mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-28 22:26:08 -04:00
Merge remote-tracking branch 'upstream/develop' into diff_tally6
This commit is contained in:
Sterling Harper
commit
24b96ba354
45 changed files with 2156 additions and 1428 deletions
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@ -338,7 +338,7 @@
|
|||
"outputs": [
|
||||
{
|
||||
"data": {
|
||||
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|
||||
"image/png": "iVBORw0KGgoAAAANSUhEUgAAAPoAAAD6AgMAAAD1grKuAAAABGdBTUEAALGPC/xhBQAAACBjSFJN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\nFrGR5QAAAABJRU5ErkJggg==\n",
|
||||
"text/plain": [
|
||||
"<IPython.core.display.Image object>"
|
||||
]
|
||||
|
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@ -386,18 +386,18 @@
|
|||
"# Create Tallies to compute microscopic multi-group cross-sections\n",
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||||
"\n",
|
||||
"# Instantiate energy filter for multi-group cross-section Tallies\n",
|
||||
"energy_filter = openmc.Filter(type='energy', bins=[0., 0.625e-6, 20.])\n",
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||||
"energy_filter = openmc.EnergyFilter([0., 0.625e-6, 20.])\n",
|
||||
"\n",
|
||||
"# Instantiate flux Tally in moderator and fuel\n",
|
||||
"tally = openmc.Tally(name='flux')\n",
|
||||
"tally.filters = [openmc.Filter(type='cell', bins=[fuel_cell.id, moderator_cell.id])]\n",
|
||||
"tally.filters = [openmc.CellFilter([fuel_cell.id, moderator_cell.id])]\n",
|
||||
"tally.filters.append(energy_filter)\n",
|
||||
"tally.scores = ['flux']\n",
|
||||
"tallies_file.append(tally)\n",
|
||||
"\n",
|
||||
"# Instantiate reaction rate Tally in fuel\n",
|
||||
"tally = openmc.Tally(name='fuel rxn rates')\n",
|
||||
"tally.filters = [openmc.Filter(type='cell', bins=[fuel_cell.id])]\n",
|
||||
"tally.filters = [openmc.CellFilter([fuel_cell.id])]\n",
|
||||
"tally.filters.append(energy_filter)\n",
|
||||
"tally.scores = ['nu-fission', 'scatter']\n",
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"tally.nuclides = [u238, u235]\n",
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|
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@ -405,7 +405,7 @@
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|||
"\n",
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||||
"# Instantiate reaction rate Tally in moderator\n",
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||||
"tally = openmc.Tally(name='moderator rxn rates')\n",
|
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"tally.filters = [openmc.Filter(type='cell', bins=[moderator_cell.id])]\n",
|
||||
"tally.filters = [openmc.CellFilter([moderator_cell.id])]\n",
|
||||
"tally.filters.append(energy_filter)\n",
|
||||
"tally.scores = ['absorption', 'total']\n",
|
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"tally.nuclides = [o16, h1]\n",
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||||
|
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@ -417,8 +417,7 @@
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|||
"mesh.dimension = [1, 1, 1]\n",
|
||||
"mesh.lower_left = [-0.63, -0.63, -100.]\n",
|
||||
"mesh.width = [1.26, 1.26, 200.]\n",
|
||||
"mesh_filter = openmc.Filter(type='mesh', bins=[mesh.id])\n",
|
||||
"mesh_filter.mesh = mesh\n",
|
||||
"mesh_filter = openmc.MeshFilter(mesh)\n",
|
||||
"\n",
|
||||
"# Instantiate thermal, fast, and total leakage tallies\n",
|
||||
"leak = openmc.Tally(name='leakage')\n",
