.000000 -(n,n3) - material group in nuclide mean std. dev. -1 1 1 total 0.000362 0.000025 -0 1 2 total 0.000000 0.000000 -(n,n4) - material group in nuclide mean std. dev. -1 1 1 total 0.000035 0.000007 -0 1 2 total 0.000000 0.000000 -(n,n5) - material group in nuclide mean std. dev. -1 1 1 total 0.000846 0.000043 -0 1 2 total 0.000000 0.000000 -(n,n6) - material group in nuclide mean std. dev. -1 1 1 total 0.000573 0.000034 -0 1 2 total 0.000000 0.000000 -(n,n7) - material group in nuclide mean std. dev. -1 1 1 total 0.00003 0.000001 -0 1 2 total 0.00000 0.000000 -(n,n8) - material group in nuclide mean std. dev. -1 1 1 total 0.000093 0.000007 -0 1 2 total 0.000000 0.000000 -(n,n9) - material group in nuclide mean std. dev. -1 1 1 total 0.000207 0.000013 -0 1 2 total 0.000000 0.000000 -(n,n10) - material group in nuclide mean std. dev. -1 1 1 total 0.000322 0.000023 -0 1 2 total 0.000000 0.000000 -(n,n11) - material group in nuclide mean std. dev. -1 1 1 total 0.000324 0.000024 -0 1 2 total 0.000000 0.000000 -(n,n12) - material group in nuclide mean std. dev. -1 1 1 total 0.000014 8.144671e-07 -0 1 2 total 0.000000 0.000000e+00 -(n,n13) - material group in nuclide mean std. dev. -1 1 1 total 0.000411 0.000031 -0 1 2 total 0.000000 0.000000 -(n,n14) - material group in nuclide mean std. dev. -1 1 1 total 0.000154 0.000012 -0 1 2 total 0.000000 0.000000 -(n,n15) - material group in nuclide mean std. dev. -1 1 1 total 0.000225 0.000018 -0 1 2 total 0.000000 0.000000 -(n,n16) - material group in nuclide mean std. dev. -1 1 1 total 0.000323 0.000027 -0 1 2 total 0.000000 0.000000 -(n,n17) - material group in nuclide mean std. dev. -1 1 1 total 0.000155 0.000014 -0 1 2 total 0.000000 0.000000 -(n,n18) - material group in nuclide mean std. dev. -1 1 1 total 0.000247 0.000022 -0 1 2 total 0.000000 0.000000 -(n,n19) - material group in nuclide mean std. dev. -1 1 1 total 0.000295 0.000026 -0 1 2 total 0.000000 0.000000 -(n,n20) - material group in nuclide mean std. dev. -1 1 1 total 0.000002 1.308956e-07 -0 1 2 total 0.000000 0.000000e+00 -(n,n21) - material group in nuclide mean std. dev. -1 1 1 total 0.00021 0.000019 -0 1 2 total 0.00000 0.000000 -(n,n22) - material group in nuclide mean std. dev. -1 1 1 total 0.000022 0.000002 -0 1 2 total 0.000000 0.000000 -(n,n23) - material group in nuclide mean std. dev. -1 1 1 total 0.000151 0.000012 -0 1 2 total 0.000000 0.000000 -(n,n24) - material group in nuclide mean std. dev. -1 1 1 total 0.000043 0.000004 -0 1 2 total 0.000000 0.000000 -(n,n25) - material group in nuclide mean std. dev. -1 1 1 total 0.000019 0.000002 -0 1 2 total 0.000000 0.000000 -(n,n26) - material group in nuclide mean std. dev. -1 1 1 total 0.000019 0.000002 -0 1 2 total 0.000000 0.000000 -(n,n27) - material group in nuclide mean std. dev. -1 1 1 total 0.000015 0.000002 -0 1 2 total 0.000000 0.000000 -(n,n28) - material group in nuclide mean std. dev. -1 1 1 total 0.000019 0.000002 -0 1 2 total 0.000000 0.000000 -(n,n29) - material group in nuclide mean std. dev. -1 1 1 total 0.000025 0.000003 -0 1 2 total 0.000000 0.000000 -(n,n30) - material group in nuclide mean std. dev. -1 1 1 total 0.000029 0.000003 -0 1 2 total 0.000000 0.000000 -(n,n31) - material group in nuclide mean std. dev. -1 1 1 total 0.000002 1.950407e-07 -0 1 2 total 0.000000 0.000000e+00 -(n,n32) - material group in nuclide mean std. dev. -1 1 1 total 0.000026 0.000003 -0 1 2 total 0.000000 0.000000 -(n,n33) - material group in nuclide mean std. dev. -1 1 1 total 0.000017 0.000002 -0 1 2 total 0.000000 0.000000 -(n,n34) - material group in nuclide mean std. dev. -1 1 1 total 0.000012 0.000002 -0 1 2 total 0.000000 0.000000 -(n,n35) - material group in nuclide mean std. dev. -1 1 1 total 0.00001 0.000002 -0 1 2 total 0.00000 0.000000 -(n,n36) - material group in nuclide mean std. dev. -1 1 1 total 0.000003 5.553612e-07 -0 1 2 total 0.000000 0.000000e+00 -(n,n37) - material group in nuclide mean std. dev. -1 1 1 total 0.000003 5.764539e-07 -0 1 2 total 0.000000 0.000000e+00 -(n,n38) - material group in nuclide mean std. dev. -1 1 1 total 0.000003 5.719436e-07 -0 1 2 total 0.000000 0.000000e+00 -(n,n39) - material group in nuclide mean std. dev. -1 1 1 total 0.000002 4.127571e-07 -0 1 2 total 0.000000 0.000000e+00 -(n,n40) - material group in nuclide mean std. dev. -1 1 1 total 0.000002 4.451184e-07 -0 1 2 total 0.000000 0.000000e+00 -(n,p0) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p1) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p2) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p3) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p4) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p5) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p6) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p7) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p8) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p9) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p10) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p11) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p12) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p13) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p14) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p15) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p16) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p17) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p18) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p19) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p20) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p21) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p22) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p23) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p24) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p25) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p26) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p27) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p28) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p29) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p30) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p31) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p32) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p33) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p34) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p35) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p36) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p37) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p38) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p39) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p40) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p41) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p42) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p43) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p44) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p45) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p46) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p47) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,p48) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d0) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d1) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d2) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d3) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d4) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d5) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d6) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d7) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d8) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d9) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d10) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d11) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d12) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d13) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d14) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d15) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d16) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d17) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d18) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d19) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d20) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d21) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d22) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d23) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d24) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d25) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d26) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d27) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d28) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d29) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d30) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d31) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d32) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d33) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d34) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d35) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d36) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d37) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d38) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d39) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d40) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d41) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d42) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d43) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d44) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d45) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d46) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d47) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,d48) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t0) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t1) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t2) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t3) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t4) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t5) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t6) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t7) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t8) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t9) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t10) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t11) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t12) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t13) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t14) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t15) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t16) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t17) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t18) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t19) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t20) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t21) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t22) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t23) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t24) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t25) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t26) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t27) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t28) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t29) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t30) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t31) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t32) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t33) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t34) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t35) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t36) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t37) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t38) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t39) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t40) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t41) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t42) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t43) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t44) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t45) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t46) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t47) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,t48) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He0) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He1) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He2) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He3) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He4) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He5) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He6) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He7) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He8) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He9) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He10) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He11) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He12) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He13) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He14) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He15) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He16) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He17) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He18) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He19) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He20) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He21) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He22) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He23) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He24) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He25) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He26) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He27) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He28) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He29) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He30) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He31) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He32) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He33) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He34) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He35) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He36) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He37) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He38) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He39) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He40) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He41) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He42) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He43) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He44) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He45) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He46) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He47) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,3He48) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 (n,a0) material group in nuclide mean std. dev. 1 1 1 total 0.000115 0.000024 0 1 2 total 0.000000 0.000000 -(n,a1) - material group in nuclide mean std. dev. -1 1 1 total 0.000003 0.000002 -0 1 2 total 0.000000 0.000000 -(n,a2) - material group in nuclide mean std. dev. -1 1 1 total 0.000003 0.000003 -0 1 2 total 0.000000 0.000000 -(n,a3) - material group in nuclide mean std. dev. -1 1 1 total 0.000003 0.000003 -0 1 2 total 0.000000 0.000000 -(n,a4) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a5) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a6) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a7) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a8) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a9) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a10) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a11) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a12) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a13) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a14) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a15) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a16) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a17) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a18) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a19) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a20) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a21) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a22) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a23) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a24) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a25) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a26) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a27) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a28) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a29) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a30) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a31) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a32) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a33) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a34) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a35) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a36) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a37) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a38) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a39) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a40) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a41) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a42) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a43) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a44) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a45) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a46) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a47) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,a48) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n0) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n1) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n2) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n3) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n4) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n5) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n6) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n7) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n8) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n9) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n10) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n11) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n12) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n13) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n14) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2n15) - material group in nuclide mean std. dev. -1 1 1 total 0.0 0.0 -0 1 2 total 0.0 0.0 -(n,2nd) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,3n) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,na) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n3a) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2na) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,3na) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,np) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n2a) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n2a) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,nd) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,nt) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n3He) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,nd2a) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,nt2a) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,4n) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2np) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,3np) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n2p) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,npa) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 (n,nc) matrix material group in group out nuclide mean std. dev. 3 1 1 1 total 0.010878 0.001184 2 1 1 2 total 0.000000 0.000000 1 1 2 1 total 0.000000 0.000000 0 1 2 2 total 0.000000 0.000000 -(n,5n) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,6n) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2nt) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,4np) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,3nd) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,nda) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2npa) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,7n) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,8n) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,5np) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,6np) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,7np) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,4na) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,5na) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,6na) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,7na) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,4nd) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,5nd) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,6nd) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,3nt) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,4nt) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,5nt) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,6nt) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n3He) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,3n3He) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,4n3He) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,3n2p) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,3n2a) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,3npa) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,npd) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,npt) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,ndt) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,np3He) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,nd3He) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,nt3He) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,nta) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n2p) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,4n2p) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,4n2a) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,4npa) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n3p) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,3n2pa) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,5n2p) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2nc) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 (n,n1) matrix material group in group out nuclide mean std. dev. 3 1 1 1 total 0.011043 0.000937 2 1 1 2 total 0.000000 0.000000 1 1 2 1 total 0.000000 0.000000 0 1 2 2 total 0.000000 0.000000 -(n,n2) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.003626 0.001073 -2 1 1 2 total 0.000000 0.000000 -1 1 2 1 total 0.000000 0.000000 -0 1 2 2 total 0.000000 0.000000 -(n,n3) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.00033 0.000202 -2 1 1 2 total 0.00000 0.000000 -1 1 2 1 total 0.00000 0.000000 -0 1 2 2 total 0.00000 0.000000 -(n,n4) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n5) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.000989 0.000311 -2 1 1 2 total 0.000000 0.000000 -1 1 2 1 total 0.000000 0.000000 -0 1 2 2 total 0.000000 0.000000 -(n,n6) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.000494 0.000203 -2 1 1 2 total 0.000000 0.000000 -1 1 2 1 total 0.000000 0.000000 -0 1 2 2 total 0.000000 0.000000 -(n,n7) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n8) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n9) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n10) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.000494 0.00033 -2 1 1 2 total 0.000000 0.00000 -1 1 2 1 total 0.000000 0.00000 -0 1 2 2 total 0.000000 0.00000 -(n,n11) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.000824 0.000453 -2 1 1 2 total 0.000000 0.000000 -1 1 2 1 total 0.000000 0.000000 -0 1 2 2 total 0.000000 0.000000 -(n,n12) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n13) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n14) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.00033 0.000202 -2 1 1 2 total 0.00000 0.000000 -1 1 2 1 total 0.00000 0.000000 -0 1 2 2 total 0.00000 0.000000 -(n,n15) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n16) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.000165 0.000165 -2 1 1 2 total 0.000000 0.000000 -1 1 2 1 total 0.000000 0.000000 -0 1 2 2 total 0.000000 0.000000 -(n,n17) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n18) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.000165 0.000165 -2 1 1 2 total 0.000000 0.000000 -1 1 2 1 total 0.000000 0.000000 -0 1 2 2 total 0.000000 0.000000 -(n,n19) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.000659 0.00031 -2 1 1 2 total 0.000000 0.00000 -1 1 2 1 total 0.000000 0.00000 -0 1 2 2 total 0.000000 0.00000 -(n,n20) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n21) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.00033 0.000202 -2 1 1 2 total 0.00000 0.000000 -1 1 2 1 total 0.00000 0.000000 -0 1 2 2 total 0.00000 0.000000 -(n,n22) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n23) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n24) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n25) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n26) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n27) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n28) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n29) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n30) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.000165 0.000165 -2 1 1 2 total 0.000000 0.000000 -1 1 2 1 total 0.000000 0.000000 -0 1 2 2 total 0.000000 0.000000 -(n,n31) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n32) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n33) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n34) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n35) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n36) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n37) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n38) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n39) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,n40) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n0) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n1) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n2) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n3) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n4) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n5) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n6) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n7) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n8) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n9) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n10) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n11) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n12) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n13) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n14) matrix - material group in group out nuclide mean std. dev. -3 1 1 1 total 0.0 0.0 -2 1 1 2 total 0.0 0.0 -1 1 2 1 total 0.0 0.0 -0 1 2 2 total 0.0 0.0 -(n,2n15) matrix +(n,2n) matrix material group in group out nuclide mean std. dev. 3 1 1 1 total 0.0 0.0 2 1 1 2 total 0.0 0.0 @@ -2748,366 +476,26 @@ nu-diffusion-coefficient material group in nuclide mean std. dev. 1 2 1 total 0.0 0.0 0 2 2 total 0.0 0.0 -(n,2nd) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 (n,2n) material group in nuclide mean std. dev. 1 2 1 total 0.000005 0.000005 0 2 2 total 0.000000 0.000000 -(n,3n) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 (n,na) material group in nuclide mean std. dev. 1 2 1 total 1.259778e-09 1.152715e-09 0 2 2 total 0.000000e+00 0.000000e+00 -(n,n3a) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2na) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3na) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,np) - material group in nuclide mean std. dev. -1 2 1 total 8.039832e-12 6.850131e-12 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,n2a) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n2a) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,nd) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,nt) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n3He) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,nd2a) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,nt2a) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,4n) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2np) - material group in nuclide mean std. dev. -1 2 1 total 6.673227e-18 3.698853e-18 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,3np) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n2p) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,npa) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 (n,nc) material group in nuclide mean std. dev. 1 2 1 total 0.002607 0.000356 0 2 2 total 0.000000 0.000000 -(n,disappear) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 (n,gamma) material group in nuclide mean std. dev. 1 2 1 total 0.001569 0.000322 0 2 2 total 0.005400 0.000618 -(n,p) - material group in nuclide mean std. dev. -1 2 1 total 0.000003 8.496498e-07 -0 2 2 total 0.000000 0.000000e+00 -(n,d) - material group in nuclide mean std. dev. -1 2 1 total 3.898895e-15 3.901193e-15 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,t) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 (n,a) material group in nuclide mean std. dev. 1 2 1 total 1.032353e-06 1.308817e-07 0 2 2 total 2.735898e-07 2.541726e-08 -(n,2a) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3a) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2p) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,pa) - material group in nuclide mean std. dev. -1 2 1 total 1.915750e-20 1.839136e-20 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,t2a) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d2a) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,pd) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,pt) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,da) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,5n) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,6n) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2nt) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,ta) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,4np) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3nd) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,nda) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2npa) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,7n) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,8n) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,5np) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,6np) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,7np) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,4na) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,5na) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,6na) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,7na) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,4nd) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,5nd) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,6nd) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3nt) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,4nt) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,5nt) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,6nt) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n3He) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3n3He) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,4n3He) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3n2p) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3n2a) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3npa) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,dt) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,npd) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,npt) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,ndt) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,np3He) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,nd3He) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,nt3He) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,nta) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n2p) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p3He) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d3He) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3Hea) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,4n2p) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,4n2a) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,4npa) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3p) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n3p) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3n2pa) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,5n2p) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,Xp) - material group in nuclide mean std. dev. -1 2 1 total 0.000003 8.496556e-07 -0 2 2 total 0.000000 0.000000e+00 -(n,Xd) - material group in nuclide mean std. dev. -1 2 1 total 3.898895e-15 3.901193e-15 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,Xt) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,X3He) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 (n,Xa) material group in nuclide mean std. dev. 1 2 1 total 1.033613e-06 1.318182e-07 @@ -3120,1959 +508,27 @@ damage-energy material group in nuclide mean std. dev. 1 2 1 total 1712.186983 87.224250 0 2 2 total 0.294202 0.032716 -(n,pc) - material group in nuclide mean std. dev. -1 2 1 total 7.504327e-07 4.278193e-07 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,dc) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,tc) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3Hec) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,ac) - material group in nuclide mean std. dev. -1 2 1 total 1.545575e-08 1.129839e-08 -0 2 2 total 2.755585e-10 2.560016e-11 -(n,2nc) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -heating-local - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 (n,n1) material group in nuclide mean std. dev. 1 2 1 total 0.003108 0.000252 0 2 2 total 0.000000 0.000000 -(n,n2) - material group in nuclide mean std. dev. -1 2 1 total 0.002073 0.000192 -0 2 2 total 0.000000 0.000000 -(n,n3) - material group in nuclide mean std. dev. -1 2 1 total 0.000774 0.000067 -0 2 2 total 0.000000 0.000000 -(n,n4) - material group in nuclide mean std. dev. -1 2 1 total 0.00075 0.000067 -0 2 2 total 0.00000 0.000000 -(n,n5) - material group in nuclide mean std. dev. -1 2 1 total 0.000646 0.00006 -0 2 2 total 0.000000 0.00000 -(n,n6) - material group in nuclide mean std. dev. -1 2 1 total 0.00045 0.000039 -0 2 2 total 0.00000 0.000000 -(n,n7) - material group in nuclide mean std. dev. -1 2 1 total 0.000325 0.000031 -0 2 2 total 0.000000 0.000000 -(n,n8) - material group in nuclide mean std. dev. -1 2 1 total 0.000173 0.000018 -0 2 2 total 0.000000 0.000000 -(n,n9) - material group in nuclide mean std. dev. -1 2 1 total 0.000135 0.000015 -0 2 2 total 0.000000 0.000000 -(n,n10) - material group in nuclide mean std. dev. -1 2 1 total 0.000044 0.000006 -0 2 2 total 0.000000 0.000000 -(n,n11) - material group in nuclide mean std. dev. -1 2 1 total 0.000011 0.000001 -0 2 2 total 0.000000 0.000000 -(n,n12) - material group in nuclide mean std. dev. -1 2 1 total 0.000028 0.000004 -0 2 2 total 0.000000 0.000000 -(n,n13) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n14) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n15) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n16) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n17) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n18) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n19) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n20) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n21) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n22) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n23) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n24) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n25) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n26) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n27) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n28) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n29) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n30) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n31) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n32) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n33) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n34) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n35) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n36) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n37) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n38) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n39) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,n40) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p0) - material group in nuclide mean std. dev. -1 2 1 total 8.187834e-07 1.608798e-07 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,p1) - material group in nuclide mean std. dev. -1 2 1 total 5.982445e-07 1.230400e-07 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,p2) - material group in nuclide mean std. dev. -1 2 1 total 4.952422e-08 1.325066e-08 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,p3) - material group in nuclide mean std. dev. -1 2 1 total 2.123867e-07 5.063386e-08 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,p4) - material group in nuclide mean std. dev. -1 2 1 total 1.551515e-07 4.218006e-08 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,p5) - material group in nuclide mean std. dev. -1 2 1 total 8.306648e-08 2.730126e-08 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,p6) - material group in nuclide mean std. dev. -1 2 1 total 1.527984e-08 6.819535e-09 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,p7) - material group in nuclide mean std. dev. -1 2 1 total 2.893616e-08 8.258429e-09 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,p8) - material group in nuclide mean std. dev. -1 2 1 total 5.213847e-08 2.066776e-08 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,p9) - material group in nuclide mean std. dev. -1 2 1 total 5.369632e-08 1.772363e-08 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,p10) - material group in nuclide mean std. dev. -1 2 1 total 6.954982e-08 2.598861e-08 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,p11) - material group in nuclide mean std. dev. -1 2 1 total 5.341202e-08 2.210101e-08 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,p12) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p13) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p14) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p15) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p16) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p17) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p18) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p19) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p20) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p21) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p22) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p23) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p24) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p25) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p26) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p27) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p28) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p29) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p30) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p31) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p32) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p33) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p34) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p35) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p36) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p37) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p38) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p39) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p40) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p41) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p42) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p43) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p44) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p45) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p46) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p47) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,p48) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d0) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d1) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d2) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d3) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d4) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d5) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d6) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d7) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d8) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d9) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d10) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d11) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d12) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d13) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d14) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d15) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d16) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d17) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d18) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d19) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d20) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d21) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d22) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d23) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d24) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d25) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d26) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d27) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d28) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d29) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d30) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d31) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d32) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d33) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d34) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d35) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d36) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d37) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d38) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d39) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d40) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d41) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d42) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d43) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d44) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d45) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d46) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d47) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,d48) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t0) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t1) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t2) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t3) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t4) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t5) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t6) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t7) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t8) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t9) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t10) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t11) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t12) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t13) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t14) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t15) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t16) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t17) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t18) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t19) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t20) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t21) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t22) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t23) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t24) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t25) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t26) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t27) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t28) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t29) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t30) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t31) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t32) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t33) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t34) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t35) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t36) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t37) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t38) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t39) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t40) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t41) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t42) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t43) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t44) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t45) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t46) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t47) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,t48) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He0) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He1) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He2) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He3) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He4) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He5) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He6) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He7) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He8) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He9) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He10) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He11) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He12) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He13) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He14) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He15) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He16) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He17) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He18) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He19) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He20) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He21) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He22) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He23) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He24) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He25) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He26) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He27) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He28) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He29) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He30) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He31) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He32) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He33) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He34) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He35) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He36) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He37) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He38) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He39) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He40) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He41) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He42) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He43) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He44) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He45) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He46) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He47) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,3He48) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 (n,a0) material group in nuclide mean std. dev. 1 2 1 total 8.426133e-07 7.088213e-08 0 2 2 total 2.733143e-07 2.539166e-08 -(n,a1) - material group in nuclide mean std. dev. -1 2 1 total 8.111158e-08 1.637917e-08 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a2) - material group in nuclide mean std. dev. -1 2 1 total 3.065762e-08 1.144497e-08 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a3) - material group in nuclide mean std. dev. -1 2 1 total 1.068284e-08 6.009240e-09 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a4) - material group in nuclide mean std. dev. -1 2 1 total 1.212970e-08 5.970811e-09 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a5) - material group in nuclide mean std. dev. -1 2 1 total 5.003474e-09 2.224568e-09 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a6) - material group in nuclide mean std. dev. -1 2 1 total 6.166393e-09 3.112158e-09 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a7) - material group in nuclide mean std. dev. -1 2 1 total 5.611547e-09 2.890685e-09 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a8) - material group in nuclide mean std. dev. -1 2 1 total 3.793611e-09 1.935920e-09 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a9) - material group in nuclide mean std. dev. -1 2 1 total 1.857119e-09 8.792743e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a10) - material group in nuclide mean std. dev. -1 2 1 total 1.501178e-09 7.171250e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a11) - material group in nuclide mean std. dev. -1 2 1 total 1.574910e-09 7.808703e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a12) - material group in nuclide mean std. dev. -1 2 1 total 1.346363e-09 6.614696e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a13) - material group in nuclide mean std. dev. -1 2 1 total 1.274516e-09 6.253215e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a14) - material group in nuclide mean std. dev. -1 2 1 total 1.132244e-09 5.771471e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a15) - material group in nuclide mean std. dev. -1 2 1 total 9.342022e-10 5.018295e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a16) - material group in nuclide mean std. dev. -1 2 1 total 8.676969e-10 4.560924e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a17) - material group in nuclide mean std. dev. -1 2 1 total 7.692156e-10 3.938850e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a18) - material group in nuclide mean std. dev. -1 2 1 total 7.001820e-10 3.621786e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a19) - material group in nuclide mean std. dev. -1 2 1 total 8.037652e-10 4.268582e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a20) - material group in nuclide mean std. dev. -1 2 1 total 6.557396e-10 3.540489e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a21) - material group in nuclide mean std. dev. -1 2 1 total 4.650172e-10 2.694122e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a22) - material group in nuclide mean std. dev. -1 2 1 total 5.418169e-10 2.993303e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a23) - material group in nuclide mean std. dev. -1 2 1 total 2.781029e-10 1.478835e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a24) - material group in nuclide mean std. dev. -1 2 1 total 5.787690e-10 3.201111e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a25) - material group in nuclide mean std. dev. -1 2 1 total 1.506724e-10 9.188318e-11 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a26) - material group in nuclide mean std. dev. -1 2 1 total 4.006915e-10 2.236672e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a27) - material group in nuclide mean std. dev. -1 2 1 total 4.107877e-10 2.304569e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a28) - material group in nuclide mean std. dev. -1 2 1 total 3.913310e-10 2.247667e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a29) - material group in nuclide mean std. dev. -1 2 1 total 3.374421e-10 1.944856e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a30) - material group in nuclide mean std. dev. -1 2 1 total 2.933203e-10 1.663174e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a31) - material group in nuclide mean std. dev. -1 2 1 total 3.301597e-10 1.940828e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a32) - material group in nuclide mean std. dev. -1 2 1 total 1.504991e-10 9.577278e-11 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a33) - material group in nuclide mean std. dev. -1 2 1 total 1.968165e-10 1.215066e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a34) - material group in nuclide mean std. dev. -1 2 1 total 2.459990e-10 1.481238e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a35) - material group in nuclide mean std. dev. -1 2 1 total 6.171189e-11 3.888766e-11 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a36) - material group in nuclide mean std. dev. -1 2 1 total 2.560736e-10 1.576972e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a37) - material group in nuclide mean std. dev. -1 2 1 total 2.145996e-10 1.326863e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a38) - material group in nuclide mean std. dev. -1 2 1 total 2.463189e-10 1.537167e-10 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a39) - material group in nuclide mean std. dev. -1 2 1 total 1.601384e-10 9.932662e-11 -0 2 2 total 0.000000e+00 0.000000e+00 -(n,a40) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,a41) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,a42) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,a43) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,a44) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,a45) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,a46) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,a47) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,a48) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n0) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n1) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n2) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n3) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n4) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n5) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n6) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n7) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n8) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n9) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n10) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n11) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n12) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n13) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n14) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2n15) - material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 -(n,2nd) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,3n) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,na) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n3a) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2na) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,3na) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,np) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n2a) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n2a) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,nd) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,nt) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n3He) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,nd2a) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,nt2a) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,4n) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2np) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,3np) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n2p) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,npa) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 (n,nc) matrix material group in group out nuclide mean std. dev. 3 2 1 1 total 0.001782 0.000845 2 2 1 2 total 0.000000 0.000000 1 2 2 1 total 0.000000 0.000000 0 2 2 2 total 0.000000 0.000000 -(n,5n) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,6n) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2nt) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,4np) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,3nd) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,nda) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2npa) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,7n) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,8n) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,5np) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,6np) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,7np) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,4na) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,5na) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,6na) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,7na) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,4nd) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,5nd) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,6nd) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,3nt) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,4nt) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,5nt) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,6nt) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n3He) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,3n3He) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,4n3He) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,3n2p) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,3n2a) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,3npa) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,npd) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,npt) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,ndt) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,np3He) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,nd3He) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,nt3He) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,nta) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n2p) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,4n2p) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,4n2a) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,4npa) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n3p) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,3n2pa) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,5n2p) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2nc) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 (n,n1) matrix material group in group out nuclide mean std. dev. 3 2 1 1 total 0.002228 0.000725 2 2 1 2 total 0.000000 0.000000 1 2 2 1 total 0.000000 0.000000 0 2 2 2 total 0.000000 0.000000 -(n,n2) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.002673 0.000859 -2 2 1 2 total 0.000000 0.000000 -1 2 2 1 total 0.000000 0.000000 -0 2 2 2 total 0.000000 0.000000 -(n,n3) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.000891 0.00055 -2 2 1 2 total 0.000000 0.00000 -1 2 2 1 total 0.000000 0.00000 -0 2 2 2 total 0.000000 0.00000 -(n,n4) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n5) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n6) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n7) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.000446 0.000447 -2 2 1 2 total 0.000000 0.000000 -1 2 2 1 total 0.000000 0.000000 -0 2 2 2 total 0.000000 0.000000 -(n,n8) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n9) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n10) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n11) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n12) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n13) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n14) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n15) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n16) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n17) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n18) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n19) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n20) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n21) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n22) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n23) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n24) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n25) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n26) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n27) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n28) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n29) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n30) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n31) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n32) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n33) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n34) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n35) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n36) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n37) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n38) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n39) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,n40) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n0) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n1) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n2) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n3) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n4) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n5) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n6) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n7) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n8) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n9) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n10) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n11) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n12) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n13) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n14) matrix - material group in group out nuclide mean std. dev. -3 2 1 1 total 0.0 0.0 -2 2 1 2 total 0.0 0.0 -1 2 2 1 total 0.0 0.0 -0 2 2 2 total 0.0 0.0 -(n,2n15) matrix +(n,2n) matrix material group in group out nuclide mean std. dev. 3 2 1 1 total 0.0 0.0 2 2 1 2 total 0.0 0.0 @@ -5326,366 +782,26 @@ nu-diffusion-coefficient material group in nuclide mean std. dev. 1 3 1 total 0.000045 0.000027 0 3 2 total 0.000000 0.000000 -(n,2nd) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 (n,2n) material group in nuclide mean std. dev. 1 3 1 total 0.0 0.0 0 3 2 total 0.0 0.0 -(n,3n) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 (n,na) material group in nuclide mean std. dev. 1 3 1 total 6.743945e-11 6.604830e-11 0 3 2 total 0.000000e+00 0.000000e+00 -(n,n3a) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2na) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3na) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,np) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n2a) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n2a) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,nd) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,nt) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n3He) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,nd2a) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,nt2a) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,4n) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2np) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3np) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n2p) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,npa) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 (n,nc) material group in nuclide mean std. dev. 1 3 1 total 0.0 0.0 0 3 2 total 0.0 0.0 -(n,disappear) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 (n,gamma) material group in nuclide mean std. dev. 1 3 1 total 0.000219 0.000014 0 3 2 total 0.011034 0.001305 -(n,p) - material group in nuclide mean std. dev. -1 3 1 total 3.105883e-08 2.515704e-09 -0 3 2 total 3.042510e-09 3.597211e-10 -(n,d) - material group in nuclide mean std. dev. -1 3 1 total 3.501368e-09 9.905391e-10 -0 3 2 total 0.000000e+00 0.000000e+00 -(n,t) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 (n,a) material group in nuclide mean std. dev. 1 3 1 total 0.000471 0.000031 0 3 2 total 0.020653 0.002442 -(n,2a) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3a) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2p) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,pa) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t2a) - material group in nuclide mean std. dev. -1 3 1 total 1.307412e-07 1.166081e-08 -0 3 2 total 3.762551e-08 4.448547e-09 -(n,d2a) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,pd) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,pt) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,da) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,5n) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,6n) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2nt) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,ta) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,4np) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3nd) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,nda) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2npa) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,7n) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,8n) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,5np) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,6np) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,7np) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,4na) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,5na) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,6na) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,7na) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,4nd) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,5nd) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,6nd) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3nt) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,4nt) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,5nt) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,6nt) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n3He) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3n3He) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,4n3He) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3n2p) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3n2a) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3npa) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,dt) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,npd) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,npt) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,ndt) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,np3He) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,nd3He) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,nt3He) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,nta) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n2p) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p3He) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d3He) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3Hea) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,4n2p) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,4n2a) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,4npa) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3p) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n3p) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3n2pa) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,5n2p) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,Xp) - material