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||||
|
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@ -427,12 +426,12 @@
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|||
"tallies_file.append(leak)\n",
|
||||
"\n",
|
||||
"thermal_leak = openmc.Tally(name='thermal leakage')\n",
|
||||
"thermal_leak.filters = [mesh_filter, openmc.Filter(type='energy', bins=[0., 0.625e-6])]\n",
|
||||
"thermal_leak.filters = [mesh_filter, openmc.EnergyFilter([0., 0.625e-6])]\n",
|
||||
"thermal_leak.scores = ['current']\n",
|
||||
"tallies_file.append(thermal_leak)\n",
|
||||
"\n",
|
||||
"fast_leak = openmc.Tally(name='fast leakage')\n",
|
||||
"fast_leak.filters = [mesh_filter, openmc.Filter(type='energy', bins=[0.625e-6, 20.])]\n",
|
||||
"fast_leak.filters = [mesh_filter, openmc.EnergyFilter([0.625e-6, 20.])]\n",
|
||||
"fast_leak.scores = ['current']\n",
|
||||
"tallies_file.append(fast_leak)"
|
||||
]
|
||||
|
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@ -464,7 +463,7 @@
|
|||
"# Resonance Escape Probability tallies\n",
|
||||
"therm_abs_rate = openmc.Tally(name='therm. abs. rate')\n",
|
||||
"therm_abs_rate.scores = ['absorption']\n",
|
||||
"therm_abs_rate.filters = [openmc.Filter(type='energy', bins=[0., 0.625e-6])]\n",
|
||||
"therm_abs_rate.filters = [openmc.EnergyFilter([0., 0.625e-6])]\n",
|
||||
"tallies_file.append(therm_abs_rate)"
|
||||
]
|
||||
},
|
||||
|
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@ -479,8 +478,8 @@
|
|||
"# Thermal Flux Utilization tallies\n",
|
||||
"fuel_therm_abs_rate = openmc.Tally(name='fuel therm. abs. rate')\n",
|
||||
"fuel_therm_abs_rate.scores = ['absorption']\n",
|
||||
"fuel_therm_abs_rate.filters = [openmc.Filter(type='energy', bins=[0., 0.625e-6]),\n",
|
||||
" openmc.Filter(type='cell', bins=[fuel_cell.id])]\n",
|
||||
"fuel_therm_abs_rate.filters = [openmc.EnergyFilter([0., 0.625e-6]),\n",
|
||||
" openmc.CellFilter([fuel_cell.id])]\n",
|
||||
"tallies_file.append(fuel_therm_abs_rate)"
|
||||
]
|
||||
},
|
||||
|
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@ -495,7 +494,7 @@
|
|||
"# Fast Fission Factor tallies\n",
|
||||
"therm_fiss_rate = openmc.Tally(name='therm. fiss. rate')\n",
|
||||
"therm_fiss_rate.scores = ['nu-fission']\n",
|
||||
"therm_fiss_rate.filters = [openmc.Filter(type='energy', bins=[0., 0.625e-6])]\n",
|
||||
"therm_fiss_rate.filters = [openmc.EnergyFilter([0., 0.625e-6])]\n",
|
||||
"tallies_file.append(therm_fiss_rate)"
|
||||
]
|
||||
},
|
||||
|
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@ -508,11 +507,11 @@
|
|||
"outputs": [],
|
||||
"source": [
|
||||
"# Instantiate energy filter to illustrate Tally slicing\n",
|
||||
"fine_energy_filter = openmc.Filter(type='energy', bins=np.logspace(np.log10(1e-8), np.log10(20), 10))\n",
|
||||
"fine_energy_filter = openmc.EnergyFilter(np.logspace(np.log10(1e-8), np.log10(20), 10))\n",
|
||||
"\n",
|
||||
"# Instantiate flux Tally in moderator and fuel\n",
|
||||
"tally = openmc.Tally(name='need-to-slice')\n",
|
||||
"tally.filters = [openmc.Filter(type='cell', bins=[fuel_cell.id, moderator_cell.id])]\n",
|
||||
"tally.filters = [openmc.CellFilter(bins=[fuel_cell.id, moderator_cell.id])]\n",
|
||||
"tally.filters.append(fine_energy_filter)\n",
|
||||
"tally.scores = ['nu-fission', 'scatter']\n",
|
||||
"tally.nuclides = [h1, u238]\n",
|
||||
|
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@ -550,7 +549,6 @@
|
|||
"name": "stdout",
|
||||
"output_type": "stream",