group in nuclide mean std. dev. -1 3 1 total 3.105983e-08 2.516107e-09 -0 3 2 total 3.042510e-09 3.597211e-10 -(n,Xd) - material group in nuclide mean std. dev. -1 3 1 total 0.000217 0.000014 -0 3 2 total 0.011029 0.001304 -(n,Xt) - material group in nuclide mean std. dev. -1 3 1 total 1.307412e-07 1.166081e-08 -0 3 2 total 3.762551e-08 4.448547e-09 -(n,X3He) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 (n,Xa) material group in nuclide mean std. dev. 1 3 1 total 0.000472 0.000031 @@ -5698,1959 +814,27 @@ damage-energy material group in nuclide mean std. dev. 1 3 1 total 1186.090822 44.862980 0 3 2 total 337.187426 39.868517 -(n,pc) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,dc) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,tc) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3Hec) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,ac) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2nc) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -heating-local - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 (n,n1) material group in nuclide mean std. dev. 1 3 1 total 0.000001 6.118682e-07 0 3 2 total 0.000000 0.000000e+00 -(n,n2) - material group in nuclide mean std. dev. -1 3 1 total 0.000033 0.000017 -0 3 2 total 0.000000 0.000000 -(n,n3) - material group in nuclide mean std. dev. -1 3 1 total 0.000005 0.000004 -0 3 2 total 0.000000 0.000000 -(n,n4) - material group in nuclide mean std. dev. -1 3 1 total 0.000005 0.000005 -0 3 2 total 0.000000 0.000000 -(n,n5) - material group in nuclide mean std. dev. -1 3 1 total 3.433156e-09 9.845768e-10 -0 3 2 total 0.000000e+00 0.000000e+00 -(n,n6) - material group in nuclide mean std. dev. -1 3 1 total 2.715569e-09 1.867713e-09 -0 3 2 total 0.000000e+00 0.000000e+00 -(n,n7) - material group in nuclide mean std. dev. -1 3 1 total 1.447480e-09 4.083538e-10 -0 3 2 total 0.000000e+00 0.000000e+00 -(n,n8) - material group in nuclide mean std. dev. -1 3 1 total 4.960111e-10 1.356859e-10 -0 3 2 total 0.000000e+00 0.000000e+00 -(n,n9) - material group in nuclide mean std. dev. -1 3 1 total 1.297766e-09 6.085607e-10 -0 3 2 total 0.000000e+00 0.000000e+00 -(n,n10) - material group in nuclide mean std. dev. -1 3 1 total 4.303991e-09 2.232772e-09 -0 3 2 total 0.000000e+00 0.000000e+00 -(n,n11) - material group in nuclide mean std. dev. -1 3 1 total 3.784266e-10 2.370870e-10 -0 3 2 total 0.000000e+00 0.000000e+00 -(n,n12) - material group in nuclide mean std. dev. -1 3 1 total 8.064497e-10 5.549579e-10 -0 3 2 total 0.000000e+00 0.000000e+00 -(n,n13) - material group in nuclide mean std. dev. -1 3 1 total 4.202255e-10 4.126831e-10 -0 3 2 total 0.000000e+00 0.000000e+00 -(n,n14) - material group in nuclide mean std. dev. -1 3 1 total 1.711097e-10 1.661696e-10 -0 3 2 total 0.000000e+00 0.000000e+00 -(n,n15) - material group in nuclide mean std. dev. -1 3 1 total 9.967363e-13 9.972028e-13 -0 3 2 total 0.000000e+00 0.000000e+00 -(n,n16) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n17) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n18) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n19) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n20) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n21) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n22) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n23) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n24) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n25) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n26) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n27) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n28) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n29) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n30) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n31) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n32) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n33) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n34) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n35) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n36) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n37) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n38) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n39) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,n40) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p0) - material group in nuclide mean std. dev. -1 3 1 total 2.607190e-08 1.833816e-09 -0 3 2 total 3.042510e-09 3.597211e-10 -(n,p1) - material group in nuclide mean std. dev. -1 3 1 total 4.362104e-09 9.397272e-10 -0 3 2 total 0.000000e+00 0.000000e+00 -(n,p2) - material group in nuclide mean std. dev. -1 3 1 total 2.175490e-10 1.637942e-10 -0 3 2 total 0.000000e+00 0.000000e+00 -(n,p3) - material group in nuclide mean std. dev. -1 3 1 total 1.305293e-10 9.827653e-11 -0 3 2 total 0.000000e+00 0.000000e+00 -(n,p4) - material group in nuclide mean std. dev. -1 3 1 total 4.619524e-11 3.620095e-11 -0 3 2 total 0.000000e+00 0.000000e+00 -(n,p5) - material group in nuclide mean std. dev. -1 3 1 total 2.305561e-10 1.811156e-10 -0 3 2 total 0.000000e+00 0.000000e+00 -(n,p6) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p7) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p8) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p9) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p10) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p11) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p12) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p13) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p14) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p15) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p16) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p17) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p18) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p19) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p20) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p21) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p22) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p23) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p24) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p25) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p26) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p27) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p28) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p29) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p30) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p31) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p32) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p33) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p34) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p35) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p36) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p37) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p38) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p39) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p40) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p41) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p42) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p43) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p44) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p45) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p46) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p47) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,p48) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d0) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d1) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d2) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d3) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d4) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d5) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d6) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d7) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d8) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d9) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d10) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d11) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d12) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d13) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d14) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d15) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d16) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d17) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d18) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d19) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d20) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d21) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d22) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d23) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d24) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d25) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d26) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d27) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d28) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d29) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d30) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d31) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d32) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d33) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d34) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d35) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d36) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d37) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d38) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d39) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d40) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d41) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d42) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d43) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d44) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d45) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d46) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d47) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,d48) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t0) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t1) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t2) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t3) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t4) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t5) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t6) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t7) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t8) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t9) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t10) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t11) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t12) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t13) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t14) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t15) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t16) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t17) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t18) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t19) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t20) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t21) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t22) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t23) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t24) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t25) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t26) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t27) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t28) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t29) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t30) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t31) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t32) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t33) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t34) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t35) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t36) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t37) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t38) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t39) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t40) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t41) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t42) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t43) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t44) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t45) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t46) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t47) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,t48) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He0) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He1) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He2) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He3) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He4) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He5) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He6) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He7) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He8) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He9) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He10) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He11) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He12) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He13) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He14) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He15) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He16) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He17) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He18) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He19) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He20) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He21) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He22) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He23) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He24) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He25) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He26) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He27) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He28) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He29) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He30) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He31) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He32) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He33) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He34) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He35) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He36) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He37) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He38) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He39) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He40) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He41) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He42) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He43) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He44) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He45) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He46) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He47) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,3He48) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 (n,a0) material group in nuclide mean std. dev. 1 3 1 total 0.000084 0.000012 0 3 2 total 0.001299 0.000154 -(n,a1) - material group in nuclide mean std. dev. -1 3 1 total 0.000383 0.000024 -0 3 2 total 0.019354 0.002288 -(n,a2) - material group in nuclide mean std. dev. -1 3 1 total 0.000002 0.000002 -0 3 2 total 0.000000 0.000000 -(n,a3) - material group in nuclide mean std. dev. -1 3 1 total 0.000002 0.000002 -0 3 2 total 0.000000 0.000000 -(n,a4) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a5) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a6) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a7) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a8) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a9) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a10) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a11) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a12) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a13) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a14) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a15) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a16) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a17) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a18) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a19) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a20) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a21) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a22) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a23) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a24) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a25) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a26) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a27) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a28) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a29) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a30) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a31) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a32) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a33) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a34) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a35) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a36) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a37) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a38) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a39) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a40) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a41) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a42) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a43) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a44) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a45) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a46) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a47) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,a48) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n0) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n1) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n2) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n3) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n4) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n5) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n6) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n7) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n8) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n9) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n10) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n11) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n12) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n13) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n14) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2n15) - material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 -(n,2nd) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,3n) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,na) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n3a) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2na) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,3na) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,np) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n2a) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n2a) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,nd) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,nt) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n3He) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,nd2a) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,nt2a) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,4n) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2np) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,3np) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n2p) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,npa) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 (n,nc) matrix material group in group out nuclide mean std. dev. 3 3 1 1 total 0.0 0.0 2 3 1 2 total 0.0 0.0 1 3 2 1 total 0.0 0.0 0 3 2 2 total 0.0 0.0 -(n,5n) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,6n) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2nt) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,4np) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,3nd) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,nda) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2npa) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,7n) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,8n) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,5np) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,6np) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,7np) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,4na) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,5na) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,6na) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,7na) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,4nd) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,5nd) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,6nd) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,3nt) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,4nt) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,5nt) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,6nt) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n3He) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,3n3He) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,4n3He) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,3n2p) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,3n2a) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,3npa) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,npd) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,npt) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,ndt) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,np3He) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,nd3He) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,nt3He) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,nta) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n2p) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,4n2p) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,4n2a) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,4npa) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n3p) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,3n2pa) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,5n2p) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2nc) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 (n,n1) matrix material group in group out nuclide mean std. dev. 3 3 1 1 total 0.0 0.0 2 3 1 2 total 0.0 0.0 1 3 2 1 total 0.0 0.0 0 3 2 2 total 0.0 0.0 -(n,n2) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n3) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n4) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n5) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n6) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n7) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n8) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n9) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n10) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n11) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n12) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n13) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n14) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n15) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n16) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n17) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n18) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n19) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n20) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n21) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n22) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n23) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n24) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n25) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n26) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n27) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n28) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n29) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n30) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n31) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n32) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n33) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n34) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n35) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n36) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n37) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n38) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n39) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,n40) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n0) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n1) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n2) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n3) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n4) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n5) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n6) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n7) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n8) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n9) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n10) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n11) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n12) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n13) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n14) matrix - material group in group out nuclide mean std. dev. -3 3 1 1 total 0.0 0.0 -2 3 1 2 total 0.0 0.0 -1 3 2 1 total 0.0 0.0 -0 3 2 2 total 0.0 0.0 -(n,2n15) matrix +(n,2n) matrix material group in group out nuclide mean std. dev. 3 3 1 1 total 0.0 0.0 2 3 1 2 total 0.0 0.0 diff --git a/tests/regression_tests/mgxs_library_no_nuclides/test.py b/tests/regression_tests/mgxs_library_no_nuclides/test.py index fdde8ca982..af14a5dc8f 100644 --- a/tests/regression_tests/mgxs_library_no_nuclides/test.py +++ b/tests/regression_tests/mgxs_library_no_nuclides/test.py @@ -2,7 +2,6 @@ import hashlib import openmc import openmc.mgxs -from openmc.data import REACTION_MT from openmc.examples import pwr_pin_cell from tests.testing_harness import PyAPITestHarness @@ -20,11 +19,17 @@ class MGXSTestHarness(PyAPITestHarness): self.mgxs_lib = openmc.mgxs.Library(self._model.geometry) self.mgxs_lib.by_nuclide = False - # Test all relevant MGXS types + # Test relevant MGXS types relevant_MGXS_TYPES = [item for item in openmc.mgxs.MGXS_TYPES if item != 'current'] - relevant_MGXS_TYPES += openmc.mgxs.ARBITRARY_VECTOR_TYPES - relevant_MGXS_TYPES += openmc.mgxs.ARBITRARY_MATRIX_TYPES + # Add in a subset of openmc.mgxs.ARBITRARY_VECTOR_TYPES and + # openmc.mgxs.ARBITRARY_MATRIX_TYPES so we can see the code works, + # but not use too much resources + relevant_MGXS_TYPES += [ + "(n,elastic)", "(n,level)", "(n,2n)", "(n,na)", "(n,nc)", + "(n,gamma)", "(n,a)", "(n,Xa)", "heating", "damage-energy", + "(n,n1)", "(n,a0)", "(n,nc) matrix", "(n,n1) matrix", + "(n,2n) matrix"] self.mgxs_lib.mgxs_types = tuple(relevant_MGXS_TYPES) + \ openmc.mgxs.MDGXS_TYPES self.mgxs_lib.energy_groups = energy_groups diff --git a/tests/regression_tests/mgxs_library_nuclides/inputs_true.dat b/tests/regression_tests/mgxs_library_nuclides/inputs_true.dat index 045b0ab8e2..f29a41f3d7 100644 --- a/tests/regression_tests/mgxs_library_nuclides/inputs_true.dat +++ b/tests/regression_tests/mgxs_library_nuclides/inputs_true.dat @@ -68,10 +68,10 @@ 0.0 20000000.0 - + 2 - + 3 @@ -461,7 +461,7 @@ 1 2 U234 U235 U238 O16 - (n,2nd) + (n,2n) tracklength @@ -473,7 +473,7 @@ 1 2 U234 U235 U238 O16 - (n,2n) + (n,na) tracklength @@ -485,7 +485,7 @@ 1 2 U234 U235 U238 O16 - (n,3n) + (n,nc) tracklength @@ -497,7 +497,7 @@ 1 2 U234 U235 U238 O16 - (n,na) + (n,gamma) tracklength @@ -509,7 +509,7 @@ 1 2 U234 U235 U238 O16 - (n,n3a) + (n,a) tracklength @@ -521,7 +521,7 @@ 1 2 U234 U235 U238 O16 - (n,2na) + (n,Xa) tracklength @@ -533,7 +533,7 @@ 1 2 U234 U235 U238 O16 - (n,3na) + heating tracklength @@ -545,7 +545,7 @@ 1 2 U234 U235 U238 O16 - (n,np) + damage-energy tracklength @@ -557,7 +557,7 @@ 1 2 U234 U235 U238 O16 - (n,n2a) + (n,n1) tracklength @@ -569,19435 +569,1111 @@ 1 2 U234 U235 U238 O16 - (n,2n2a) + (n,a0) tracklength 1 2 total flux - tracklength + analog - 1 2 + 1 2 5 U234 U235 U238 O16 - (n,nd) - tracklength + (n,nc) + analog 1 2 total flux - tracklength + analog - 1 2 + 1 2 5 U234 U235 U238 O16 - (n,nt) - tracklength + (n,n1) + analog 1 2 total flux - tracklength + analog - 1 2 + 1 2 5 U234 U235 U238 O16 - (n,n3He) - tracklength + (n,2n) + analog - 1 2 + 104 2 total flux tracklength - 1 2 - U234 U235 U238 O16 - (n,nd2a) + 104 2 + Zr90 Zr91 Zr92 Zr94 Zr96 + total tracklength - 1 2 + 104 2 total flux tracklength - 1 2 - U234 U235 U238 O16 - (n,nt2a) + 104 2 + Zr90 Zr91 Zr92 Zr94 Zr96 + total tracklength - 1 2 + 104 2 total flux - tracklength + analog - 1 2 - U234 U235 U238 O16 - (n,4n) - tracklength + 104 5 6 + Zr90 Zr91 Zr92 Zr94 Zr96 + scatter + analog - 1 2 + 104 2 total flux tracklength - 1 2 - U234 U235 U238 O16 - (n,2np) + 104 2 + Zr90 Zr91 Zr92 Zr94 Zr96 + total tracklength - 1 2 + 104 2 total flux - tracklength + analog - 1 2 - U234 U235 U238 O16 - (n,3np) - tracklength + 104 5 6 + Zr90 Zr91 Zr92 Zr94 Zr96 + nu-scatter + analog - 1 2 + 104 2 total flux tracklength - 1 2 - U234 U235 U238 O16 - (n,n2p) + 104 2 + Zr90 Zr91 Zr92 Zr94 Zr96 + absorption tracklength - 1 2 + 104 2 total flux tracklength - 1 2 - U234 U235 U238 O16 - (n,npa) + 104 2 + Zr90 Zr91 Zr92 Zr94 Zr96 + absorption tracklength - 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tracklength + analog + + + 104 2 5 + Zr90 Zr91 Zr92 Zr94 Zr96 + prompt-nu-fission + analog - 1 2 - U234 U235 U238 O16 - (n,6n) + 104 2 + total + flux tracklength - 1 2 - total - flux + 104 2 + Zr90 Zr91 Zr92 Zr94 Zr96 + total tracklength - 1 2 - U234 U235 U238 O16 - (n,2nt) - tracklength - - - 1 2 + 104 2 total flux - tracklength + analog + + + 104 5 6 + Zr90 Zr91 Zr92 Zr94 Zr96 + scatter + analog - 1 2 - U234 U235 U238 O16 - (n,ta) + 104 2 + total + flux tracklength - 1 2 - total - flux + 104 2 + Zr90 Zr91 Zr92 Zr94 Zr96 + total tracklength - 1 2 - U234 U235 U238 O16 - (n,4np) - tracklength - - - 1 2 + 104 2 total flux - tracklength + analog + + + 104 5 6 + Zr90 Zr91 Zr92 Zr94 Zr96 + nu-scatter + analog - 1 2 - U234 U235 U238 O16 - (n,3nd) + 104 2 + total + flux tracklength - 1 2 - total - flux + 104 2 + Zr90 Zr91 Zr92 Zr94 Zr96 + (n,elastic) tracklength - 1 2 - U234 U235 U238 O16 - (n,nda) + 104 2 + total + flux tracklength - 1 2 - total - flux + 104 2 + Zr90 Zr91 Zr92 Zr94 Zr96 + (n,level) tracklength - 1 2 - U234 U235 U238 O16 - (n,2npa) + 104 2 + total + flux tracklength - 1 2 - total - flux + 104 2 + Zr90 Zr91 Zr92 Zr94 Zr96 + (n,2n) tracklength - 1 2 - U234 U235 U238 O16 - (n,7n) + 104 2 + total + flux tracklength - 1 2 - total - flux + 104 2 + Zr90 Zr91 Zr92 Zr94 Zr96 + (n,na) tracklength - 1 2 - U234 U235 U238 O16 - (n,8n) + 104 2 + total + flux tracklength - 1 2 - total - flux + 104 2 + Zr90 Zr91 Zr92 Zr94 Zr96 + (n,nc) tracklength - 1 2 - U234 U235 U238 O16 - (n,5np) + 104 2 + total + flux tracklength - 1 2 - total - flux + 104 2 + Zr90 Zr91 Zr92 Zr94 Zr96 + (n,gamma) tracklength - 1 2 - U234 U235 U238 O16 - (n,6np) + 104 2 + total + flux tracklength - 1 2 - total - flux + 104 2 + Zr90 Zr91 Zr92 Zr94 Zr96 + (n,a) tracklength - 1 2 - U234 U235 U238 O16 - (n,7np) + 104 2 + total + flux tracklength - 1 2 - total - flux + 104 2 + Zr90 Zr91 Zr92 Zr94 Zr96 + (n,Xa) tracklength - 1 2 - U234 U235 U238 O16 - (n,4na) + 104 2 + total + flux tracklength - 1 2 - total - flux + 104 2 + Zr90 Zr91 Zr92 Zr94 Zr96 + heating tracklength - 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H1 O16 B10 B11 - (n,n35) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,n36) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,n37) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,n38) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,n39) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,n40) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,2n0) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,2n1) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,2n2) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,2n3) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,2n4) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,2n5) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,2n6) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,2n7) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,2n8) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,2n9) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,2n10) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,2n11) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,2n12) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,2n13) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,2n14) - analog - - - 2479 2 - total - flux - analog - - - 2479 2 5 - H1 O16 B10 B11 - (n,2n15) analog diff --git a/tests/regression_tests/mgxs_library_nuclides/results_true.dat b/tests/regression_tests/mgxs_library_nuclides/results_true.dat index 0b0349aacc..a2be43e800 100644 --- a/tests/regression_tests/mgxs_library_nuclides/results_true.dat +++ b/tests/regression_tests/mgxs_library_nuclides/results_true.dat @@ -1 +1 @@ -7462fdc05825053847d93b9238b57d47ab5eb9244542279489a23b2a87423e7e58d22efa9b6db7db74ab9628b73ff37750af3de60102da5ad05f69700a1b3b8d \ No newline at end of file +a9999488e2aa2ad0f1d694afedb71fbb56f1d0c8e8abdb6616698505a9d85302bf90586866fdb58eac96f76712a2dfbc884cc03087df7b5d148fb29d14dd2bbb \ No newline at end of file diff --git a/tests/regression_tests/mgxs_library_nuclides/test.py b/tests/regression_tests/mgxs_library_nuclides/test.py index 0305e00793..8a7673565e 100644 --- a/tests/regression_tests/mgxs_library_nuclides/test.py +++ b/tests/regression_tests/mgxs_library_nuclides/test.py @@ -18,11 +18,17 @@ class MGXSTestHarness(PyAPITestHarness): self.mgxs_lib = openmc.mgxs.Library(self._model.geometry) self.mgxs_lib.by_nuclide = True - # Test relevant all MGXS types + # Test relevant MGXS types relevant_MGXS_TYPES = [item for item in openmc.mgxs.MGXS_TYPES if item != 'current'] - relevant_MGXS_TYPES += openmc.mgxs.ARBITRARY_VECTOR_TYPES - relevant_MGXS_TYPES += openmc.mgxs.ARBITRARY_MATRIX_TYPES + # Add in a subset of openmc.mgxs.ARBITRARY_VECTOR_TYPES and + # openmc.mgxs.ARBITRARY_MATRIX_TYPES so we can see the code works, + # but not use too much resources + relevant_MGXS_TYPES += [ + "(n,elastic)", "(n,level)", "(n,2n)", "(n,na)", "(n,nc)", + "(n,gamma)", "(n,a)", "(n,Xa)", "heating", "damage-energy", + "(n,n1)", "(n,a0)", "(n,nc) matrix", "(n,n1) matrix", + "(n,2n) matrix"] self.mgxs_lib.mgxs_types = tuple(relevant_MGXS_TYPES) self.mgxs_lib.energy_groups = energy_groups self.mgxs_lib.legendre_order = 3 From 1e2735df93787664bda58273c009e6d85b824a59 Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Fri, 30 Oct 2020 23:20:05 -0500 Subject: [PATCH 53/79] Updating h5py calls in the plot test files. --- tests/regression_tests/plot/test.py | 8 ++++---- tests/regression_tests/plot_overlaps/test.py | 8 ++++---- tests/regression_tests/plot_voxel/test.py | 10 +++++----- 3 files changed, 13 insertions(+), 13 deletions(-) diff --git a/tests/regression_tests/plot/test.py b/tests/regression_tests/plot/test.py index bfaef019c1..a6f7306a0e 100644 --- a/tests/regression_tests/plot/test.py +++ b/tests/regression_tests/plot/test.py @@ -42,10 +42,10 @@ class PlotTestHarness(TestHarness): # Add voxel data to results with h5py.File(fname, 'r') as fh: outstr += fh.attrs['filetype'] - outstr += fh.attrs['num_voxels'].tostring() - outstr += fh.attrs['lower_left'].tostring() - outstr += fh.attrs['voxel_width'].tostring() - outstr += fh['data'].value.tostring() + outstr += fh.attrs['num_voxels'].tobytes() + outstr += fh.attrs['lower_left'].tobytes() + outstr += fh.attrs['voxel_width'].tobytes() + outstr += fh['data'][()].tobytes() # Hash the information and return. sha512 = hashlib.sha512() diff --git a/tests/regression_tests/plot_overlaps/test.py b/tests/regression_tests/plot_overlaps/test.py index d8c0943cf5..62236081b3 100644 --- a/tests/regression_tests/plot_overlaps/test.py +++ b/tests/regression_tests/plot_overlaps/test.py @@ -42,10 +42,10 @@ class PlotTestHarness(TestHarness): # Add voxel data to results with h5py.File(fname, 'r') as fh: outstr += fh.attrs['filetype'] - outstr += fh.attrs['num_voxels'].tostring() - outstr += fh.attrs['lower_left'].tostring() - outstr += fh.attrs['voxel_width'].tostring() - outstr += fh['data'].value.tostring() + outstr += fh.attrs['num_voxels'].tobytes() + outstr += fh.attrs['lower_left'].tobytes() + outstr += fh.attrs['voxel_width'].tobytes() + outstr += fh['data'][()].tobytes() # Hash the information and return. sha512 = hashlib.sha512() diff --git a/tests/regression_tests/plot_voxel/test.py b/tests/regression_tests/plot_voxel/test.py index d2767e2f18..3b7a6bef28 100644 --- a/tests/regression_tests/plot_voxel/test.py +++ b/tests/regression_tests/plot_voxel/test.py @@ -23,7 +23,7 @@ class PlotVoxelTestHarness(TestHarness): check_call(['../../../scripts/openmc-voxel-to-vtk'] + glob.glob('plot_4.h5')) - + def _test_output_created(self): """Make sure *.ppm has been created.""" for fname in self._plot_names: @@ -44,10 +44,10 @@ class PlotVoxelTestHarness(TestHarness): # Add voxel data to results with h5py.File(fname, 'r') as fh: outstr += fh.attrs['filetype'] - outstr += fh.attrs['num_voxels'].tostring() - outstr += fh.attrs['lower_left'].tostring() - outstr += fh.attrs['voxel_width'].tostring() - outstr += fh['data'].value.tostring() + outstr += fh.attrs['num_voxels'].tobytes() + outstr += fh.attrs['lower_left'].tobytes() + outstr += fh.attrs['voxel_width'].tobytes() + outstr += fh['data'][()].tobytes() # Hash the information and return. sha512 = hashlib.sha512() From 2d94535627a1aeeb6578eb6816ca4c127ab6b1f4 Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Sat, 31 Oct 2020 00:20:00 -0500 Subject: [PATCH 54/79] Another .value replacement in the track-to-vtk script. --- scripts/openmc-track-to-vtk | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/scripts/openmc-track-to-vtk b/scripts/openmc-track-to-vtk index fa154a2a7f..3c781d19ec 100755 --- a/scripts/openmc-track-to-vtk +++ b/scripts/openmc-track-to-vtk @@ -46,7 +46,7 @@ def main(): n_coords = track.attrs['n_coords'] coords = [] for i in range(n_particles): - coords.append(track['coordinates_' + str(i + 1)].value) + coords.append(track['coordinates_' + str(i + 1)][()]) for j in range(n_coords[i]): points.InsertNextPoint(coords[i][j,:]) From f60364421238b40edb3298c19bf699ccf75c57be Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Mon, 2 Nov 2020 15:26:08 -0600 Subject: [PATCH 55/79] Add missing 'import sys' in helpers.py --- openmc/deplete/helpers.py | 5 +++-- 1 file changed, 3 insertions(+), 2 deletions(-) diff --git a/openmc/deplete/helpers.py b/openmc/deplete/helpers.py index 0f55bb910e..6c3badc090 100644 --- a/openmc/deplete/helpers.py +++ b/openmc/deplete/helpers.py @@ -1,11 +1,12 @@ """ Class for normalizing fission energy deposition """ +import bisect +from collections import defaultdict from copy import deepcopy from itertools import product from numbers import Real -import bisect -from collections import defaultdict +import sys from numpy import dot, zeros, newaxis, asarray From 954450a84145fe2a3feda908a2a7029efc02fab5 Mon Sep 17 00:00:00 2001 From: Miriam Date: Wed, 4 Nov 2020 16:58:43 +0000 Subject: [PATCH 56/79] Fixed several bugs related to decay-rate 1) In mdgxs.py, DecayRate, get_xs(). There is no need to reverse the order since there isn't an energy group filter anymore. Also, the new_shape addition formats the cross section like all the others. I updated mgxs_library_hdf5 test results accordingly. 2) In material.cpp. If you use a macroscopic dnesity other than 1.0, the code still pushed back '1.0'. My change fixes that. Using a macro density other than 1.0 wasn't tested anywhere, so I modifed mg_convert to take a density of 1.1. The default macro density of 1.0 is used in many other tests. 3) tally_scoring.cpp. Notice that the score is accumulated, then sent to the function score_fission_delayed_dg where the tally is accumulated. This amounts to "double accumulation". It makes sense to accumulate the score over the delayed groups if there is no delayed group filter, but in this case, when delayed group filter is not None, the score needs to reset each time. In other parts of SCORE_DECAY_RATE, I think the distinction between accumulating and resetting the score is correct. The only place I wasn't sure was line 1057 (and its equivalent in multi-group, line 1962). It's too bad the decay-rate isn't tested very thoroughly. Although I don't have time to do it myself, I think adding a DelayedGroups filter to the mg_tallies test would be a good start. --- openmc/mgxs/mdgxs.py | 6 +---- src/material.cpp | 4 ++-- src/tallies/tally_scoring.cpp | 4 ++-- .../mg_convert/inputs_true.dat | 2 +- .../mg_convert/results_true.dat | 24 +++++++++---------- tests/regression_tests/mg_convert/test.py | 2 +- .../mgxs_library_hdf5/results_true.dat | 16 +++++++++---- 7 files changed, 31 insertions(+), 27 deletions(-) diff --git a/openmc/mgxs/mdgxs.py b/openmc/mgxs/mdgxs.py index 8f35d58799..f511579528 100644 --- a/openmc/mgxs/mdgxs.py +++ b/openmc/mgxs/mdgxs.py @@ -2044,13 +2044,9 @@ class DecayRate(MDGXS): num_delayed_groups) else: new_shape = (num_subdomains, num_delayed_groups) + new_shape += xs.shape[1:] xs = np.reshape(xs, new_shape) - # Reverse data if user requested increasing energy groups since - # tally data is stored in order of increasing energies - if order_groups == 'increasing': - xs = xs[..., ::-1, :] - if squeeze: # We want to squeeze out everything but the polar, azimuthal, # delayed group, and energy group data. diff --git a/src/material.cpp b/src/material.cpp index 1d4e18108e..fed915043c 100644 --- a/src/material.cpp +++ b/src/material.cpp @@ -149,7 +149,7 @@ Material::Material(pugi::xml_node node) // Set density for macroscopic data if (units == "macro") { - densities.push_back(1.0); + densities.push_back(density_); } else { fatal_error("Units can only be macro for macroscopic data " + name); } @@ -169,7 +169,7 @@ Material::Material(pugi::xml_node node) // Check if no atom/weight percents were specified or if both atom and // weight percents were specified if (units == "macro") { - densities.push_back(1.0); + densities.push_back(density_); } else { bool has_ao = check_for_node(node_nuc, "ao"); bool has_wo = check_for_node(node_nuc, "wo"); diff --git a/src/tallies/tally_scoring.cpp b/src/tallies/tally_scoring.cpp index 396ab2f82b..0ffcf821bd 100644 --- a/src/tallies/tally_scoring.cpp +++ b/src/tallies/tally_scoring.cpp @@ -1995,13 +1995,13 @@ score_general_mg(Particle& p, int i_tally, int start_index, int filter_index, for (auto d_bin = 0; d_bin < filt.n_bins(); ++d_bin) { auto d = filt.groups()[d_bin] - 1; if (i_nuclide >= 0) { - score += atom_density * flux + score = atom_density * flux * nuc_xs.get_xs(MgxsType::DECAY_RATE, p_g, nullptr, nullptr, &d) * nuc_xs.get_xs(MgxsType::DELAYED_NU_FISSION, p_g, nullptr, nullptr, &d); } else { - score += flux + score = flux * macro_xs.get_xs(MgxsType::DECAY_RATE, p_g, nullptr, nullptr, &d) * macro_xs.get_xs(MgxsType::DELAYED_NU_FISSION, p_g, nullptr, diff --git a/tests/regression_tests/mg_convert/inputs_true.dat b/tests/regression_tests/mg_convert/inputs_true.dat index e2c3a01fa7..9db9b7d7c3 100644 --- a/tests/regression_tests/mg_convert/inputs_true.dat +++ b/tests/regression_tests/mg_convert/inputs_true.dat @@ -10,7 +10,7 @@ ./mgxs.h5 - + diff --git a/tests/regression_tests/mg_convert/results_true.dat b/tests/regression_tests/mg_convert/results_true.dat index a52b929dcf..5a17fe1073 100644 --- a/tests/regression_tests/mg_convert/results_true.dat +++ b/tests/regression_tests/mg_convert/results_true.dat @@ -1,24 +1,24 @@ k-combined: -9.930873E-01 2.221904E-03 +9.834385E-01 7.095193E-03 k-combined: -9.948148E-01 1.216270E-03 +9.936965E-01 4.118371E-03 k-combined: -9.930873E-01 2.221904E-03 +9.834385E-01 7.095193E-03 k-combined: -9.755034E-01 6.178296E-03 +9.977232E-01 1.084193E-02 k-combined: -9.738059E-01 4.529068E-03 +9.945011E-01 5.571771E-03 k-combined: -9.866847E-01 9.485912E-03 +9.982627E-01 2.662444E-03 k-combined: -9.755024E-01 6.179047E-03 +9.977232E-01 1.084193E-02 k-combined: -9.738061E-01 4.529462E-03 +9.945007E-01 5.571589E-03 