|
||||
"text": [
|
||||
"rm: cannot remove 'statepoint.*': No such file or directory\n",
|
||||
"\n",
|
||||
" %%%%%%%%%%%%%%%\n",
|
||||
" %%%%%%%%%%%%%%%%%%%%%%%%\n",
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||||
|
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@ -580,9 +578,9 @@
|
|||
" Copyright | 2011-2016 Massachusetts Institute of Technology\n",
|
||||
" License | http://openmc.readthedocs.io/en/latest/license.html\n",
|
||||
" Version | 0.8.0\n",
|
||||
" Git SHA1 | 623b705a399f16c8e5063732bc6e6a357611542d\n",
|
||||
" Date/Time | 2016-09-03 04:38:41\n",
|
||||
" OpenMP Threads | 4\n",
|
||||
" Git SHA1 | b02fa21928a37a2254bec13c9802ff8173b6aefd\n",
|
||||
" Date/Time | 2016-09-29 23:59:21\n",
|
||||
" MPI Processes | 1\n",
|
||||
"\n",
|
||||
" ===========================================================================\n",
|
||||
" ========================> INITIALIZATION <=========================\n",
|
||||
|
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@ -592,12 +590,12 @@
|
|||
" Reading geometry XML file...\n",
|
||||
" Reading cross sections XML file...\n",
|
||||
" Reading materials XML file...\n",
|
||||
" Reading U235 from /opt/xsdata/nndc_new/U235.h5\n",
|
||||
" Reading U238 from /opt/xsdata/nndc_new/U238.h5\n",
|
||||
" Reading O16 from /opt/xsdata/nndc_new/O16.h5\n",
|
||||
" Reading H1 from /opt/xsdata/nndc_new/H1.h5\n",
|
||||
" Reading B10 from /opt/xsdata/nndc_new/B10.h5\n",
|
||||
" Reading Zr90 from /opt/xsdata/nndc_new/Zr90.h5\n",
|
||||
" Reading U235 from /home/smharper/openmc/data/nndc_hdf5/U235.h5\n",
|
||||
" Reading U238 from /home/smharper/openmc/data/nndc_hdf5/U238.h5\n",
|
||||
" Reading O16 from /home/smharper/openmc/data/nndc_hdf5/O16.h5\n",
|
||||
" Reading H1 from /home/smharper/openmc/data/nndc_hdf5/H1.h5\n",
|
||||
" Reading B10 from /home/smharper/openmc/data/nndc_hdf5/B10.h5\n",
|
||||
" Reading Zr90 from /home/smharper/openmc/data/nndc_hdf5/Zr90.h5\n",
|
||||
" Maximum neutron transport energy: 20.0000 MeV for U235\n",
|
||||
" Reading tallies XML file...\n",
|
||||
" Building neighboring cells lists for each surface...\n",
|
||||
|
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@ -638,20 +636,20 @@
|
|||
"\n",
|
||||
" =======================> TIMING STATISTICS <=======================\n",
|
||||
"\n",
|
||||
" Total time for initialization = 3.8900E-01 seconds\n",
|
||||
" Reading cross sections = 2.7000E-01 seconds\n",
|
||||
" Total time in simulation = 4.6960E+00 seconds\n",
|
||||
" Time in transport only = 4.6760E+00 seconds\n",
|
||||
" Time in inactive batches = 6.6400E-01 seconds\n",
|
||||
" Time in active batches = 4.0320E+00 seconds\n",
|
||||
" Total time for initialization = 2.9900E-01 seconds\n",
|
||||
" Reading cross sections = 1.8000E-01 seconds\n",
|
||||
" Total time in simulation = 1.6156E+01 seconds\n",
|
||||
" Time in transport only = 1.6145E+01 seconds\n",
|
||||
" Time in inactive batches = 2.3940E+00 seconds\n",
|
||||
" Time in active batches = 1.3762E+01 seconds\n",
|
||||
" Time synchronizing fission bank = 1.0000E-03 seconds\n",
|
||||
" Sampling source sites = 1.0000E-03 seconds\n",
|
||||
" SEND/RECV source sites = 0.0000E+00 seconds\n",
|
||||
" Time accumulating tallies = 0.0000E+00 seconds\n",
|
||||
" Total time for finalization = 1.0000E-03 seconds\n",
|
||||
" Total time elapsed = 5.0960E+00 seconds\n",
|
||||
" Calculation Rate (inactive) = 18825.3 neutrons/second\n",
|
||||
" Calculation Rate (active) = 9300.60 neutrons/second\n",
|
||||
" Total time elapsed = 1.6476E+01 seconds\n",
|
||||
" Calculation Rate (inactive) = 5221.39 neutrons/second\n",
|
||||
" Calculation Rate (active) = 2724.89 neutrons/second\n",
|
||||
"\n",
|
||||
" ============================> RESULTS <============================\n",
|
||||
"\n",
|
||||
|
|
@ -768,8 +766,8 @@
|
|||
"\n",
|
||||
"# Get the leakage tally\n",
|
||||
"leak = sp.get_tally(name='leakage')\n",
|
||||
"leak = leak.summation(filter_type='surface', remove_filter=True)\n",
|
||||
"leak = leak.summation(filter_type='mesh', remove_filter=True)\n",
|
||||
"leak = leak.summation(filter_type=openmc.SurfaceFilter, remove_filter=True)\n",
|
||||
"leak = leak.summation(filter_type=openmc.MeshFilter, remove_filter=True)\n",
|
||||
"\n",
|
||||
"# Compute k-infinity using tally arithmetic\n",
|
||||
"keff = fiss_rate / (abs_rate + leak)\n",
|
||||
|
|
@ -839,8 +837,8 @@
|
|||
"# Compute resonance escape probability using tally arithmetic\n",
|
||||
"therm_abs_rate = sp.get_tally(name='therm. abs. rate')\n",
|
||||
"thermal_leak = sp.get_tally(name='thermal leakage')\n",
|
||||
"thermal_leak = thermal_leak.summation(filter_type='surface', remove_filter=True)\n",
|
||||
"thermal_leak = thermal_leak.summation(filter_type='mesh', remove_filter=True)\n",
|
||||
"thermal_leak = thermal_leak.summation(filter_type=openmc.SurfaceFilter, remove_filter=True)\n",
|
||||
"thermal_leak = thermal_leak.summation(filter_type=openmc.MeshFilter, remove_filter=True)\n",
|
||||
"res_esc = (therm_abs_rate + thermal_leak) / (abs_rate + thermal_leak)\n",
|
||||
"res_esc.get_pandas_dataframe()"
|
||||
]
|
||||
|
|
@ -1248,7 +1246,7 @@
|
|||
"source": [
|
||||
"# Compute microscopic multi-group cross-sections\n",
|
||||
"flux = sp.get_tally(name='flux')\n",
|
||||
"flux = flux.get_slice(filters=['cell'], filter_bins=[(fuel_cell.id,)])\n",
|
||||
"flux = flux.get_slice(filters=[openmc.CellFilter], filter_bins=[(fuel_cell.id,)])\n",
|
||||
"fuel_rxn_rates = sp.get_tally(name='fuel rxn rates')\n",
|
||||
"mod_rxn_rates = sp.get_tally(name='moderator rxn rates')"
|
||||
]
|
||||
|
|
@ -1475,7 +1473,7 @@
|
|||
],
|
||||
"source": [
|
||||
"# Show how to use Tally.get_values(...) with a CrossFilter and CrossScore\n",
|
||||
"fast_scatter_xs = fuel_xs.get_values(filters=['energy'], \n",
|
||||
"fast_scatter_xs = fuel_xs.get_values(filters=[openmc.EnergyFilter], \n",
|
||||
" filter_bins=[((0.625e-6, 20.),)], \n",
|
||||
" scores=['(scatter / flux)'])\n",
|
||||
"print(fast_scatter_xs)"
|
||||
|
|
@ -1734,9 +1732,18 @@
|
|||
"# \"Slice\" the H-1 scatter data in the moderator Cell into a new derived Tally\n",
|
||||
"need_to_slice = sp.get_tally(name='need-to-slice')\n",
|
||||
"slice_test = need_to_slice.get_slice(scores=['scatter'], nuclides=['H1'],\n",
|
||||
" filters=['cell'], filter_bins=[(moderator_cell.id,)])\n",
|
||||
" filters=[openmc.CellFilter], filter_bins=[(moderator_cell.id,)])\n",
|
||||
"slice_test.get_pandas_dataframe()"
|
||||
]
|
||||
},
|
||||
{
|
||||
"cell_type": "code",
|
||||
"execution_count": null,
|
||||
"metadata": {
|
||||
"collapsed": true
|
||||
},
|
||||
"outputs": [],
|
||||
"source": []
|
||||
}
|
||||
],
|
||||
"metadata": {
|
||||
|
|
|
|||
|
|
@ -133,7 +133,19 @@ Constructing Tallies
|
|||
:nosignatures:
|
||||
:template: myclass.rst
|
||||
|
||||
openmc.Filter
|
||||
openmc.UniverseFilter
|
||||
openmc.MaterialFilter
|
||||
openmc.CellFilter
|
||||
openmc.CellbornFilter