k-combined: -9.866835E-01 9.485832E-03 +9.982620E-01 2.662746E-03 k-combined: -9.719024E-01 4.213166E-03 +1.000071E+00 3.364791E-03 k-combined: -9.930873E-01 2.221904E-03 +9.834385E-01 7.095193E-03 k-combined: -9.930873E-01 2.221904E-03 +9.834385E-01 7.095193E-03 diff --git a/tests/regression_tests/mg_convert/test.py b/tests/regression_tests/mg_convert/test.py index 4cc6b656a2..f22c15dc07 100755 --- a/tests/regression_tests/mg_convert/test.py +++ b/tests/regression_tests/mg_convert/test.py @@ -67,7 +67,7 @@ class MGXSTestHarness(PyAPITestHarness): # Instantiate some Materials and register the appropriate objects mat = openmc.Material(material_id=1, name='UO2 fuel') - mat.set_density('macro', 1.0) + mat.set_density('macro', 1.1) mat.add_macroscopic(uo2_data) # Instantiate a Materials collection and export to XML diff --git a/tests/regression_tests/mgxs_library_hdf5/results_true.dat b/tests/regression_tests/mgxs_library_hdf5/results_true.dat index 4a796b0a51..4aa243b9e3 100644 --- a/tests/regression_tests/mgxs_library_hdf5/results_true.dat +++ b/tests/regression_tests/mgxs_library_hdf5/results_true.dat @@ -193,10 +193,18 @@ domain=1 type=beta [1.21876271e-04 8.77101834e-05] [4.95946084e-05 3.67414816e-05]] domain=1 type=decay-rate -[1.33568413e-02 3.25887984e-02 1.21105565e-01 3.06139633e-01 - 8.62763808e-01 2.89789222e+00] -[9.57055016e-04 2.28222032e-03 8.35436401e-03 2.06734948e-02 - 5.63019289e-02 1.89486538e-01] +[[1.33568413e-02] + [3.25887984e-02] + [1.21105565e-01] + [3.06139633e-01] + [8.62763808e-01] + [2.89789222e+00]] +[[9.57055016e-04] + [2.28222032e-03] + [8.35436401e-03] + [2.06734948e-02] + [5.63019289e-02] + [1.89486538e-01]] domain=1 type=delayed-nu-fission matrix [[[0.00000000e+00 0.00000000e+00] [0.00000000e+00 0.00000000e+00]] From 3ee40ea37c290167a0f59061693b2c053f693e23 Mon Sep 17 00:00:00 2001 From: Yue JIN Date: Thu, 5 Nov 2020 10:18:26 +0800 Subject: [PATCH 57/79] Distribute depletable materials in all cell instances containing it. --- openmc/deplete/operator.py | 12 +++++++----- 1 file changed, 7 insertions(+), 5 deletions(-) diff --git a/openmc/deplete/operator.py b/openmc/deplete/operator.py index 1f99abe955..0e28b7ed33 100644 --- a/openmc/deplete/operator.py +++ b/openmc/deplete/operator.py @@ -371,15 +371,17 @@ class Operator(TransportOperator): [mat for mat in self.geometry.get_all_materials().values() if mat.depletable and mat.num_instances > 1]) + for mat in distribmats: + if mat.volume is None: + raise RuntimeError("Volume not specified for depletable " + "material with ID={}.".format(mat.id)) + mat.volume /= mat.num_instances + if distribmats: # Assign distribmats to cells for cell in self.geometry.get_all_material_cells().values(): - if cell.fill in distribmats and cell.num_instances > 1: + if cell.fill in distribmats: mat = cell.fill - if mat.volume is None: - raise RuntimeError("Volume not specified for depletable " - "material with ID={}.".format(mat.id)) - mat.volume /= mat.num_instances cell.fill = [mat.clone() for i in range(cell.num_instances)] From d276fb590d7afcd9b4d0f32c2dae81a0087ef6dd Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Mon, 9 Nov 2020 14:33:29 -0600 Subject: [PATCH 58/79] Avoid mocking many third-party packages when building documentation --- docs/requirements-rtd.txt | 6 ++++++ docs/source/conf.py | 11 +---------- 2 files changed, 7 insertions(+), 10 deletions(-) diff --git a/docs/requirements-rtd.txt b/docs/requirements-rtd.txt index 776bbc24d6..fd76dfffb9 100644 --- a/docs/requirements-rtd.txt +++ b/docs/requirements-rtd.txt @@ -3,3 +3,9 @@ jupyter sphinxcontrib-katex sphinxcontrib-svg2pdfconverter nbsphinx +numpy +scipy +h5py +pandas +uncertainties +matplotlib diff --git a/docs/source/conf.py b/docs/source/conf.py index 5ea2ec8ae9..dea3440a76 100644 --- a/docs/source/conf.py +++ b/docs/source/conf.py @@ -21,19 +21,10 @@ on_rtd = os.environ.get('READTHEDOCS', None) == 'True' from unittest.mock import MagicMock MOCK_MODULES = [ - 'numpy', 'numpy.polynomial', 'numpy.polynomial.polynomial', - 'numpy.ctypeslib', 'scipy', 'scipy.sparse', 'scipy.sparse.linalg', - 'scipy.interpolate', 'scipy.integrate', 'scipy.optimize', 'scipy.signal', - 'scipy.special', 'scipy.stats', 'scipy.spatial', 'h5py', 'pandas', - 'uncertainties', 'matplotlib', 'matplotlib.pyplot', 'openmoc', - 'openmc.data.reconstruct', 'openmc.checkvalue' + 'openmoc', 'openmc.data.reconstruct', ] sys.modules.update((mod_name, MagicMock()) for mod_name in MOCK_MODULES) -import numpy as np -np.ndarray = MagicMock -np.polynomial.Polynomial = MagicMock - # If extensions (or modules to document with autodoc) are in another directory, # add these directories to sys.path here. If the directory is relative to the From a9ebadaecc378953745a02a27e72dd4b301bd6ce Mon Sep 17 00:00:00 2001 From: agnelson Date: Mon, 9 Nov 2020 15:59:23 -0600 Subject: [PATCH 59/79] Fixing comments per the review by @paulromano --- openmc/mgxs/library.py | 18 +++++++++--------- openmc/mgxs/mgxs.py | 11 +++++------ 2 files changed, 14 insertions(+), 15 deletions(-) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 0d8373592b..5c70720334 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -946,10 +946,10 @@ class Library: apply_domain_chi : bool This parameter sets whether (True) or not (False) the domain-averaged values of chi, chi-prompt, and chi-delayed are to - be applied to each of the nuclidic fission energy spectra of a - domain. In effect, if this is True, then every nuclide in the + be applied to each of the nuclide-dependent fission energy spectra + of a domain. In effect, if this is True, then every nuclide in the domain receives the same flux-weighted Chi. This is useful for - downstream multigroup solvers that pre-compute a material-specific + downstream multigroup solvers that precompute a material-specific chi before the transport solve provides group-wise fluxes. Defaults to False. @@ -1242,10 +1242,10 @@ class Library: apply_domain_chi : bool This parameter sets whether (True) or not (False) the domain-averaged values of chi, chi-prompt, and chi-delayed are to - be applied to each of the nuclidic fission energy spectra of a - domain. In effect, if this is True, then every nuclide in the + be applied to each of the nuclide-dependent fission energy spectra + of a domain. In effect, if this is True, then every nuclide in the domain receives the same flux-weighted Chi. This is useful for - downstream multigroup solvers that pre-compute a material-specific + downstream multigroup solvers that precompute a material-specific chi before the transport solve provides group-wise fluxes. Defaults to False. @@ -1354,10 +1354,10 @@ class Library: apply_domain_chi : bool This parameter sets whether (True) or not (False) the domain-averaged values of chi, chi-prompt, and chi-delayed are to - be applied to each of the nuclidic fission energy spectra of a - domain. In effect, if this is True, then every nuclide in the + be applied to each of the nuclide-dependent fission energy spectra + of a domain. In effect, if this is True, then every nuclide in the domain receives the same flux-weighted Chi. This is useful for - downstream multigroup solvers that pre-compute a material-specific + downstream multigroup solvers that precompute a material-specific chi before the transport solve provides group-wise fluxes. Defaults to False. diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index ef6c3de1c6..0f1bf56a12 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -47,8 +47,8 @@ MGXS_TYPES = ( # support and test (like inelastic levels), remoev those from consideration _BAD_SCORES = ["(n,misc)", "(n,absorption)", "(n,total)", "fission"] _BAD_SCORES += [REACTION_NAME[mt] for mt in FISSION_MTS] -ARBITRARY_VECTOR_TYPES = [k for k in REACTION_MT.keys() if k not in _BAD_SCORES] -ARBITRARY_VECTOR_TYPES = tuple(ARBITRARY_VECTOR_TYPES) +ARBITRARY_VECTOR_TYPES = tuple(k for k in REACTION_MT.keys() + if k not in _BAD_SCORES) ARBITRARY_MATRIX_TYPES = [] for rxn in ARBITRARY_VECTOR_TYPES: # Preclude the fission channels from being treated as a matrix @@ -1237,12 +1237,11 @@ class MGXS: # Determine which flux to obtain # Step through in order of usefulness - tally = None for key in ['flux', 'flux (tracklength)', 'flux (analog)']: if key in self.tally_keys: tally = self.tallies[key] break - if tally is None: + else: msg = "MGXS of Type {} do not have an explicit weighting flux!" raise ValueError(msg.format(self.__name__)) @@ -4021,7 +4020,7 @@ class ArbitraryXS(MGXS): \sigma_X (r, E) \psi (r, E, \Omega)}{\int_{r \in V} dr \int_{4\pi} d\Omega \int_{E_g}^{E_{g-1}} dE \; \psi (r, E, \Omega)} - where :math:`_\sigma_X` is the requested reaction type of interest. + where :math:`\sigma_X` is the requested reaction type of interest. Parameters ---------- @@ -4152,7 +4151,7 @@ class ArbitraryMatrixXS(MatrixMGXS): g} \phi \rangle}{\langle \phi \rangle} \end{aligned} - where :math:`_\sigma_X` is the requested reaction type of interest. + where :math:`\sigma_X` is the requested reaction type of interest. Parameters ---------- From 4b2130712868401142ad08e948ce67b9fe13d1be Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 10 Nov 2020 14:09:44 -0600 Subject: [PATCH 60/79] Make sure is specified on a mesh --- src/mesh.cpp | 43 +++++++++++++++++++++---------------------- 1 file changed, 21 insertions(+), 22 deletions(-) diff --git a/src/mesh.cpp b/src/mesh.cpp index 53279cc57a..64d2c269ba 100644 --- a/src/mesh.cpp +++ b/src/mesh.cpp @@ -525,18 +525,21 @@ RegularMesh::RegularMesh(pugi::xml_node node) : StructuredMesh {node} { // Determine number of dimensions for mesh - if (check_for_node(node, "dimension")) { - shape_ = get_node_xarray(node, "dimension"); - int n = n_dimension_ = shape_.size(); - if (n != 1 && n != 2 && n != 3) { - fatal_error("Mesh must be one, two, or three dimensions."); - } + if (!check_for_node(node, "dimension")) { + fatal_error("Must specify on a regular mesh."); + } - // Check that dimensions are all greater than zero - if (xt::any(shape_ <= 0)) { - fatal_error("All entries on the element for a tally " - "mesh must be positive."); - } + + shape_ = get_node_xarray(node, "dimension"); + int n = n_dimension_ = shape_.size(); + if (n != 1 && n != 2 && n != 3) { + fatal_error("Mesh must be one, two, or three dimensions."); + } + + // Check that dimensions are all greater than zero + if (xt::any(shape_ <= 0)) { + fatal_error("All entries on the element for a tally " + "mesh must be positive."); } // Check for lower-left coordinates @@ -587,23 +590,19 @@ RegularMesh::RegularMesh(pugi::xml_node node) } // Set width - if (shape_.size() > 0) { - width_ = xt::eval((upper_right_ - lower_left_) / shape_); - } + width_ = xt::eval((upper_right_ - lower_left_) / shape_); } else { fatal_error("Must specify either and on a mesh."); } // Make sure lower_left and dimension match - if (shape_.size() > 0) { - if (shape_.size() != lower_left_.size()) { - fatal_error("Number of entries on must be the same " - "as the number of entries on ."); - } - - // Set volume fraction - volume_frac_ = 1.0/xt::prod(shape_)(); + if (shape_.size() != lower_left_.size()) { + fatal_error("Number of entries on must be the same " + "as the number of entries on ."); } + + // Set volume fraction + volume_frac_ = 1.0/xt::prod(shape_)(); } int RegularMesh::get_index_in_direction(double r, int i) const From d05bf7789db0d42f5240696e1141e6fd441afff9 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 10 Nov 2020 21:43:13 -0600 Subject: [PATCH 61/79] Move check for consistent shape/lower_left on regular mesh --- src/mesh.cpp | 12 ++++++------ 1 file changed, 6 insertions(+), 6 deletions(-) diff --git a/src/mesh.cpp b/src/mesh.cpp index 64d2c269ba..a5409f05a0 100644 --- a/src/mesh.cpp +++ b/src/mesh.cpp @@ -550,6 +550,12 @@ RegularMesh::RegularMesh(pugi::xml_node node) fatal_error("Must specify on a mesh."); } + // Make sure lower_left and dimension match + if (shape_.size() != lower_left_.size()) { + fatal_error("Number of entries on must be the same " + "as the number of entries on ."); + } + if (check_for_node(node, "width")) { // Make sure both upper-right or width were specified if (check_for_node(node, "upper_right")) { @@ -595,12 +601,6 @@ RegularMesh::RegularMesh(pugi::xml_node node) fatal_error("Must specify either and on a mesh."); } - // Make sure lower_left and dimension match - if (shape_.size() != lower_left_.size()) { - fatal_error("Number of entries on must be the same " - "as the number of entries on ."); - } - // Set volume fraction volume_frac_ = 1.0/xt::prod(shape_)(); } From a117694930b65214855789581e5b484c1591377b Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Wed, 11 Nov 2020 11:17:35 -0600 Subject: [PATCH 62/79] If some natural isos are missing when adding element, check '0' nuclide first --- openmc/element.py | 36 +++++++++++++++++------------------- 1 file changed, 17 insertions(+), 19 deletions(-) diff --git a/openmc/element.py b/openmc/element.py index 6a808df621..2eacaf867d 100644 --- a/openmc/element.py +++ b/openmc/element.py @@ -149,30 +149,28 @@ class Element(str): mutual_nuclides = sorted(list(mutual_nuclides)) absent_nuclides = sorted(list(absent_nuclides)) - # If all natural nuclides are present in the library, - # expand element using all natural nuclides + # If all naturally ocurring isotopes are present in the library, + # add them based on their abundance if len(absent_nuclides) == 0: for nuclide in mutual_nuclides: abundances[nuclide] = NATURAL_ABUNDANCE[nuclide] - # If no natural elements are present in the library, check if the - # 0 nuclide is present. If so, set the abundance to 1 for this - # nuclide. Else, raise an error. - elif len(mutual_nuclides) == 0: - nuclide_0 = self + '0' - if nuclide_0 in library_nuclides: - abundances[nuclide_0] = 1.0 - else: - msg = 'Unable to expand element {0} because the cross '\ - 'section library provided does not contain any of '\ - 'the natural isotopes for that element.'\ - .format(self) - raise ValueError(msg) + # If some naturally occurring isotopes are not present in the + # library, check if the "natural" nuclide (e.g., C0) is present. If + # so, set the abundance to 1 for this nuclide. + elif (self + '0') in library_nuclides: + abundances[self + '0'] = 1.0 - # If some, but not all, natural nuclides are in the library, add - # the mutual nuclides. For the absent nuclides, add them based on - # our knowledge of the common cross section libraries - # (ENDF, JEFF, and JENDL) + elif len(mutual_nuclides) == 0: + msg = ('Unable to expand element {} because the cross ' + 'section library provided does not contain any of ' + 'the natural isotopes for that element.' + .format(self)) + raise ValueError(msg) + + # If some naturally occurring isotopes are in the library, add them. + # For the absent nuclides, add them based on our knowledge of the + # common cross section libraries (ENDF, JEFF, and JENDL) else: # Add the mutual isotopes for nuclide in mutual_nuclides: From 654d27a3e56f06e7abf07125b185bd1dd2265008 Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Thu, 12 Nov 2020 12:43:40 -0600 Subject: [PATCH 63/79] Typo fix in RectangularParallelepiped.__pos__ method. --- openmc/model/surface_composite.py | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/openmc/model/surface_composite.py b/openmc/model/surface_composite.py index 9f9cd39c60..09a3c0170f 100644 --- a/openmc/model/surface_composite.py +++ b/openmc/model/surface_composite.py @@ -163,7 +163,7 @@ class RectangularParallelepiped(CompositeSurface): return +self.xmin & -self.xmax & +self.ymin & -self.ymax & +self.zmin & -self.zmax def __pos__(self): - return -self.xmin | +self.ymax | -self.ymin | +self.ymax | -self.zmin | +self.zmax + return -self.xmin | +self.xmax | -self.ymin | +self.ymax | -self.zmin | +self.zmax class XConeOneSided(CompositeSurface): From e87e5ba3dcd2ff8f965dc1c2bea39e45e07e9701 Mon Sep 17 00:00:00 2001 From: Shikhar Kumar Date: Tue, 24 Nov 2020 22:56:31 -0500 Subject: [PATCH 64/79] Move CMFD reweight to cpp, minor discrepancies in regression tests --- include/openmc/capi.h | 13 ++- openmc/cmfd.py | 161 +++--------------------------- openmc/lib/core.py | 7 +- src/cmfd_solver.cpp | 225 +++++++++++++++++++++++++++++++++++++++--- 4 files changed, 240 insertions(+), 166 deletions(-) diff --git a/include/openmc/capi.h b/include/openmc/capi.h index 6d82929d17..19f31479a2 100644 --- a/include/openmc/capi.h +++ b/include/openmc/capi.h @@ -131,6 +131,18 @@ extern "C" { int openmc_zernike_filter_set_params(int32_t index, const double* x, const double* y, const double* r); + //! Sets the mesh and energy grid for CMFD reweight + //! \param[in] id of CMFD Mesh Tally + //! \param[in] CMFD normalization factor + //! \param[in] CMFD weight clipping factor + extern "C" void openmc_initialize_mesh_egrid(const int meshtally_id, const int* cmfd_indices, + const double norm); + + //! Sets the mesh and energy grid for CMFD reweight + //! \param[in] whether or not to run CMFD feedback + //! \param[in] computed CMFD source + extern "C" void openmc_cmfd_reweight(const bool feedback, const double* cmfd_src); + //! Sets the fixed variables that are used for CMFD linear solver //! \param[in] CSR format index pointer array of loss matrix //! \param[in] length of indptr @@ -143,7 +155,6 @@ extern "C" { extern "C" void openmc_initialize_linsolver(const int* indptr, int len_indptr, const int* indices, int n_elements, int dim, double spectral, - const int* cmfd_indices, const int* map, bool use_all_threads); //! Runs a Gauss Seidel linear solver to solve CMFD matrix equations diff --git a/openmc/cmfd.py b/openmc/cmfd.py index 78901b03b9..a99b606193 100644 --- a/openmc/cmfd.py +++ b/openmc/cmfd.py @@ -366,8 +366,6 @@ class CMFDRun: self._current = None self._cmfd_src = None self._openmc_src = None - self._sourcecounts = None - self._weightfactors = None self._entropy = [] self._balance = [] self._src_cmp = [] @@ -914,7 +912,7 @@ class CMFDRun: args = temp_loss.indptr, len(temp_loss.indptr), \ temp_loss.indices, len(temp_loss.indices), n, \ - self._spectral, self._indices, coremap, self._use_all_threads + self._spectral, coremap, self._use_all_threads return openmc.lib._dll.openmc_initialize_linsolver(*args) def _write_cmfd_output(self): @@ -1171,8 +1169,12 @@ class CMFDRun: # Calculate fission source self._calc_fission_source() - # Calculate weight factors - self._cmfd_reweight() + # Calculate weight factors through C++ and manipulate CMFD + # source into a 1-D vector that matches C++ array ordering + src_flipped = np.flip(self._cmfd_src, axis=3) + src_swapped = np.swapaxes(src_flipped, 0, 2) + args = self._feedback, src_swapped.flatten() + openmc.lib._dll.openmc_cmfd_reweight(*args) # Stop CMFD timer if openmc.lib.master(): @@ -1390,151 +1392,6 @@ class CMFDRun: self._src_cmp.append(np.sqrt(1.0 / self._norm * np.sum((self._cmfd_src - self._openmc_src)**2))) - def _cmfd_reweight(self): - """Performs weighting of particles in source bank""" - # Get spatial dimensions and energy groups - nx, ny, nz, ng = self._indices - - # Count bank site in mesh and reverse due to egrid structured - outside = self._count_bank_sites() - - # Check and raise error if source sites exist outside of CMFD mesh - if openmc.lib.master() and outside: - raise OpenMCError('Source sites outside of the CMFD mesh') - - # Have master compute weight factors, ignore any zeros in - # sourcecounts or cmfd_src - if openmc.lib.master(): - # Compute normalization factor - norm = np.sum(self._sourcecounts) / np.sum(self._cmfd_src) - - # Define target reshape dimensions for sourcecounts. This - # defines how self._sourcecounts is ordered by dimension - target_shape = [nz, ny, nx, ng] - - # Reshape sourcecounts to target shape. Swap x and z axes so - # that the shape is now [nx, ny, nz, ng] - sourcecounts = np.swapaxes( - self._sourcecounts.reshape(target_shape), 0, 2) - - # Flip index of energy dimension - sourcecounts = np.flip(sourcecounts, axis=3) - - # Compute weight factors - div_condition = np.logical_and(sourcecounts > 0, - self._cmfd_src > 0) - self._weightfactors = (np.divide(self._cmfd_src * norm, - sourcecounts, where=div_condition, - out=np.ones_like(self._cmfd_src), - dtype=np.float32)) - - if not self._feedback: - return - - # Broadcast weight factors to all procs - if have_mpi: - self._weightfactors = self._intracomm.bcast( - self._weightfactors) - - m = openmc.lib.meshes[self._mesh_id] - energy = self._egrid - ng = self._indices[3] - - # Get locations and energies of all particles in source bank - source_xyz = openmc.lib.source_bank()['r'] - source_energies = openmc.lib.source_bank()['E'] - - # Convert xyz location to the CMFD mesh index - mesh_ijk = np.floor((source_xyz - m.lower_left)/m.width).astype(int) - - # Determine which energy bin each particle's energy belongs to - # Separate into cases bases on where source energies lies on egrid - energy_bins = np.zeros(len(source_energies), dtype=int) - idx = np.where(source_energies < energy[0]) - energy_bins[idx] = ng - 1 - idx = np.where(source_energies > energy[-1]) - energy_bins[idx] = 0 - idx = np.where((source_energies >= energy[0]) & - (source_energies <= energy[-1])) - energy_bins[idx] = ng - np.digitize(source_energies[idx], energy) - - # Determine weight factor of each particle based on its mesh index - # and energy bin and updates its weight - openmc.lib.source_bank()['wgt'] *= self._weightfactors[ - mesh_ijk[:,0], mesh_ijk[:,1], mesh_ijk[:,2], energy_bins] - - if openmc.lib.master() and np.any(source_energies < energy[0]): - print(' WARNING: Source point below energy grid') - sys.stdout.flush() - if openmc.lib.master() and np.any(source_energies > energy[-1]): - print(' WARNING: Source point above energy grid') - sys.stdout.flush() - - def _count_bank_sites(self): - """Determines the number of fission bank sites in each cell of a given - mesh and energy group structure. - Returns - ------- - bool - Wheter any source sites outside of CMFD mesh were found - - """ - # Initialize variables - m = openmc.lib.meshes[self._mesh_id] - bank = openmc.lib.source_bank() - energy = self._egrid - sites_outside = np.zeros(1, dtype=bool) - nxnynz = np.prod(self._indices[0:3]) - ng = self._indices[3] - - outside = np.zeros(1, dtype=bool) - self._sourcecounts = np.zeros((nxnynz, ng)) - count = np.zeros(self._sourcecounts.shape) - - # Get location and energy of each particle in source bank - source_xyz = openmc.lib.source_bank()['r'] - source_energies = openmc.lib.source_bank()['E'] - - # Convert xyz location to mesh index and ravel index to scalar - mesh_locations = np.floor((source_xyz - m.lower_left) / m.width) - mesh_bins = mesh_locations[:,2] * m.dimension[1] * m.dimension[0] + \ - mesh_locations[:,1] * m.dimension[0] + mesh_locations[:,0] - - # Check if any source locations lie outside of defined CMFD mesh - if np.any(mesh_bins < 0) or np.any(mesh_bins >= np.prod(m.dimension)): - outside[0] = True - - # Determine which energy bin each particle's energy belongs to - # Separate into cases bases on where source energies lies on egrid - energy_bins = np.zeros(len(source_energies), dtype=int) - idx = np.where(source_energies < energy[0]) - energy_bins[idx] = 0 - idx = np.where(source_energies > energy[-1]) - energy_bins[idx] = ng - 1 - idx = np.where((source_energies >= energy[0]) & - (source_energies <= energy[-1])) - energy_bins[idx] = np.digitize(source_energies[idx], energy) - 1 - - # Determine all unique combinations of mesh bin and energy bin, and - # count number of particles that belong to these combinations - idx, counts = np.unique(np.array([mesh_bins, energy_bins]), axis=1, - return_counts=True) - - # Store counts to appropriate mesh-energy combination - count[idx[0].astype(int), idx[1].astype(int)] = counts - - if have_mpi: - # Collect values of count from all processors - self._intracomm.Reduce(count, self._sourcecounts, MPI.SUM) - # Check if there were sites outside the mesh for any processor - self._intracomm.Reduce(outside, sites_outside, MPI.LOR) - # Deal with case if MPI not defined (only one proc) - else: - sites_outside = outside - self._sourcecounts = count - - return sites_outside[0] - def _build_loss_matrix(self, adjoint): # Extract spatial and energy indices and define matrix dimension ng = self._indices[3] @@ -3045,3 +2902,7 @@ class CMFDRun: # Set all tallies to be active from beginning cmfd_tally.active = True + + # Initialize CMFD mesh and energy grid in C++ for CMFD reweight + args = self._tally_ids[0], self._indices, self._norm + openmc.lib._dll.openmc_initialize_mesh_egrid(*args) diff --git a/openmc/lib/core.py b/openmc/lib/core.py index 3fe75dccf6..f24f5d7dc6 100644 --- a/openmc/lib/core.py +++ b/openmc/lib/core.py @@ -31,6 +31,8 @@ _array_1d_dble = np.ctypeslib.ndpointer(dtype=np.double, ndim=1, _dll.openmc_calculate_volumes.restype = c_int _dll.openmc_calculate_volumes.errcheck = _error_handler +_dll.openmc_cmfd_reweight.argtypes = c_bool, _array_1d_dble +_dll.openmc_cmfd_reweight.restype = None _dll.openmc_finalize.restype = c_int _dll.openmc_finalize.errcheck = _error_handler _dll.openmc_find_cell.argtypes = [POINTER(c_double*3), POINTER(c_int32), @@ -45,8 +47,11 @@ _dll.openmc_init.errcheck = _error_handler _dll.openmc_get_keff.argtypes = [POINTER(c_double*2)] _dll.openmc_get_keff.restype = c_int _dll.openmc_get_keff.errcheck = _error_handler +_init_mesh_egrid_args = [c_int, _array_1d_int, c_double] +_dll.openmc_initialize_mesh_egrid.argtypes = _init_mesh_egrid_args +_dll.openmc_initialize_mesh_egrid.restype = None _init_linsolver_argtypes = [_array_1d_int, c_int, _array_1d_int, c_int, c_int, - c_double, _array_1d_int, _array_1d_int, c_bool] + c_double, _array_1d_int, c_bool] _dll.openmc_initialize_linsolver.argtypes = _init_linsolver_argtypes _dll.openmc_initialize_linsolver.restype = None _dll.openmc_is_statepoint_batch.restype = c_bool diff --git a/src/cmfd_solver.cpp b/src/cmfd_solver.cpp index 8406c98995..a3f354c17d 100644 --- a/src/cmfd_solver.cpp +++ b/src/cmfd_solver.cpp @@ -8,9 +8,15 @@ #endif #include "xtensor/xtensor.hpp" +#include "openmc/bank.h" #include "openmc/error.h" #include "openmc/constants.h" #include "openmc/capi.h" +#include "openmc/mesh.h" +#include "openmc/message_passing.h" +#include "openmc/tallies/filter_energy.h" +#include "openmc/tallies/filter_mesh.h" +#include "openmc/tallies/tally.h" namespace openmc { @@ -34,8 +40,203 @@ xt::xtensor indexmap; int use_all_threads; +RegularMesh* mesh; + +std::vector egrid; + +double norm; + } // namespace cmfd +//============================================================================== +// GET_CMFD_ENERGY_BIN returns the energy bin for a source site energy +//============================================================================== + +int get_cmfd_energy_bin(const double E) +{ + // Check if energy is out of grid bounds + if (E < cmfd::egrid[0]) { + // throw warning message + warning("Detected source point below energy grid"); + return 0; + } else if (E >= cmfd::egrid[cmfd::ng]) { + // throw warning message + warning("Detected source point above energy grid"); + return cmfd::ng - 1; + } else { + // Iterate through energy grid to find matching bin + for (int g = 0; g < cmfd::ng; g++) { + if (E >= cmfd::egrid[g] && E < cmfd::egrid[g+1]) { + return g; + } + } + } + // Return -1 by default + return -1; +} + +//============================================================================== +// COUNT_BANK_SITES bins fission sites according to CMFD mesh and energy +//============================================================================== + +xt::xtensor count_bank_sites(xt::xtensor& bins, bool* outside) +{ + // Determine shape of array for counts + std::size_t cnt_size = cmfd::nx * cmfd::ny * cmfd::nz * cmfd::ng; + std::vector cnt_shape = {cnt_size}; + + // Create array of zeros + xt::xarray cnt {cnt_shape, 0.0}; + bool outside_ = false; + + auto bank_size = simulation::source_bank.size(); + for (int i = 0; i < bank_size; i++) { + const auto& site = simulation::source_bank[i]; + + // determine scoring bin for CMFD mesh + int mesh_bin = cmfd::mesh->get_bin(site.r); + + // if outside mesh, skip particle + if (mesh_bin < 0) { + outside_ = true; + continue; + } + + // determine scoring bin for CMFD energy + int energy_bin = get_cmfd_energy_bin(site.E); + + // add to appropriate bin + cnt(mesh_bin*cmfd::ng+energy_bin) += site.wgt; + + // store bin index which is used again when updating weights + bins[i] = mesh_bin*cmfd::ng+energy_bin; + } + + // Create copy of count data. Since ownership will be acquired by xtensor, + // std::allocator must be used to avoid Valgrind mismatched free() / delete + // warnings. + int total = cnt.size(); + double* cnt_reduced = std::allocator{}.allocate(total); + +#ifdef OPENMC_MPI + // collect values from all processors + MPI_Reduce(cnt.data(), cnt_reduced, total, MPI_DOUBLE, MPI_SUM, 0, + mpi::intracomm); + + // Check if there were sites outside the mesh for any processor + MPI_Reduce(&outside_, outside, 1, MPI_C_BOOL, MPI_LOR, 0, mpi::intracomm); + +#else + std::copy(cnt.data(), cnt.data() + total, cnt_reduced); + *outside = outside_; +#endif + + // Adapt reduced values in array back into an xarray + auto arr = xt::adapt(cnt_reduced, total, xt::acquire_ownership(), cnt_shape); + xt::xarray counts = arr; + + return counts; +} + +//============================================================================== +// OPENMC_CMFD_REWEIGHT performs reweighting of particles in source bank +//============================================================================== + +extern "C" +void openmc_cmfd_reweight(const bool feedback, const double* cmfd_src) +{ + // Get size of source bank and cmfd_src + auto bank_size = simulation::source_bank.size(); + std::size_t src_size = cmfd::nx * cmfd::ny * cmfd::nz * cmfd::ng; + + // count bank sites for CMFD mesh, store bins in bank_bins for reweighting + xt::xtensor bank_bins({bank_size}, 0); + bool sites_outside; + xt::xtensor sourcecounts = count_bank_sites(bank_bins, + &sites_outside); + + // Compute CMFD weightfactors + xt::xtensor weightfactors = xt::xtensor({src_size}, 1.); + if (mpi::master) { + if (sites_outside) { + fatal_error("Source sites outside of the CMFD mesh"); + } + + double norm = xt::sum(sourcecounts)()/cmfd::norm; + for (int i = 0; i < src_size; i++) { + if (sourcecounts[i] > 0 && cmfd_src[i] > 0) { + weightfactors[i] = cmfd_src[i] * norm / sourcecounts[i]; + } + } + } + + if (!feedback) { + return; + } + +#ifdef OPENMC_MPI + // Send weightfactors to all processors + MPI_Bcast(weightfactors.data(), src_size, MPI_DOUBLE, 0, mpi::intracomm); +#endif + + // Iterate through fission bank and update particle weights + for (int64_t i = 0; i < bank_size; i++) { + auto& site = simulation::source_bank[i]; + site.wgt *= weightfactors(bank_bins(i)); + } +} + +//============================================================================== +// OPENMC_INITIALIZE_MESH_EGRID sets the mesh and energy grid for CMFD reweight +//============================================================================== + +extern "C" +void openmc_initialize_mesh_egrid(const int meshtally_id, const int* cmfd_indices, + const double norm) +{ + // Make sure all CMFD memory is freed + free_memory_cmfd(); + + // Set CMFD indices + cmfd::nx = cmfd_indices[0]; + cmfd::ny = cmfd_indices[1]; + cmfd::nz = cmfd_indices[2]; + cmfd::ng = cmfd_indices[3]; + + // Set CMFD reweight properties + cmfd::norm = norm; + + // Find index corresponding to tally id + int32_t tally_index; + openmc_get_tally_index(meshtally_id, &tally_index); + + // Get filters assocaited with tally + auto tally_filters = model::tallies[tally_index]->filters(); + + // Get mesh filter index + auto meshfilter_index = tally_filters[0]; + + // Store energy filter index if defined, otherwise set to -1 + auto energy_index = (tally_filters.size() == 2) ? tally_filters[1] : -1; + + // Get mesh index from mesh filter index + int32_t mesh_index; + openmc_mesh_filter_get_mesh(meshfilter_index, &mesh_index); + + // Get mesh from mesh index + cmfd::mesh = get_regular_mesh(mesh_index); + + // Get energy bins from energy index, otherwise use default + if (energy_index != -1) + { + auto efilt_base = model::tally_filters[energy_index].get(); + auto* efilt = dynamic_cast(efilt_base); + cmfd::egrid = efilt->bins(); + } else { + cmfd::egrid = {0.0, INFTY}; + } +} + //============================================================================== // MATRIX_TO_INDICES converts a matrix index to spatial and group // indices @@ -309,12 +510,9 @@ int cmfd_linsolver_ng(const double* A_data, const double* b, double* x, extern "C" void openmc_initialize_linsolver(const int* indptr, int len_indptr, const int* indices, int n_elements, int dim, - double spectral, const int* cmfd_indices, - const int* map, bool use_all_threads) + double spectral, const int* map, + bool use_all_threads) { - // Make sure vectors are empty - free_memory_cmfd(); - // Store elements of indptr for (int i = 0; i < len_indptr; i++) cmfd::indptr.push_back(indptr[i]); @@ -327,15 +525,8 @@ void openmc_initialize_linsolver(const int* indptr, int len_indptr, cmfd::dim = dim; cmfd::spectral = spectral; - // Set number of groups - cmfd::ng = cmfd_indices[3]; - - // Set problem dimensions and indexmap if 1 or 2 group problem + // Set indexmap if 1 or 2 group problem if (cmfd::ng == 1 || cmfd::ng == 2) { - cmfd::nx = cmfd_indices[0]; - cmfd::ny = cmfd_indices[1]; - cmfd::nz = cmfd_indices[2]; - // Resize indexmap and set its elements cmfd::indexmap.resize({static_cast(dim), 3}); set_indexmap(map); @@ -366,10 +557,16 @@ int openmc_run_linsolver(const double* A_data, const double* b, double* x, void free_memory_cmfd() { + // Clear std::vectors cmfd::indptr.clear(); cmfd::indices.clear(); - // Resize indexmap to be an empty array + cmfd::egrid.clear(); + + // Resize xtensors to be empty cmfd::indexmap.resize({0}); + + // Set pointers to null + cmfd::mesh = nullptr; } } // namespace openmc From 2931ebef9e77991e0cf1a19b174d87c5e81c3493 Mon Sep 17 00:00:00 2001 From: Shikhar Kumar Date: Tue, 24 Nov 2020 23:44:38 -0500 Subject: [PATCH 65/79] Confirm precision differences between Python and C++ --- .../cmfd_feed/results_true.dat | 14 ++++---- .../cmfd_feed_2g/results_true.dat | 36 +++++++++---------- .../results_true.dat | 28 +++++++-------- .../cmfd_feed_ng/results_true.dat | 16 ++++----- .../cmfd_feed_ref_d/results_true.dat | 24 ++++++------- .../cmfd_feed_rolling_window/results_true.dat | 36 +++++++++---------- .../cmfd_restart/results_true.dat | 14 ++++---- 7 files changed, 84 insertions(+), 84 deletions(-) diff --git a/tests/regression_tests/cmfd_feed/results_true.dat b/tests/regression_tests/cmfd_feed/results_true.dat index ea25c88565..85498af19c 100644 --- a/tests/regression_tests/cmfd_feed/results_true.dat +++ b/tests/regression_tests/cmfd_feed/results_true.dat @@ -16,7 +16,7 @@ tally 1: 3.347757E+01 1.124264E+02 2.931336E+01 -8.607238E+01 +8.607239E+01 2.182947E+01 4.789565E+01 1.147668E+01 @@ -378,7 +378,7 @@ tally 5: 5.253064E+00 1.396224E+00 2.996497E+01 -4.508839E+01 +4.508840E+01 3.818076E+00 7.509442E-01 1.574994E+01 @@ -461,17 +461,17 @@ cmfd dominance ratio cmfd openmc source comparison 6.959834E-03 5.655657E-03 -3.886186E-03 +3.886185E-03 4.035116E-03 3.043277E-03 -5.455474E-03 -4.515310E-03 +5.455475E-03 +4.515311E-03 2.439840E-03 2.114032E-03 -2.673131E-03 +2.673132E-03 2.431749E-03 4.330928E-03 -3.404646E-03 +3.404647E-03 3.680298E-03 3.309620E-03 3.705541E-03 diff --git a/tests/regression_tests/cmfd_feed_2g/results_true.dat b/tests/regression_tests/cmfd_feed_2g/results_true.dat index d928b33e8a..4b3dc3c960 100644 --- a/tests/regression_tests/cmfd_feed_2g/results_true.dat +++ b/tests/regression_tests/cmfd_feed_2g/results_true.dat @@ -80,7 +80,7 @@ tally 3: 0.000000E+00 0.000000E+00 1.796382E-02 -3.190855E-05 +3.190854E-05 4.343238E+00 9.514040E-01 3.504683E+00 @@ -90,7 +90,7 @@ tally 3: 9.818871E+01 4.822799E+02 8.401346E-01 -3.664038E-02 +3.664037E-02 6.130607E+01 1.882837E+02 0.000000E+00 @@ -212,7 +212,7 @@ tally 4: 0.000000E+00 0.000000E+00 0.000000E+00 -9.042232E+00 +9.042233E+00 4.097018E+00 3.711597E+01 6.891834E+01 @@ -256,7 +256,7 @@ tally 4: 4.161211E+00 3.715168E+01 6.904544E+01 -9.042232E+00 +9.042233E+00 4.097018E+00 3.711597E+01 6.891834E+01 @@ -314,7 +314,7 @@ tally 5: 1.007512E+02 5.078162E+02 1.403236E+01 -9.884346E+00 +9.884347E+00 4.598486E+01 1.058070E+02 6.194677E+01 @@ -377,13 +377,13 @@ cmfd balance 4.16856E-04 6.38469E-04 3.92822E-04 -3.78984E-04 +3.78983E-04 2.68486E-04 4.84991E-04 1.08402E-03 -1.09177E-03 +1.09178E-03 5.45977E-04 -4.45554E-04 +4.45555E-04 4.01147E-04 3.71025E-04 3.57715E-04 @@ -408,21 +408,21 @@ cmfd dominance ratio 5.996E-03 cmfd openmc source comparison 1.931386E-05 -2.839161E-05 -1.407963E-05 -6.718156E-06 -9.164199E-06 -1.382540E-05 +2.839162E-05 +1.407962E-05 +6.718148E-06 +9.164193E-06 +1.382539E-05 2.871606E-05 4.192300E-05 -5.327515E-05 +5.327516E-05 6.566500E-05 -6.655540E-05 +6.655541E-05 6.034977E-05 6.004677E-05 -5.711622E-05 -6.271263E-05 -6.425362E-05 +5.711623E-05 +6.271264E-05 +6.425363E-05 cmfd source 2.510278E-01 2.480592E-01 diff --git a/tests/regression_tests/cmfd_feed_expanding_window/results_true.dat b/tests/regression_tests/cmfd_feed_expanding_window/results_true.dat index 897f9e9a88..8253d82c33 100644 --- a/tests/regression_tests/cmfd_feed_expanding_window/results_true.dat +++ b/tests/regression_tests/cmfd_feed_expanding_window/results_true.dat @@ -37,7 +37,7 @@ tally 2: 3.708857E+00 1.375562E+01 2.698010E+00 -7.279259E+00 +7.279260E+00 4.233192E+00 1.791991E+01 3.023990E+00 @@ -51,11 +51,11 @@ tally 2: 2.497751E+00 6.238760E+00 2.974675E+00 -8.848691E+00 +8.848690E+00 2.121163E+00 4.499332E+00 2.329248E+00 -5.425398E+00 +5.425397E+00 1.658233E+00 2.749736E+00 1.158552E+00 @@ -109,7 +109,7 @@ tally 4: 0.000000E+00 0.000000E+00 1.420707E-01 -2.018410E-02 +2.018409E-02 2.633150E-01 6.933479E-02 0.000000E+00 @@ -131,7 +131,7 @@ tally 4: 2.633150E-01 6.933479E-02 1.420707E-01 -2.018410E-02 +2.018409E-02 2.628613E-01 6.909608E-02 3.590382E-01 @@ -229,7 +229,7 @@ tally 4: 4.909661E-01 2.410477E-01 5.152690E-01 -2.655022E-01 +2.655021E-01 4.788649E-01 2.293116E-01 0.000000E+00 @@ -251,7 +251,7 @@ tally 4: 4.788649E-01 2.293116E-01 5.152690E-01 -2.655022E-01 +2.655021E-01 4.266876E-01 1.820623E-01 3.401342E-01 @@ -277,7 +277,7 @@ tally 4: 4.266876E-01 1.820623E-01 3.724186E-01 -1.386957E-01 +1.386956E-01 2.560013E-01 6.553669E-02 0.000000E+00 @@ -299,7 +299,7 @@ tally 4: 2.560013E-01 6.553669E-02 3.724186E-01 -1.386957E-01 +1.386956E-01 2.892134E-01 8.364439E-02 1.556176E-01 @@ -441,13 +441,13 @@ cmfd dominance ratio cmfd openmc source comparison 7.459013E-03 5.012869E-03 -1.770224E-03 -5.242540E-03 -3.888027E-03 +1.770225E-03 +5.242539E-03 +3.888028E-03 6.653433E-03 8.839928E-03 -5.456904E-03 -5.668412E-03 +5.456903E-03 +5.668411E-03 4.016377E-03 4.179381E-03 cmfd source diff --git a/tests/regression_tests/cmfd_feed_ng/results_true.dat b/tests/regression_tests/cmfd_feed_ng/results_true.dat index d9660f7bb5..7074114598 100644 --- a/tests/regression_tests/cmfd_feed_ng/results_true.dat +++ b/tests/regression_tests/cmfd_feed_ng/results_true.dat @@ -572,7 +572,7 @@ cmfd entropy 1.999693E+00 cmfd balance 8.98944E-04 -4.45874E-04 +4.45875E-04 2.18562E-04 2.83412E-04 3.60924E-04 @@ -599,13 +599,13 @@ cmfd openmc source comparison 2.585546E-05 2.217204E-05 2.121913E-05 -9.253928E-06 -2.940947E-05 -3.083596E-05 -2.547491E-05 -2.602691E-05 -2.561169E-05 -2.816825E-05 +9.253920E-06 +2.940945E-05 +3.083595E-05 +2.547490E-05 +2.602689E-05 +2.561168E-05 +2.816824E-05 cmfd source 2.417661E-01 2.547768E-01 diff --git a/tests/regression_tests/cmfd_feed_ref_d/results_true.dat b/tests/regression_tests/cmfd_feed_ref_d/results_true.dat index b1f14ac58f..2f0d4713cd 100644 --- a/tests/regression_tests/cmfd_feed_ref_d/results_true.dat +++ b/tests/regression_tests/cmfd_feed_ref_d/results_true.dat @@ -1,7 +1,7 @@ k-combined: 1.165408E+00 1.127320E-02 tally 1: -1.141008E+01 +1.141009E+01 1.305436E+01 2.074878E+01 4.311543E+01 @@ -29,7 +29,7 @@ tally 2: 1.991651E+00 3.966673E+00 1.411802E+00 -1.993185E+00 +1.993186E+00 2.978294E+00 8.870233E+00 2.130084E+00 @@ -63,7 +63,7 @@ tally 2: 8.282626E-01 6.860190E-01 tally 3: -7.459524E-01 +7.459525E-01 5.564451E-01 4.877161E-02 2.378670E-03 @@ -345,10 +345,10 @@ tally 4: 0.000000E+00 0.000000E+00 tally 5: -7.459524E-01 +7.459525E-01 5.564451E-01 1.149859E-01 -1.322176E-02 +1.322177E-02 1.356729E+00 1.840713E+00 1.801152E-01 @@ -362,7 +362,7 @@ tally 5: 3.360312E-01 1.129170E-01 2.909427E+00 -8.464764E+00 +8.464765E+00 4.095398E-01 1.677229E-01 2.805095E+00 @@ -442,13 +442,13 @@ cmfd openmc source comparison 7.433111E-03 5.006211E-03 1.766072E-03 -5.184425E-03 -3.864321E-03 -6.617152E-03 +5.184426E-03 +3.864323E-03 +6.617153E-03 8.841210E-03 -5.454747E-03 -5.652690E-03 -4.006767E-03 +5.454745E-03 +5.652688E-03 +4.006766E-03 4.167617E-03 cmfd source 4.116746E-02 diff --git a/tests/regression_tests/cmfd_feed_rolling_window/results_true.dat b/tests/regression_tests/cmfd_feed_rolling_window/results_true.dat index 0974fcb8be..5d3ea4ec9d 100644 --- a/tests/regression_tests/cmfd_feed_rolling_window/results_true.dat +++ b/tests/regression_tests/cmfd_feed_rolling_window/results_true.dat @@ -31,7 +31,7 @@ tally 2: 1.324803E+00 1.755104E+00 2.585263E+00 -6.683587E+00 +6.683586E+00 1.840969E+00 3.389167E+00 3.737263E+00 @@ -41,7 +41,7 @@ tally 2: 3.989056E+00 1.591257E+01 2.843382E+00 -8.084820E+00 +8.084819E+00 3.951710E+00 1.561601E+01 2.838216E+00 @@ -54,7 +54,7 @@ tally 2: 1.050543E+01 2.315684E+00 5.362392E+00 -2.459493E+00 +2.459494E+00 6.049108E+00 1.734344E+00 3.007949E+00 @@ -72,7 +72,7 @@ tally 3: 7.284456E-02 5.306329E-03 1.779821E+00 -3.167762E+00 +3.167761E+00 1.110012E-01 1.232127E-02 2.586020E+00 @@ -92,7 +92,7 @@ tally 3: 1.503142E-01 2.259435E-02 2.233122E+00 -4.986832E+00 +4.986833E+00 1.456891E-01 2.122532E-02 1.682929E+00 @@ -301,7 +301,7 @@ tally 4: 4.201532E-01 1.765287E-01 2.898817E-01 -8.403142E-02 +8.403143E-02 1.509185E-01 2.277639E-02 0.000000E+00 @@ -323,7 +323,7 @@ tally 4: 1.509185E-01 2.277639E-02 2.898817E-01 -8.403142E-02 +8.403143E-02 1.482175E-01 2.196844E-02 0.000000E+00 @@ -354,7 +354,7 @@ tally 5: 1.458271E-01 2.126554E-02 1.779821E+00 -3.167762E+00 +3.167761E+00 2.705917E-01 7.321987E-02 2.584069E+00 @@ -374,9 +374,9 @@ tally 5: 3.296244E-01 1.086523E-01 2.233122E+00 -4.986832E+00 +4.986833E+00 3.106254E-01 -9.648813E-02 +9.648814E-02 1.682929E+00 2.832250E+00 2.709632E-01 @@ -440,16 +440,16 @@ cmfd dominance ratio 5.321E-01 cmfd openmc source comparison 7.693485E-03 -4.158805E-03 +4.158806E-03 2.962505E-03 -4.415044E-03 -2.304495E-03 -7.921580E-03 -8.609203E-03 -8.945198E-03 -8.054204E-03 +4.415043E-03 +2.304496E-03 +7.921579E-03 +8.609204E-03 +8.945200E-03 +8.054206E-03 1.164189E-02 -5.945645E-03 +5.945644E-03 cmfd source 4.077779E-02 6.659143E-02 diff --git a/tests/regression_tests/cmfd_restart/results_true.dat b/tests/regression_tests/cmfd_restart/results_true.dat index ea25c88565..85498af19c 100644 --- a/tests/regression_tests/cmfd_restart/results_true.dat +++ b/tests/regression_tests/cmfd_restart/results_true.dat @@ -16,7 +16,7 @@ tally 1: 3.347757E+01 1.124264E+02 2.931336E+01 -8.607238E+01 +8.607239E+01 2.182947E+01 4.789565E+01 1.147668E+01 @@ -378,7 +378,7 @@ tally 5: 5.253064E+00 1.396224E+00 2.996497E+01 -4.508839E+01 +4.508840E+01 3.818076E+00 7.509442E-01 1.574994E+01 @@ -461,17 +461,17 @@ cmfd dominance ratio cmfd openmc source comparison 6.959834E-03 5.655657E-03 -3.886186E-03 +3.886185E-03 4.035116E-03 3.043277E-03 -5.455474E-03 -4.515310E-03 +5.455475E-03 +4.515311E-03 2.439840E-03 2.114032E-03 -2.673131E-03 +2.673132E-03 2.431749E-03 4.330928E-03 -3.404646E-03 +3.404647E-03 3.680298E-03 3.309620E-03 3.705541E-03 From d630746191bbaac82d9797610d31c37dbf12a2a0 Mon Sep 17 00:00:00 2001 From: Shikhar Kumar Date: Thu, 3 Dec 2020 10:37:13 -0500 Subject: [PATCH 66/79] Address @paulromano comments --- include/openmc/capi.h | 34 +++++++++++++++++----------------- openmc/lib/core.py | 5 +++-- src/cmfd_solver.cpp | 11 ++++------- 3 files changed, 24 insertions(+), 26 deletions(-) diff --git a/include/openmc/capi.h b/include/openmc/capi.h index 19f31479a2..8094a2e2f8 100644 --- a/include/openmc/capi.h +++ b/include/openmc/capi.h @@ -132,26 +132,26 @@ extern "C" { const double* y, const double* r); //! Sets the mesh and energy grid for CMFD reweight - //! \param[in] id of CMFD Mesh Tally - //! \param[in] CMFD normalization factor - //! \param[in] CMFD weight clipping factor + //! \param[in] meshtyally_id id of CMFD Mesh Tally + //! \param[in] cmfd_indices indices storing spatial and energy dimensions of CMFD problem + //! \param[in] norm CMFD normalization factor extern "C" void openmc_initialize_mesh_egrid(const int meshtally_id, const int* cmfd_indices, const double norm); //! Sets the mesh and energy grid for CMFD reweight - //! \param[in] whether or not to run CMFD feedback - //! \param[in] computed CMFD source + //! \param[in] feedback whether or not to run CMFD feedback + //! \param[in] cmfd_src computed CMFD source extern "C" void openmc_cmfd_reweight(const bool feedback, const double* cmfd_src); //! Sets the fixed variables that are used for CMFD linear solver - //! \param[in] CSR format index pointer array of loss matrix - //! \param[in] length of indptr - //! \param[in] CSR format index array of loss matrix - //! \param[in] number of non-zero elements in CMFD loss matrix - //! \param[in] dimension n of nxn CMFD loss matrix - //! \param[in] spectral radius of CMFD matrices and tolerances - //! \param[in] indices storing spatial and energy dimensions of CMFD problem - //! \param[in] coremap for problem, storing accelerated regions + //! \param[in] indptr CSR format index pointer array of loss matrix + //! \param[in] len_indptr length of indptr + //! \param[in] indices CSR format index array of loss matrix + //! \param[in] n_elements number of non-zero elements in CMFD loss matrix + //! \param[in] dim dimension n of nxn CMFD loss matrix + //! \param[in] spectral spectral radius of CMFD matrices and tolerances + //! \param[in] map coremap for problem, storing accelerated regions + //! \param[in] use_all_threads whether to use all threads when running CMFD solver extern "C" void openmc_initialize_linsolver(const int* indptr, int len_indptr, const int* indices, int n_elements, int dim, double spectral, @@ -159,10 +159,10 @@ extern "C" { //! Runs a Gauss Seidel linear solver to solve CMFD matrix equations //! linear solver - //! \param[in] CSR format data array of coefficient matrix - //! \param[in] right hand side vector - //! \param[out] unknown vector - //! \param[in] tolerance on final error + //! \param[in] A_data CSR format data array of coefficient matrix + //! \param[in] b right hand side vector + //! \param[out] x unknown vector + //! \param[in] tol tolerance on final error //! \return number of inner iterations required to reach convergence extern "C" int openmc_run_linsolver(const double* A_data, const double* b, double* x, double tol); diff --git a/openmc/lib/core.py b/openmc/lib/core.py index f24f5d7dc6..7be94e03d3 100644 --- a/openmc/lib/core.py +++ b/openmc/lib/core.py @@ -47,8 +47,9 @@ _dll.openmc_init.errcheck = _error_handler _dll.openmc_get_keff.argtypes = [POINTER(c_double*2)] _dll.openmc_get_keff.restype = c_int _dll.openmc_get_keff.errcheck = _error_handler -_init_mesh_egrid_args = [c_int, _array_1d_int, c_double] -_dll.openmc_initialize_mesh_egrid.argtypes = _init_mesh_egrid_args +_dll.openmc_initialize_mesh_egrid.argtypes = [ + c_int, _array_1d_int, c_double +] _dll.openmc_initialize_mesh_egrid.restype = None _init_linsolver_argtypes = [_array_1d_int, c_int, _array_1d_int, c_int, c_int, c_double, _array_1d_int, c_bool] diff --git a/src/cmfd_solver.cpp b/src/cmfd_solver.cpp index a3f354c17d..98ba0f6b4e 100644 --- a/src/cmfd_solver.cpp +++ b/src/cmfd_solver.cpp @@ -170,9 +170,7 @@ void openmc_cmfd_reweight(const bool feedback, const double* cmfd_src) } } - if (!feedback) { - return; - } + if (!feedback) return; #ifdef OPENMC_MPI // Send weightfactors to all processors @@ -211,7 +209,7 @@ void openmc_initialize_mesh_egrid(const int meshtally_id, const int* cmfd_indice openmc_get_tally_index(meshtally_id, &tally_index); // Get filters assocaited with tally - auto tally_filters = model::tallies[tally_index]->filters(); + const auto& tally_filters = model::tallies[tally_index]->filters(); // Get mesh filter index auto meshfilter_index = tally_filters[0]; @@ -220,15 +218,14 @@ void openmc_initialize_mesh_egrid(const int meshtally_id, const int* cmfd_indice auto energy_index = (tally_filters.size() == 2) ? tally_filters[1] : -1; // Get mesh index from mesh filter index - int32_t mesh_index; + int32_t mesh_index; openmc_mesh_filter_get_mesh(meshfilter_index, &mesh_index); // Get mesh from mesh index cmfd::mesh = get_regular_mesh(mesh_index); // Get energy bins from energy index, otherwise use default - if (energy_index != -1) - { + if (energy_index != -1) { auto efilt_base = model::tally_filters[energy_index].get(); auto* efilt = dynamic_cast(efilt_base); cmfd::egrid = efilt->bins(); From 37944edd95ac7ff8dcfb6120f6749e15714ce94f Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Fri, 11 Dec 2020 20:04:26 +0000 Subject: [PATCH 67/79] Adding a GitHub actions CI file. --- .github/workflows/ci.yml | 102 +++++++++++++++++++ src/summary.cpp | 5 + tests/regression_tests/cpp_driver/driver.cpp | 4 + tools/ci/travis-install.py | 1 + tools/ci/travis-install.sh | 10 +- 5 files changed, 117 insertions(+), 5 deletions(-) create mode 100644 .github/workflows/ci.yml diff --git a/.github/workflows/ci.yml b/.github/workflows/ci.yml new file mode 100644 index 0000000000..42cf53762d --- /dev/null +++ b/.github/workflows/ci.yml @@ -0,0 +1,102 @@ +name: CI + +on: [push] + +env: + MPI_DIR: /usr + DAGMC_ROOT: $HOME/DAGMC + HDF5_ROOT: /usr + OMP_NUM_THREADS: 2 + OPENMC_CROSS_SECTIONS: $HOME/nndc_hdf5/cross_sections.xml + OPENMC_ENDF_DATA: $HOME/endf-b-vii.1 + COVERALLS_PARALLEL: true + NUMPY_EXPERIMENTAL_ARRAY_FUNCTION: 0 + GITHUB_TOKEN: ${{ secrets.GITHUB_TOKEN }} + + +jobs: + main: + runs-on: ubuntu-16.04 + strategy: + matrix: + python-version: [3.8] + mpi: [n, y] + omp: [n, y] + dagmc: [n] + event: [n] + vectfit: [n] + + include: + - python-version: 3.6 + omp: n + mpi: n + - python-version: 3.7 + omp: n + mpi: n + - dagmc: y + python-version: 3.8 + mpi: y + omp: y + - event: y + python-version: 3.8 + omp: y + mpi: n + - vectfit: y + python-version: 3.8 + omp: n + mpi: y + + steps: + - + uses: actions/checkout@v2 + + - + name: Set up Python ${{ matrix.python-version }} + uses: actions/setup-python@v2 + with: + python-version: ${{ matrix.python-version }} + + - + name: Environment Variables + run: | + echo "OPENMC_CROSS_SECTIONS=$HOME/nndc_hdf5/cross_sections.xml" >> $GITHUB_ENV + echo "OPENMC_ENDF_DATA=$HOME/endf-b-vii.1" >> $GITHUB_ENV + echo "MPI=${{ matrix.mpi }}" >> $GITHUB_ENV + echo "PHDF5=${{ matrix.mpi }}" >> $GITHUB_ENV + echo "OMP=${{ matrix.omp }}" >> $GITHUB_ENV + echo "DAGMC=${{ matrix.dagmc }}" >> $GITHUB_ENV + echo "EVENT=${{ matrix.event }}" >> $GITHUB_ENV + echo "VECTFIT=${{ matrix.vectfit }}" >> $GITHUB_ENV + + - + name: Apt dependencies + shell: bash + run: | + sudo apt -y update + sudo apt install -y mpich \ + libmpich-dev \ + libhdf5-serial-dev \ + libhdf5-mpich-dev \ + libeigen3-dev + - + name: install + shell: bash + run: | + echo "$HOME/NJOY2016/build" >> $GITHUB_PATH + $GITHUB_WORKSPACE/tools/ci/travis-install.sh + - + name: before + shell: bash + run: $GITHUB_WORKSPACE/tools/ci/travis-before-script.sh + + - + name: test + shell: bash + run: $GITHUB_WORKSPACE/tools/ci/travis-script.sh + + - + name: after_success + shell: bash + run: | + cpp-coveralls -i src -i include --exclude-pattern "/usr/*" --dump cpp_cov.json + coveralls --merge=cpp_cov.json diff --git a/src/summary.cpp b/src/summary.cpp index 1f5f7a097b..cb7527208e 100644 --- a/src/summary.cpp +++ b/src/summary.cpp @@ -14,6 +14,11 @@ namespace openmc { void write_summary() { + +#ifdef MPI + if (!mpi::master) return; +#endif + // Display output message write_message("Writing summary.h5 file...", 5); diff --git a/tests/regression_tests/cpp_driver/driver.cpp b/tests/regression_tests/cpp_driver/driver.cpp index f6fde30fd3..db6137f1d9 100644 --- a/tests/regression_tests/cpp_driver/driver.cpp +++ b/tests/regression_tests/cpp_driver/driver.cpp @@ -48,7 +48,11 @@ int main(int argc, char** argv) { // the summary file will be used to check that // temperatures were set correctly so clear // error output can be provided +#ifdef OPENMC_MPI + if (openmc::mpi::master) openmc::write_summary(); +#else openmc::write_summary(); +#endif openmc_run(); openmc_finalize(); diff --git a/tools/ci/travis-install.py b/tools/ci/travis-install.py index a2b1b61753..2f573b1a97 100644 --- a/tools/ci/travis-install.py +++ b/tools/ci/travis-install.py @@ -47,6 +47,7 @@ def install(omp=False, mpi=False, phdf5=False, dagmc=False): if dagmc: cmake_cmd.append('-Ddagmc=ON') + cmake_cmd.append('-DCMAKE_PREFIX_PATH=~/DAGMC') # Build in coverage mode for coverage testing cmake_cmd.append('-Dcoverage=on') diff --git a/tools/ci/travis-install.sh b/tools/ci/travis-install.sh index 7bbe160aa5..4e5da241a9 100755 --- a/tools/ci/travis-install.sh +++ b/tools/ci/travis-install.sh @@ -1,6 +1,11 @@ #!/bin/bash set -ex +# Upgrade pip, pytest, numpy before doing anything else +pip install --upgrade pip +pip install --upgrade pytest +pip install --upgrade numpy + # Install NJOY 2016 ./tools/ci/travis-install-njoy.sh @@ -14,11 +19,6 @@ if [[ $VECTFIT = 'y' ]]; then ./tools/ci/travis-install-vectfit.sh fi -# Upgrade pip, pytest, numpy before doing anything else -pip install --upgrade pip -pip install --upgrade pytest -pip install --upgrade numpy - # Install mpi4py for MPI configurations if [[ $MPI == 'y' ]]; then pip install --no-binary=mpi4py mpi4py From 793f4253727002995d5dd484d3dd224d9f9ed0f0 Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Mon, 14 Dec 2020 05:50:03 +0000 Subject: [PATCH 68/79] Updating ubuntu version. --- .github/workflows/ci.yml | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/.github/workflows/ci.yml b/.github/workflows/ci.yml index 42cf53762d..5750053eba 100644 --- a/.github/workflows/ci.yml +++ b/.github/workflows/ci.yml @@ -16,7 +16,7 @@ env: jobs: main: - runs-on: ubuntu-16.04 + runs-on: ubuntu-18.04 strategy: matrix: python-version: [3.8] From 1734a07295f0cd286670690943279a531c3f3127 Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Mon, 14 Dec 2020 06:18:41 +0000 Subject: [PATCH 69/79] Adding message passing header to the C++ driver test. --- tests/regression_tests/cpp_driver/driver.cpp | 1 + 1 file changed, 1 insertion(+) diff --git a/tests/regression_tests/cpp_driver/driver.cpp b/tests/regression_tests/cpp_driver/driver.cpp index db6137f1d9..3b4bd1daa2 100644 --- a/tests/regression_tests/cpp_driver/driver.cpp +++ b/tests/regression_tests/cpp_driver/driver.cpp @@ -2,6 +2,7 @@ #include "openmc/capi.h" #include "openmc/cell.h" #include "openmc/geometry.h" +#include "openmc/message_passing.h" #include "openmc/summary.h" #include "openmc/tallies/filter.h" #include "openmc/tallies/filter_cell.h" From 1f0d53f693a9fa7b658d405983f4bfe47869fc86 Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Mon, 14 Dec 2020 16:25:41 +0000 Subject: [PATCH 70/79] Removing unecessary variables in environment. --- .github/workflows/ci.yml | 3 --- 1 file changed, 3 deletions(-) diff --git a/.github/workflows/ci.yml b/.github/workflows/ci.yml index 5750053eba..bfdaf51dec 100644 --- a/.github/workflows/ci.yml +++ b/.github/workflows/ci.yml @@ -10,9 +10,6 @@ env: OPENMC_CROSS_SECTIONS: $HOME/nndc_hdf5/cross_sections.xml OPENMC_ENDF_DATA: $HOME/endf-b-vii.1 COVERALLS_PARALLEL: true - NUMPY_EXPERIMENTAL_ARRAY_FUNCTION: 0 - GITHUB_TOKEN: ${{ secrets.GITHUB_TOKEN }} - jobs: main: From f6e1d64beabc41bb0fb56ae66edfe2f45cb06eba Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Mon, 14 Dec 2020 16:56:58 +0000 Subject: [PATCH 71/79] Re-adding GitHub token to CI file -- used to push coveralls results. --- .github/workflows/ci.yml | 4 +++- 1 file changed, 3 insertions(+), 1 deletion(-) diff --git a/.github/workflows/ci.yml b/.github/workflows/ci.yml index bfdaf51dec..9cb51aa0f6 100644 --- a/.github/workflows/ci.yml +++ b/.github/workflows/ci.yml @@ -10,10 +10,12 @@ env: OPENMC_CROSS_SECTIONS: $HOME/nndc_hdf5/cross_sections.xml OPENMC_ENDF_DATA: $HOME/endf-b-vii.1 COVERALLS_PARALLEL: true + GITHUB_TOKEN: ${{ secrets.GITHUB_TOKEN }} + jobs: main: - runs-on: ubuntu-18.04 + runs-on: ubuntu-16.04 strategy: matrix: python-version: [3.8] From 3b4a6ae0b8e147ded7df17bc79a0c17875998616 Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Mon, 14 Dec 2020 16:57:16 +0000 Subject: [PATCH 72/79] Adding GitHub actions badge to the README. --- README.md | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/README.md b/README.md index f0bb67989d..5a1a8d3d53 100644 --- a/README.md +++ b/README.md @@ -1,7 +1,7 @@ # OpenMC Monte Carlo Particle Transport Code [![License](https://img.shields.io/github/license/openmc-dev/openmc.svg)](http://openmc.readthedocs.io/en/latest/license.html) -[![Travis CI build status (Linux)](https://travis-ci.org/openmc-dev/openmc.svg?branch=develop)](https://travis-ci.org/openmc-dev/openmc) +[![GitHub Actions build status (Linux)](https://github.com/pshriwise/openmc/workflows/CI/badge.svg?branch=develop) [![Code Coverage](https://coveralls.io/repos/github/openmc-dev/openmc/badge.svg?branch=develop)](https://coveralls.io/github/openmc-dev/openmc?branch=develop) The OpenMC project aims to provide a fully-featured Monte Carlo particle From 7a294ce2673c0c0d1931e2a57aa35b91d8e1e704 Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Mon, 14 Dec 2020 16:59:23 +0000 Subject: [PATCH 73/79] Updating CI triggers. --- .github/workflows/ci.yml | 10 +++++++++- README.md | 2 +- 2 files changed, 10 insertions(+), 2 deletions(-) diff --git a/.github/workflows/ci.yml b/.github/workflows/ci.yml index 9cb51aa0f6..3945f19d5e 100644 --- a/.github/workflows/ci.yml +++ b/.github/workflows/ci.yml @@ -1,6 +1,14 @@ name: CI -on: [push] +on: + pull_request: + branches: + - develop + - master + push: + branches: + - develop + - master env: MPI_DIR: /usr diff --git a/README.md b/README.md index 5a1a8d3d53..92ea1d8db3 100644 --- a/README.md +++ b/README.md @@ -1,7 +1,7 @@ # OpenMC Monte Carlo Particle Transport Code [![License](https://img.shields.io/github/license/openmc-dev/openmc.svg)](http://openmc.readthedocs.io/en/latest/license.html) -[![GitHub Actions build status (Linux)](https://github.com/pshriwise/openmc/workflows/CI/badge.svg?branch=develop) +[![GitHub Actions build status (Linux)](https://github.com/pshriwise/openmc/workflows/CI/badge.svg?branch=develop)](https://github.com/openmc-dev/openmc/actions) [![Code Coverage](https://coveralls.io/repos/github/openmc-dev/openmc/badge.svg?branch=develop)](https://coveralls.io/github/openmc-dev/openmc?branch=develop) The OpenMC project aims to provide a fully-featured Monte Carlo particle From f0d09e4c7d29c10cc76aa7671cef1ca1aee58bab Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Mon, 14 Dec 2020 18:25:07 +0000 Subject: [PATCH 74/79] Reverting change in summary file. --- src/summary.cpp | 5 ----- 1 file changed, 5 deletions(-) diff --git a/src/summary.cpp b/src/summary.cpp index cb7527208e..1f5f7a097b 100644 --- a/src/summary.cpp +++ b/src/summary.cpp @@ -14,11 +14,6 @@ namespace openmc { void write_summary() { - -#ifdef MPI - if (!mpi::master) return; -#endif - // Display output message write_message("Writing summary.h5 file...", 5); From a0d8c5dfa6b5ebe670856b0c930ecfb1135fb925 Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Wed, 16 Dec 2020 08:24:52 -0600 Subject: [PATCH 75/79] Update README.md Co-authored-by: Paul Romano --- README.md | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/README.md b/README.md index 92ea1d8db3..a905a501c0 100644 --- a/README.md +++ b/README.md @@ -1,7 +1,7 @@ # OpenMC Monte Carlo Particle Transport Code [![License](https://img.shields.io/github/license/openmc-dev/openmc.svg)](http://openmc.readthedocs.io/en/latest/license.html) -[![GitHub Actions build status (Linux)](https://github.com/pshriwise/openmc/workflows/CI/badge.svg?branch=develop)](https://github.com/openmc-dev/openmc/actions) +[![GitHub Actions build status (Linux)](https://github.com/openmc-dev/openmc/workflows/CI/badge.svg?branch=develop)](https://github.com/openmc-dev/openmc/actions) [![Code Coverage](https://coveralls.io/repos/github/openmc-dev/openmc/badge.svg?branch=develop)](https://coveralls.io/github/openmc-dev/openmc?branch=develop) The OpenMC project aims to provide a fully-featured Monte Carlo particle From d08baece5f552967e682dcb9b370f42f06b8a54e Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Wed, 16 Dec 2020 14:28:51 +0000 Subject: [PATCH 76/79] Addressing comments from @paulromano. --- .github/workflows/ci.yml | 18 ++++-- .travis.yml | 60 ------------------- ...-before-script.sh => gha-before-script.sh} | 0 ...-install-dagmc.sh => gha-install-dagmc.sh} | 0 ...is-install-njoy.sh => gha-install-njoy.sh} | 0 ...tall-vectfit.sh => gha-install-vectfit.sh} | 0 .../ci/{travis-install.py => gha-install.py} | 0 .../ci/{travis-install.sh => gha-install.sh} | 0 tools/ci/{travis-script.sh => gha-script.sh} | 0 9 files changed, 13 insertions(+), 65 deletions(-) delete mode 100644 .travis.yml rename tools/ci/{travis-before-script.sh => gha-before-script.sh} (100%) rename tools/ci/{travis-install-dagmc.sh => gha-install-dagmc.sh} (100%) rename tools/ci/{travis-install-njoy.sh => gha-install-njoy.sh} (100%) rename tools/ci/{travis-install-vectfit.sh => gha-install-vectfit.sh} (100%) rename tools/ci/{travis-install.py => gha-install.py} (100%) rename tools/ci/{travis-install.sh => gha-install.sh} (100%) rename tools/ci/{travis-script.sh => gha-script.sh} (100%) diff --git a/.github/workflows/ci.yml b/.github/workflows/ci.yml index 3945f19d5e..5088f283eb 100644 --- a/.github/workflows/ci.yml +++ b/.github/workflows/ci.yml @@ -66,8 +66,6 @@ jobs: - name: Environment Variables run: | - echo "OPENMC_CROSS_SECTIONS=$HOME/nndc_hdf5/cross_sections.xml" >> $GITHUB_ENV - echo "OPENMC_ENDF_DATA=$HOME/endf-b-vii.1" >> $GITHUB_ENV echo "MPI=${{ matrix.mpi }}" >> $GITHUB_ENV echo "PHDF5=${{ matrix.mpi }}" >> $GITHUB_ENV echo "OMP=${{ matrix.omp }}" >> $GITHUB_ENV @@ -90,16 +88,16 @@ jobs: shell: bash run: | echo "$HOME/NJOY2016/build" >> $GITHUB_PATH - $GITHUB_WORKSPACE/tools/ci/travis-install.sh + $GITHUB_WORKSPACE/tools/ci/gha-install.sh - name: before shell: bash - run: $GITHUB_WORKSPACE/tools/ci/travis-before-script.sh + run: $GITHUB_WORKSPACE/tools/ci/gha-before-script.sh - name: test shell: bash - run: $GITHUB_WORKSPACE/tools/ci/travis-script.sh + run: $GITHUB_WORKSPACE/tools/ci/gha-script.sh - name: after_success @@ -107,3 +105,13 @@ jobs: run: | cpp-coveralls -i src -i include --exclude-pattern "/usr/*" --dump cpp_cov.json coveralls --merge=cpp_cov.json + + finish: + needs: main + runs-on: ubuntu-latest + steps: + - name: Coveralls Finished + uses: coverallsapp/github-action@master + with: + github-token: ${{ secrets.github_token }} + parallel-finished: true \ No newline at end of file diff --git a/.travis.yml b/.travis.yml deleted file mode 100644 index 6eee7f7429..0000000000 --- a/.travis.yml +++ /dev/null @@ -1,60 +0,0 @@ - -sudo: required -dist: xenial -language: python -addons: - apt: - packages: - - mpich - - libmpich-dev - - libhdf5-serial-dev - - libhdf5-mpich-dev - - libeigen3-dev - config: - retries: true -services: - - xvfb -cache: - directories: - - $HOME/nndc_hdf5 - - $HOME/endf-b-vii.1 -env: - global: - - MPI_DIR=/usr - - DAGMC_ROOT=$HOME/DAGMC - - HDF5_ROOT=/usr - - OMP_NUM_THREADS=2 - - OPENMC_CROSS_SECTIONS=$HOME/nndc_hdf5/cross_sections.xml - - OPENMC_ENDF_DATA=$HOME/endf-b-vii.1 - - PATH=$PATH:$HOME/NJOY2016/build - - COVERALLS_PARALLEL=true - - NUMPY_EXPERIMENTAL_ARRAY_FUNCTION=0 -matrix: - include: - - python: "3.6" - env: OMP=n MPI=n PHDF5=n - - python: "3.7" - env: OMP=n MPI=n PHDF5=n - - python: "3.8" - env: OMP=n MPI=n PHDF5=n - - python: "3.8" - env: OMP=y MPI=n PHDF5=n - - python: "3.8" - env: OMP=n MPI=y PHDF5=n VECTFIT=y - - python: "3.8" - env: OMP=n MPI=y PHDF5=y - - python: "3.8" - env: OMP=y MPI=y PHDF5=y DAGMC=y - - python: "3.8" - env: OMP=y MPI=n PHDF5=n EVENT=y -notifications: - webhooks: https://coveralls.io/webhook?repo_token=$COVERALLS_REPO_TOKEN -install: - - ./tools/ci/travis-install.sh -before_script: - - ./tools/ci/travis-before-script.sh -script: - - ./tools/ci/travis-script.sh -after_success: - - cpp-coveralls -i src -i include --exclude-pattern "/usr/*" --dump cpp_cov.json - - coveralls --merge=cpp_cov.json diff --git a/tools/ci/travis-before-script.sh b/tools/ci/gha-before-script.sh similarity index 100% rename from tools/ci/travis-before-script.sh rename to tools/ci/gha-before-script.sh diff --git a/tools/ci/travis-install-dagmc.sh b/tools/ci/gha-install-dagmc.sh similarity index 100% rename from tools/ci/travis-install-dagmc.sh rename to tools/ci/gha-install-dagmc.sh diff --git a/tools/ci/travis-install-njoy.sh b/tools/ci/gha-install-njoy.sh similarity index 100% rename from tools/ci/travis-install-njoy.sh rename to tools/ci/gha-install-njoy.sh diff --git a/tools/ci/travis-install-vectfit.sh b/tools/ci/gha-install-vectfit.sh similarity index 100% rename from tools/ci/travis-install-vectfit.sh rename to tools/ci/gha-install-vectfit.sh diff --git a/tools/ci/travis-install.py b/tools/ci/gha-install.py similarity index 100% rename from tools/ci/travis-install.py rename to tools/ci/gha-install.py diff --git a/tools/ci/travis-install.sh b/tools/ci/gha-install.sh similarity index 100% rename from tools/ci/travis-install.sh rename to tools/ci/gha-install.sh diff --git a/tools/ci/travis-script.sh b/tools/ci/gha-script.sh similarity index 100% rename from tools/ci/travis-script.sh rename to tools/ci/gha-script.sh From 8d92d4517ebd9b7138a9832adafc88c459411af4 Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Wed, 16 Dec 2020 14:33:12 +0000 Subject: [PATCH 77/79] Changing name of ci scripts in ci scripts. --- tools/ci/gha-install.sh | 8 ++++---- 1 file changed, 4 insertions(+), 4 deletions(-) diff --git a/tools/ci/gha-install.sh b/tools/ci/gha-install.sh index 4e5da241a9..debf833145 100755 --- a/tools/ci/gha-install.sh +++ b/tools/ci/gha-install.sh @@ -7,16 +7,16 @@ pip install --upgrade pytest pip install --upgrade numpy # Install NJOY 2016 -./tools/ci/travis-install-njoy.sh +./tools/ci/gha-install-njoy.sh # Install DAGMC if needed if [[ $DAGMC = 'y' ]]; then - ./tools/ci/travis-install-dagmc.sh + ./tools/ci/gha-install-dagmc.sh fi # Install vectfit for WMP generation if needed if [[ $VECTFIT = 'y' ]]; then - ./tools/ci/travis-install-vectfit.sh + ./tools/ci/gha-install-vectfit.sh fi # Install mpi4py for MPI configurations @@ -25,7 +25,7 @@ if [[ $MPI == 'y' ]]; then fi # Build and install OpenMC executable -python tools/ci/travis-install.py +python tools/ci/gha-install.py # Install Python API in editable mode pip install -e .[test,vtk] From 81c50485a031f55513391437e473b631e144dce0 Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Wed, 16 Dec 2020 16:34:12 +0000 Subject: [PATCH 78/79] Updating enrivonment handling. Using env block where possible. --- .github/workflows/ci.yml | 23 ++++++++++++++--------- 1 file changed, 14 insertions(+), 9 deletions(-) diff --git a/.github/workflows/ci.yml b/.github/workflows/ci.yml index 5088f283eb..5509e85c0a 100644 --- a/.github/workflows/ci.yml +++ b/.github/workflows/ci.yml @@ -1,6 +1,9 @@ name: CI on: + # allows us to run workflows manually + workflow_dispatch: + pull_request: branches: - develop @@ -15,8 +18,6 @@ env: DAGMC_ROOT: $HOME/DAGMC HDF5_ROOT: /usr OMP_NUM_THREADS: 2 - OPENMC_CROSS_SECTIONS: $HOME/nndc_hdf5/cross_sections.xml - OPENMC_ENDF_DATA: $HOME/endf-b-vii.1 COVERALLS_PARALLEL: true GITHUB_TOKEN: ${{ secrets.GITHUB_TOKEN }} @@ -53,6 +54,14 @@ jobs: omp: n mpi: y + env: + MPI: ${{ matrix.mpi }} + PHDF5: ${{ matrix.mpi }} + OMP: ${{ matrix.omp }} + DAGMC: ${{ matrix.dagmc }} + EVENT: ${{ matrix.event }} + VECTFIT: ${{ matrix.vectfit }} + steps: - uses: actions/checkout@v2 @@ -66,13 +75,9 @@ jobs: - name: Environment Variables run: | - echo "MPI=${{ matrix.mpi }}" >> $GITHUB_ENV - echo "PHDF5=${{ matrix.mpi }}" >> $GITHUB_ENV - echo "OMP=${{ matrix.omp }}" >> $GITHUB_ENV - echo "DAGMC=${{ matrix.dagmc }}" >> $GITHUB_ENV - echo "EVENT=${{ matrix.event }}" >> $GITHUB_ENV - echo "VECTFIT=${{ matrix.vectfit }}" >> $GITHUB_ENV - + echo "OPENMC_CROSS_SECTIONS=${{ env.HOME }}/nndc_hdf5/cross_sections.xml" >> $GITHUB_ENV + echo "OPENMC_ENDF_DATA=${{ env.HOME }}/endf-b-vii.1" >> $GITHUB_ENV + - name: Apt dependencies shell: bash From d77bc644c324a2547129c7fb3911113a4bf16767 Mon Sep 17 00:00:00 2001 From: Patrick Shriwise Date: Wed, 16 Dec 2020 18:35:39 +0000 Subject: [PATCH 79/79] Abandoning the use of env context for now. Back to the bash HOME variable. --- .github/workflows/ci.yml | 6 +++--- 1 file changed, 3 insertions(+), 3 deletions(-) diff --git a/.github/workflows/ci.yml b/.github/workflows/ci.yml index 5509e85c0a..f8ab9235ef 100644 --- a/.github/workflows/ci.yml +++ b/.github/workflows/ci.yml @@ -15,7 +15,6 @@ on: env: MPI_DIR: /usr - DAGMC_ROOT: $HOME/DAGMC HDF5_ROOT: /usr OMP_NUM_THREADS: 2 COVERALLS_PARALLEL: true @@ -75,8 +74,9 @@ jobs: - name: Environment Variables run: | - echo "OPENMC_CROSS_SECTIONS=${{ env.HOME }}/nndc_hdf5/cross_sections.xml" >> $GITHUB_ENV - echo "OPENMC_ENDF_DATA=${{ env.HOME }}/endf-b-vii.1" >> $GITHUB_ENV + echo "DAGMC_ROOT=$HOME/DAGMC" + echo "OPENMC_CROSS_SECTIONS=$HOME/nndc_hdf5/cross_sections.xml" >> $GITHUB_ENV + echo "OPENMC_ENDF_DATA=$HOME/endf-b-vii.1" >> $GITHUB_ENV - name: Apt dependencies