|
||||
openmc.SurfaceFilter
|
||||
openmc.MeshFilter
|
||||
openmc.EnergyFilter
|
||||
openmc.EnergyoutFilter
|
||||
openmc.MuFilter
|
||||
openmc.PolarFilter
|
||||
openmc.AzimuthalFilter
|
||||
openmc.DistribcellFilter
|
||||
openmc.DelayedGroupFilter
|
||||
openmc.Mesh
|
||||
openmc.Trigger
|
||||
openmc.Tally
|
||||
|
|
|
|||
|
|
@ -292,8 +292,8 @@ OpenMC can use it for on-the-fly Doppler-broadening of resolved resonance range
|
|||
cross sections. If this element is absent from the settings.xml file, the
|
||||
:envvar:`OPENMC_MULTIPOLE_LIBRARY` environment variable will be used.
|
||||
|
||||
.. note:: The :ref:`temperature_method` must also be set to "multipole" for
|
||||
windowed multipole functionality.
|
||||
.. note:: The <temperature_multipole> element must also be set to "true" for
|
||||
windowed multipole functionality.
|
||||
|
||||
``<max_order>`` Element
|
||||
---------------------------
|
||||
|
|
@ -725,19 +725,29 @@ a material default temperature.
|
|||
``<temperature_method>`` Element
|
||||
--------------------------------
|
||||
|
||||
The ``<temperature_method>`` element has an accepted value of "nearest",
|
||||
"interpolation", or "multipole". A value of "nearest" indicates that for each
|
||||
The ``<temperature_method>`` element has an accepted value of "nearest" or
|
||||
"interpolation". A value of "nearest" indicates that for each
|
||||
cell, the nearest temperature at which cross sections are given is to be
|
||||
applied, within a given tolerance (see :ref:`temperature_tolerance`). A value of
|
||||
"interpolation" indicates that cross sections are to be linear-linear
|
||||
interpolated between temperatures at which nuclear data are present (see
|
||||
:ref:`temperature_treatment`). A value of "multipole" indicates that the
|
||||
windowed multipole method should be used to evaluate temperature-dependent cross
|
||||
sections in the resolved resonance range (a :ref:`windowed multipole library
|
||||
<multipole_library>` must also be available).
|
||||
:ref:`temperature_treatment`).
|
||||
|
||||
*Default*: "nearest"
|
||||
|
||||
.. _temperature_multipole:
|
||||
|
||||
``<temperature_multipole>`` Element
|
||||
-----------------------------------
|
||||
|
||||
The ``<temperature_multipole>`` element toggles the windowed multipole
|
||||
capability on or off. If this element is set to "True" and the relevant data is
|
||||
available, OpenMC will use the windowed multipole method to evaluate and Doppler
|
||||
broaden cross sections in the resolved resonance range. This override other
|
||||
methods like "nearest" and "interpolation" in the resolved resonance range.
|
||||
|
||||
*Default*: False
|
||||
|
||||
.. _temperature_tolerance:
|
||||
|
||||
``<temperature_tolerance>`` Element
|
||||
|
|
@ -850,17 +860,6 @@ problem. It has the following attributes/sub-elements:
|
|||
|
||||
*Default*: None
|
||||
|
||||
|
||||
``<use_windowed_multipole>`` Element
|
||||
------------------------------------
|
||||
|
||||
The ``<use_windowed_multipole>`` element toggles the windowed multipole
|
||||
capability on or off. If this element is set to "True" and the relevant data is
|
||||
available, OpenMC will use the windowed multipole method to evaluate and Doppler
|
||||
broaden cross sections in the resolved resonance range.
|
||||
|
||||
*Default*: False
|
||||
|
||||
``<verbosity>`` Element
|
||||
-----------------------
|
||||
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue