mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-28 14:15:42 -04:00
Merge branch 'develop' of github.com:openmc-dev/openmc into cmfd-omp
Conflicts: openmc/cmfd.py
This commit is contained in:
Shikhar Kumar
commit
362e4d16b4
181 changed files with 4426 additions and 2007 deletions
|
|
@ -114,7 +114,11 @@ endif()
|
|||
#===============================================================================
|
||||
|
||||
add_library(pugixml vendor/pugixml/pugixml.cpp)
|
||||
target_include_directories(pugixml PUBLIC vendor/pugixml/)
|
||||
target_include_directories(pugixml
|
||||
PUBLIC
|
||||
$<INSTALL_INTERFACE:include/pugixml>
|
||||
$<BUILD_INTERFACE:${CMAKE_CURRENT_SOURCE_DIR}/vendor/pugixml>
|
||||
)
|
||||
|
||||
#===============================================================================
|
||||
# xtensor header-only library
|
||||
|
|
@ -134,7 +138,11 @@ target_link_libraries(xtensor INTERFACE xtl)
|
|||
#===============================================================================
|
||||
|
||||
add_library(gsl INTERFACE)
|
||||
target_include_directories(gsl INTERFACE vendor/gsl/include)
|
||||
target_include_directories(gsl
|
||||
INTERFACE
|
||||
$<INSTALL_INTERFACE:include/gsl/include>
|
||||
$<BUILD_INTERFACE:${CMAKE_CURRENT_SOURCE_DIR}/vendor/gsl/include>
|
||||
)
|
||||
|
||||
# Make sure contract violations throw exceptions
|
||||
target_compile_definitions(gsl INTERFACE GSL_THROW_ON_CONTRACT_VIOLATION)
|
||||
|
|
@ -172,7 +180,11 @@ endif()
|
|||
#===============================================================================
|
||||
|
||||
add_library(faddeeva STATIC vendor/faddeeva/Faddeeva.cc)
|
||||
target_include_directories(faddeeva PUBLIC vendor/faddeeva/)
|
||||
target_include_directories(faddeeva
|
||||
PUBLIC
|
||||
$<INSTALL_INTERFACE:include/faddeeva>
|
||||
$<BUILD_INTERFACE:${CMAKE_CURRENT_SOURCE_DIR}/vendor/faddeeva>
|
||||
)
|
||||
target_compile_options(faddeeva PRIVATE ${cxxflags})
|
||||
|
||||
#===============================================================================
|
||||
|
|
@ -283,7 +295,11 @@ set_target_properties(libopenmc PROPERTIES
|
|||
OUTPUT_NAME openmc)
|
||||
|
||||
target_include_directories(libopenmc
|
||||
PUBLIC include ${HDF5_INCLUDE_DIRS})
|
||||
PUBLIC
|
||||
$<INSTALL_INTERFACE:include>
|
||||
$<BUILD_INTERFACE:${CMAKE_CURRENT_SOURCE_DIR}/include>
|
||||
${HDF5_INCLUDE_DIRS}
|
||||
)
|
||||
|
||||
# Set compile flags
|
||||
target_compile_options(libopenmc PRIVATE ${cxxflags})
|
||||
|
|
@ -336,19 +352,35 @@ set_target_properties(
|
|||
add_custom_command(TARGET libopenmc POST_BUILD
|
||||
COMMAND ${CMAKE_COMMAND} -E copy
|
||||
$<TARGET_FILE:libopenmc>
|
||||
${CMAKE_CURRENT_SOURCE_DIR}/openmc/capi/$<TARGET_FILE_NAME:libopenmc>
|
||||
${CMAKE_CURRENT_SOURCE_DIR}/openmc/lib/$<TARGET_FILE_NAME:libopenmc>
|
||||
COMMENT "Copying libopenmc to Python module directory")
|
||||
|
||||
#===============================================================================
|
||||
# Install executable, scripts, manpage, license
|
||||
#===============================================================================
|
||||
|
||||
install(TARGETS openmc libopenmc
|
||||
RUNTIME DESTINATION bin
|
||||
LIBRARY DESTINATION lib
|
||||
ARCHIVE DESTINATION lib
|
||||
)
|
||||
install(DIRECTORY src/relaxng DESTINATION share/openmc)
|
||||
install(FILES man/man1/openmc.1 DESTINATION share/man/man1)
|
||||
install(FILES LICENSE DESTINATION "share/doc/openmc" RENAME copyright)
|
||||
install(DIRECTORY include/ DESTINATION include)
|
||||
include(GNUInstallDirs)
|
||||
set(INSTALL_CONFIGDIR ${CMAKE_INSTALL_LIBDIR}/cmake/OpenMC)
|
||||
install(TARGETS openmc libopenmc pugixml faddeeva gsl
|
||||
EXPORT openmc-targets
|
||||
RUNTIME DESTINATION ${CMAKE_INSTALL_BINDIR}
|
||||
LIBRARY DESTINATION ${CMAKE_INSTALL_LIBDIR}
|
||||
ARCHIVE DESTINATION ${CMAKE_INSTALL_LIBDIR}
|
||||
)
|
||||
install(EXPORT openmc-targets
|
||||
FILE OpenMCTargets.cmake
|
||||
NAMESPACE OpenMC::
|
||||
DESTINATION ${INSTALL_CONFIGDIR})
|
||||
|
||||
install(DIRECTORY src/relaxng DESTINATION ${CMAKE_INSTALL_DATADIR}/openmc)
|
||||
install(FILES cmake/OpenMCConfig.cmake DESTINATION ${INSTALL_CONFIGDIR})
|
||||
install(FILES man/man1/openmc.1 DESTINATION ${CMAKE_INSTALL_MANDIR}/man1)
|
||||
install(FILES LICENSE DESTINATION "${CMAKE_INSTALL_DOCDIR}" RENAME copyright)
|
||||
install(DIRECTORY include/ DESTINATION ${CMAKE_INSTALL_INCLUDEDIR})
|
||||
|
||||
# Copy headers for vendored dependencies (note that xtensor/xtl are handled
|
||||
# separately since they are managed by CMake)
|
||||
install(DIRECTORY vendor/pugixml DESTINATION ${CMAKE_INSTALL_INCLUDEDIR}
|
||||
FILES_MATCHING PATTERN "*.hpp")
|
||||
install(DIRECTORY vendor/gsl DESTINATION ${CMAKE_INSTALL_INCLUDEDIR})
|
||||
install(DIRECTORY vendor/faddeeva DESTINATION ${CMAKE_INSTALL_INCLUDEDIR})
|
||||
|
|
|
|||
48
CODEOWNERS
Normal file
48
CODEOWNERS
Normal file
|
|
@ -0,0 +1,48 @@
|
|||
# Data interface
|
||||
openmc/data/ @paulromano
|
||||
|
||||
# Python bindings to C/C++ API
|
||||
openmc/lib/ @paulromano
|
||||
|
||||
# Depletion
|
||||
openmc/deplete/ @drewejohnson
|
||||
tests/regression_tests/deplete/ @drewejohnson
|
||||
tests/unit_tests/test_deplete_*.py @drewejohnson
|
||||
|
||||
# MG-related functionality
|
||||
openmc/mgxs_library.py @nelsonag
|
||||
src/mgxs.cpp @nelsonag
|
||||
src/mgxs_interface.cpp @nelsonag
|
||||
src/physics_mg.cpp @nelsonag
|
||||
src/scattdata.cpp @nelsonag
|
||||
src/xsdata.cpp @nelsonag
|
||||
|
||||
# CMFD
|
||||
openmc/cmfd.py @shikhar413
|
||||
src/cmfd_solver.cpp @shikhar413
|
||||
|
||||
# DAGMC
|
||||
src/dagmc.cpp @pshriwise
|
||||
tests/regression_tests/dagmc/ @pshriwise
|
||||
tests/unit_tests/dagmc/ @pshriwise
|
||||
|
||||
# Photon transport
|
||||
openmc/data/BREMX.DAT @amandalund
|
||||
openmc/data/compton_profiles.h5 @amandalund
|
||||
openmc/data/photon.py @amandalund
|
||||
src/photon.cpp @amandalund
|
||||
src/bremsstrahlung.cpp @amandalund
|
||||
tests/regression_tests/photon_production/ @amandalund
|
||||
tests/regression_tests/photon_source/ @amandalund
|
||||
|
||||
# RCP and TRISOs
|
||||
openmc/model/triso.py @amandalund
|
||||
tests/regression_tests/triso/ @amandalund
|
||||
tests/unit_tests/test_model_triso.py @amandalund
|
||||
|
||||
# Geometry plotting
|
||||
src/plot.cpp @pshriwise
|
||||
openmc/lib/plot.py @pshriwise
|
||||
|
||||
# Resonance covariance
|
||||
openmc/data/resonance_covariance.py @icmeyer
|
||||
2
LICENSE
2
LICENSE
|
|
@ -1,4 +1,4 @@
|
|||
Copyright (c) 2011-2018 Massachusetts Institute of Technology and OpenMC contributors
|
||||
Copyright (c) 2011-2019 Massachusetts Institute of Technology and OpenMC contributors
|
||||
|
||||
Permission is hereby granted, free of charge, to any person obtaining a copy of
|
||||
this software and associated documentation files (the "Software"), to deal in
|
||||
|
|
|
|||
8
cmake/OpenMCConfig.cmake
Normal file
8
cmake/OpenMCConfig.cmake
Normal file
|
|
@ -0,0 +1,8 @@
|
|||
get_filename_component(OpenMC_CMAKE_DIR "${CMAKE_CURRENT_LIST_FILE}" DIRECTORY)
|
||||
|
||||
find_package(xtl REQUIRED HINTS ${OpenMC_CMAKE_DIR}/../xtl)
|
||||
find_package(xtensor REQUIRED HINTS ${OpenMC_CMAKE_DIR}/../xtensor)
|
||||
|
||||
if(NOT TARGET OpenMC::libopenmc)
|
||||
include("${OpenMC_CMAKE_DIR}/OpenMCTargets.cmake")
|
||||
endif()
|
||||
|
|
@ -1,3 +1,4 @@
|
|||
sphinx-numfig
|
||||
jupyter
|
||||
sphinxcontrib-katex
|
||||
sphinxcontrib-svg2pdfconverter
|
||||
|
|
|
|||
BIN
docs/source/_images/cosine-dist.png
Normal file
BIN
docs/source/_images/cosine-dist.png
Normal file
Binary file not shown.
|
After Width: | Height: | Size: 39 KiB |
9
docs/source/_templates/mycallable.rst
Normal file
9
docs/source/_templates/mycallable.rst
Normal file
|
|
@ -0,0 +1,9 @@
|
|||
{{ fullname }}
|
||||
{{ underline }}
|
||||
|
||||
.. currentmodule:: {{ module }}
|
||||
|
||||
.. autoclass:: {{ objname }}
|
||||
:members:
|
||||
:special-members: __call__
|
||||
|
||||
|
|
@ -1,17 +1,17 @@
|
|||
.. _capi:
|
||||
|
||||
=====
|
||||
C API
|
||||
=====
|
||||
=========
|
||||
C/C++ API
|
||||
=========
|
||||
|
||||
The libopenmc shared library that is built when installing OpenMC exports a
|
||||
number of C interoperable functions and global variables that can be used for
|
||||
in-memory coupling. While it is possible to directly use the C API as documented
|
||||
here for coupling, most advanced users will find it easier to work with the
|
||||
Python bindings in the :py:mod:`openmc.capi` module.
|
||||
in-memory coupling. While it is possible to directly use the C/C++ API as
|
||||
documented here for coupling, most advanced users will find it easier to work
|
||||
with the Python bindings in the :py:mod:`openmc.lib` module.
|
||||
|
||||
.. warning:: The C API is still experimental and may undergo substantial changes
|
||||
in future releases.
|
||||
.. warning:: The C/C++ API is still experimental and may undergo substantial
|
||||
changes in future releases.
|
||||
|
||||
----------------
|
||||
Type Definitions
|
||||
|
|
|
|||
|
|
@ -27,7 +27,7 @@ MOCK_MODULES = [
|
|||
'scipy.interpolate', 'scipy.integrate', 'scipy.optimize', 'scipy.special',
|
||||
'scipy.stats', 'scipy.spatial', 'h5py', 'pandas', 'uncertainties',
|
||||
'matplotlib', 'matplotlib.pyplot', 'openmoc',
|
||||
'openmc.data.reconstruct'
|
||||
'openmc.data.reconstruct', 'openmc.checkvalue'
|
||||
]
|
||||
sys.modules.update((mod_name, MagicMock()) for mod_name in MOCK_MODULES)
|
||||
|
||||
|
|
@ -56,7 +56,7 @@ extensions = ['sphinx.ext.autodoc',
|
|||
'sphinx_numfig',
|
||||
'notebook_sphinxext']
|
||||
if not on_rtd:
|
||||
extensions.append('sphinx.ext.imgconverter')
|
||||
extensions.append('sphinxcontrib.rsvgconverter')
|
||||
|
||||
# Add any paths that contain templates here, relative to this directory.
|
||||
templates_path = ['_templates']
|
||||
|
|
@ -79,9 +79,9 @@ copyright = '2011-2019, Massachusetts Institute of Technology and OpenMC contrib
|
|||
# built documents.
|
||||
#
|
||||
# The short X.Y version.
|
||||
version = "0.11"
|
||||
version = "0.12"
|
||||
# The full version, including alpha/beta/rc tags.
|
||||
release = "0.11.0-dev"
|
||||
release = "0.12.0-dev"
|
||||
|
||||
# The language for content autogenerated by Sphinx. Refer to documentation
|
||||
# for a list of supported languages.
|
||||
|
|
|
|||
|
|
@ -5,27 +5,28 @@ Building Sphinx Documentation
|
|||
=============================
|
||||
|
||||
In order to build the documentation in the ``docs`` directory, you will need to
|
||||
have the `Sphinx <http://openmc.readthedocs.io/en/latest/>`_ third-party Python
|
||||
have the `Sphinx <https://www.sphinx-doc.org/en/master/>`_ third-party Python
|
||||
package. The easiest way to install Sphinx is via pip:
|
||||
|
||||
.. code-block:: sh
|
||||
|
||||
sudo pip install sphinx
|
||||
pip install sphinx
|
||||
|
||||
Additionally, you will also need a Sphinx extension for numbering figures. The
|
||||
`Numfig <http://openmc.readthedocs.io/en/latest/>`_ package can be installed
|
||||
Additionally, you will need several Sphinx extensions that can be installed
|
||||
directly with pip:
|
||||
|
||||
.. code-block:: sh
|
||||
|
||||
sudo pip install sphinx-numfig
|
||||
pip install sphinx-numfig
|
||||
pip install sphinxcontrib-katex
|
||||
pip install sphinxcontrib-svg2pdfconverter
|
||||
|
||||
-----------------------------------
|
||||
Building Documentation as a Webpage
|
||||
-----------------------------------
|
||||
|
||||
To build the documentation as a webpage (what appears at
|
||||
http://openmc.readthedocs.io), simply go to the ``docs`` directory and run:
|
||||
https://docs.openmc.org), simply go to the ``docs`` directory and run:
|
||||
|
||||
.. code-block:: sh
|
||||
|
||||
|
|
|
|||
|
|
@ -19,7 +19,7 @@ build a Docker image with OpenMC installed. The image includes OpenMC with
|
|||
MPICH and parallel HDF5 in the ``/opt/openmc`` directory, and
|
||||
`Miniconda3 <https://conda.io/miniconda.html>`_ with all of the Python
|
||||
pre-requisites (NumPy, SciPy, Pandas, etc.) installed. The
|
||||
`NJOY2016 <http://www.njoy21.io/NJOY2016/>`_ codebase is installed in
|
||||
`NJOY2016 <https://www.njoy21.io/NJOY2016/>`_ codebase is installed in
|
||||
``/opt/NJOY2016`` to support full functionality and testing of the
|
||||
``openmc.data`` Python module. The publicly available nuclear data libraries
|
||||
necessary to run OpenMC's test suite -- including NNDC and WMP cross sections
|
||||
|
|
@ -54,4 +54,3 @@ Docker container where you have access to use OpenMC.
|
|||
.. _Docker container: https://www.docker.com/resources/what-container
|
||||
.. _options: https://docs.docker.com/engine/reference/commandline/run/
|
||||
.. _mounting volumes: https://docs.docker.com/storage/volumes/
|
||||
|
||||
|
|
|
|||
|
|
@ -207,8 +207,8 @@ Documentation
|
|||
-------------
|
||||
|
||||
Classes, structs, and functions are to be annotated for the `Doxygen
|
||||
<http://www.stack.nl/~dimitri/doxygen/>`_ documentation generation tool. Use the
|
||||
``\`` form of Doxygen commands, e.g., ``\brief`` instead of ``@brief``.
|
||||
<http://www.doxygen.nl/>`_ documentation generation tool. Use the ``\`` form of
|
||||
Doxygen commands, e.g., ``\brief`` instead of ``@brief``.
|
||||
|
||||
------
|
||||
Python
|
||||
|
|
@ -231,7 +231,7 @@ represent a filesystem path should work with both strings and Path_ objects.
|
|||
.. _C++ Core Guidelines: http://isocpp.github.io/CppCoreGuidelines/CppCoreGuidelines
|
||||
.. _PEP8: https://www.python.org/dev/peps/pep-0008/
|
||||
.. _numpydoc: https://numpydoc.readthedocs.io/en/latest/format.html
|
||||
.. _numpy: http://www.numpy.org/
|
||||
.. _numpy: https://numpy.org/
|
||||
.. _scipy: https://www.scipy.org/
|
||||
.. _matplotlib: https://matplotlib.org/
|
||||
.. _pandas: https://pandas.pydata.org/
|
||||
|
|
|
|||
|
|
@ -124,7 +124,7 @@ can interfere with virtual environments.
|
|||
.. _GitHub: https://github.com/
|
||||
.. _git flow: http://nvie.com/git-model
|
||||
.. _valgrind: http://valgrind.org/
|
||||
.. _style guide: http://openmc.readthedocs.io/en/latest/devguide/styleguide.html
|
||||
.. _style guide: https://docs.openmc.org/en/latest/devguide/styleguide.html
|
||||
.. _pull request: https://help.github.com/articles/using-pull-requests
|
||||
.. _openmc-dev/openmc: https://github.com/openmc-dev/openmc
|
||||
.. _paid plan: https://github.com/plans
|
||||
|
|
|
|||
|
|
@ -24,6 +24,7 @@ General Usage
|
|||
nuclear-data
|
||||
nuclear-data-resonance-covariance
|
||||
cad-geom
|
||||
pincell-depletion
|
||||
|
||||
--------
|
||||
Geometry
|
||||
|
|
|
|||
14
docs/source/examples/pincell-depletion.rst
Normal file
14
docs/source/examples/pincell-depletion.rst
Normal file
|
|
@ -0,0 +1,14 @@
|
|||
.. _notebook_depletion:
|
||||
|
||||
=================
|
||||
Pincell Depletion
|
||||
=================
|
||||
|
||||
|
||||
.. only:: html
|
||||
|
||||
.. notebook:: ../../../examples/jupyter/pincell_depletion.ipynb
|
||||
|
||||
.. only:: latex
|
||||
|
||||
IPython notebooks must be viewed in the online HTML documentation.
|
||||
|
|
@ -2,12 +2,14 @@
|
|||
The OpenMC Monte Carlo Code
|
||||
===========================
|
||||
|
||||
OpenMC is a Monte Carlo particle transport simulation code focused on neutron
|
||||
criticality calculations. It is capable of simulating 3D models based on
|
||||
constructive solid geometry with second-order surfaces. OpenMC supports either
|
||||
continuous-energy or multi-group transport. The continuous-energy particle
|
||||
OpenMC is a community-developed Monte Carlo neutron and photon transport
|
||||
simulation code. It is capable of performing fixed source, k-eigenvalue, and
|
||||
subcritical multiplication calculations on models built using either a
|
||||
constructive solid geometry or CAD representation. OpenMC supports both
|
||||
continuous-energy and multigroup transport. The continuous-energy particle
|
||||
interaction data is based on a native HDF5 format that can be generated from ACE
|
||||
files used by the MCNP and Serpent Monte Carlo codes.
|
||||
files produced by NJOY. Parallelism is enabled via a hybrid MPI and OpenMP
|
||||
programming model.
|
||||
|
||||
OpenMC was originally developed by members of the `Computational Reactor Physics
|
||||
Group <http://crpg.mit.edu>`_ at the `Massachusetts Institute of Technology
|
||||
|
|
|
|||
|
|
@ -333,7 +333,7 @@ or sub-elements:
|
|||
velocity sampling) or "dbrc" (Doppler broadening rejection correction).
|
||||
Descriptions of each of these methods are documented here_.
|
||||
|
||||
.. _here: http://dx.doi.org/10.1016/j.anucene.2017.12.044
|
||||
.. _here: https://doi.org/10.1016/j.anucene.2017.12.044
|
||||
|
||||
*Default*: "rvs"
|
||||
|
||||
|
|
|
|||
|
|
@ -109,6 +109,11 @@ The current version of the statepoint file format is 17.0.
|
|||
|
||||
**/tallies/tally <uid>/**
|
||||
|
||||
:Attributes:
|
||||
- **internal** (*int*) -- Flag indicating the presence of tally
|
||||
data (0) or absence of tally data (1). All user defined
|
||||
tallies will have a value of 0 unless otherwise instructed.
|
||||
|
||||
:Datasets: - **n_realizations** (*int*) -- Number of realizations.
|
||||
- **n_filters** (*int*) -- Number of filters used.
|
||||
- **filters** (*int[]*) -- User-defined unique IDs of the filters on
|
||||
|
|
|
|||
|
|
@ -23,6 +23,8 @@ The current version of the volume file format is 1.0.
|
|||
bounding box
|
||||
- **upper_right** (*double[3]*) -- Upper-right coordinates of
|
||||
bounding box
|
||||
- **threshold** (*double*) -- Threshold used for volume uncertainty
|
||||
- **trigger_type** (*char[]*) -- Trigger type used for volume uncertainty
|
||||
|
||||
**/domain_<id>/**
|
||||
|
||||
|
|
|
|||
|
|
@ -538,7 +538,7 @@ Examples of CMFD simulations using OpenMC can be found in [HermanThesis]_.
|
|||
.. rubric:: References
|
||||
|
||||
.. [BEAVRS] Nick Horelik, Bryan Herman. *Benchmark for Evaluation And Verification of Reactor
|
||||
Simulations*. Massachusetts Institute of Technology, http://crpg.mit.edu/pub/beavrs
|
||||
Simulations*. Massachusetts Institute of Technology, https://crpg.mit.edu/research/beavrs
|
||||
, 2013.
|
||||
|
||||
.. [Gill] Daniel F. Gill. *Newton-Krylov methods for the solution of the k-eigenvalue problem in
|
||||
|
|
|
|||
|
|
@ -8,13 +8,14 @@ Cross Section Representations
|
|||
Continuous-Energy Data
|
||||
----------------------
|
||||
|
||||
The data governing the interaction of neutrons with
|
||||
various nuclei for continous-energy problems are represented using the ACE
|
||||
format which is used by MCNP_ and Serpent_. ACE-format data can be generated
|
||||
with the NJOY_ nuclear data processing system which converts raw
|
||||
`ENDF/B data`_ into linearly-interpolable data as required by most Monte Carlo
|
||||
codes. The use of a standard cross section format allows for a direct comparison
|
||||
of OpenMC with other codes since the same cross section libraries can be used.
|
||||
In OpenMC, the data governing the interaction of neutrons with various nuclei
|
||||
for continous-energy problems are represented using an HDF5 format that can be
|
||||
produced by converting files in the ACE format, which is used by MCNP_ and
|
||||
Serpent_. ACE-format data can be generated with the NJOY_ nuclear data
|
||||
processing system, which converts raw `ENDF/B data`_ into linearly-interpolable
|
||||
data as required by most Monte Carlo codes. Since ACE-format data can be
|
||||
converted into OpenMC's HDF5 format, it is possible to perform direct comparison
|
||||
of OpenMC with other codes using the same underlying nuclear data library.
|
||||
|
||||
The ACE format contains continuous-energy cross sections for the following types
|
||||
of reactions: elastic scattering, fission (or first-chance fission,
|
||||
|
|
@ -31,7 +32,7 @@ data can be used.
|
|||
Energy Grid Methods
|
||||
-------------------
|
||||
|
||||
The method by which continuous energy cross sections for each nuclide in a
|
||||
The method by which continuous-energy cross sections for each nuclide in a
|
||||
problem are stored as a function of energy can have a substantial effect on the
|
||||
performance of a Monte Carlo simulation. Since the ACE format is based on
|
||||
linearly-interpolable cross sections, each nuclide has cross sections tabulated
|
||||
|
|
@ -72,9 +73,9 @@ Windowed Multipole Representation
|
|||
---------------------------------
|
||||
|
||||
In addition to the usual pointwise representation of cross sections, OpenMC
|
||||
offers support for an experimental data format called windowed multipole (WMP).
|
||||
This data format requires less memory than pointwise cross sections, and it
|
||||
allows on-the-fly Doppler broadening to arbitrary temperature.
|
||||
offers support for a data format called windowed multipole (WMP). This data
|
||||
format requires less memory than pointwise cross sections, and it allows
|
||||
on-the-fly Doppler broadening to arbitrary temperature.
|
||||
|
||||
The multipole method was introduced by Hwang_ and the faster windowed multipole
|
||||
method by Josey_. In the multipole format, cross section resonances are
|
||||
|
|
@ -258,7 +259,7 @@ where a material has a very large cross sections relative to the other material
|
|||
used to minimize this error.
|
||||
|
||||
Finally, the above options for representing the physics do not have to be
|
||||
consistent across the problem. The number of groups and the structure, however,
|
||||
consistent across the problem. The number of groups and the structure, however,
|
||||
does have to be consistent across the data sets. That is to say that each
|
||||
microscopic or macroscopic data set does not have to apply the same scattering
|
||||
expansion, treatment of multiplicity or angular representation of the cross
|
||||
|
|
@ -269,11 +270,11 @@ or even isotropic scattering.
|
|||
.. _logarithmic mapping technique:
|
||||
https://laws.lanl.gov/vhosts/mcnp.lanl.gov/pdf_files/la-ur-14-24530.pdf
|
||||
.. _Hwang: http://www.ans.org/pubs/journals/nse/a_16381
|
||||
.. _Josey: http://dx.doi.org/10.1016/j.jcp.2015.08.013
|
||||
.. _Josey: https://doi.org/10.1016/j.jcp.2015.08.013
|
||||
.. _WMP Library: https://github.com/mit-crpg/WMP_Library
|
||||
.. _MCNP: http://mcnp.lanl.gov
|
||||
.. _Serpent: http://montecarlo.vtt.fi
|
||||
.. _NJOY: http://t2.lanl.gov/codes.shtml
|
||||
.. _ENDF/B data: http://www.nndc.bnl.gov/endf
|
||||
.. _Leppanen: http://dx.doi.org/10.1016/j.anucene.2009.03.019
|
||||
.. _Leppanen: https://doi.org/10.1016/j.anucene.2009.03.019
|
||||
.. _algorithms: http://ab-initio.mit.edu/wiki/index.php/Faddeeva_Package
|
||||
|
|
|
|||
149
docs/source/methods/energy_deposition.rst
Normal file
149
docs/source/methods/energy_deposition.rst
Normal file
|
|
@ -0,0 +1,149 @@
|
|||
.. _methods_heating:
|
||||
|
||||
=============================
|
||||
Heating and Energy Deposition
|
||||
=============================
|
||||
|
||||
As particles traverse a problem, some portion of their energy is deposited at
|
||||
collision sites. This energy is deposited when charged particles, including
|
||||
electrons and recoil nuclei, undergo electromagnetic interactions with
|
||||
surrounding electons and ions. The information describing how much energy
|
||||
is deposited for a specific reaction is referred to as
|
||||
"heating numbers" and can be computed using a program like NJOY with the
|
||||
``heatr`` module.
|
||||
|
||||
These heating rate is the product of reaction-specific coefficients and
|
||||
a reaction cross section
|
||||
|
||||
.. math::
|
||||
|
||||
H(E) = \phi(E)\sum_i\rho_i\sum_rk_{i, r}(E),
|
||||
|
||||
and has units energy per time, typically eV / s.
|
||||
Here, :math:`k_{i, r}` are the KERMA (Kinetic Energy Release in Materials)
|
||||
[Mack97]_ coefficients for reaction :math:`r` of isotope :math:`i`.
|
||||
The KERMA coefficients have units energy :math:`\times` cross-section, e.g.
|
||||
eV-barn, and can be used much like a reaction cross section for the purpose
|
||||
of tallying energy deposition.
|
||||
|
||||
KERMA coefficients can be computed using the energy-balance method with
|
||||
a nuclear data processing code like NJOY, which performs the following
|
||||
iteration over all reactions :math:`r` for all isotopes :math:`i`
|
||||
requested
|
||||
|
||||
.. math::
|
||||
|
||||
k_{i, r}(E) = \left(E + Q_{i, r} - \bar{E}_{i, r, n}
|
||||
- \bar{E}_{i, r, \gamma}\right)\sigma_{i, r}(E),
|
||||
|
||||
removing the energy of neutral particles (neutrons and photons) that are
|
||||
transported away from the reaction site :math:`\bar{E}`, and the reaction
|
||||
:math:`Q` value.
|
||||
|
||||
-------
|
||||
Fission
|
||||
-------
|
||||
|
||||
During a fission event, there are potentially many secondary particles, and all
|
||||
must be considered. The total energy released in a fission event is typically
|
||||
broken up into the following categories:
|
||||
|
||||
- :math:`E_{fr}` - kinetic energy of fission fragments
|
||||
- :math:`E_{n,p}` - energy of prompt fission neutrons
|
||||
- :math:`E_{n,d}` - energy of delayed fission neutrons
|
||||
- :math:`E_{\gamma,p}` - energy of prompt fission photons
|
||||
- :math:`E_{\gamma,d}` - energy of delayed fission photons
|
||||
- :math:`E_{\beta}` - energy of released :math:`\beta` particles
|
||||
- :math:`E_{\nu}` - energy of neutrinos
|
||||
|
||||
These components are defined in MF=1,MT=458 data in a standard ENDF/B-6 formatted
|
||||
file. All these quantities may depend upon incident neutron energy,
|
||||
but this dependence is not shown to make the following demonstrations cleaner.
|
||||
As neutrinos scarcely interact with matter, the recoverable energy from
|
||||
fission is defined as
|
||||
|
||||
.. math::
|
||||
|
||||
E_r\equiv E_{fr} + E_{n,p} + E_{n, d} + E_{\gamma, p}
|
||||
+ E_{\gamma, d} + E_{\beta}
|
||||
|
||||
Furthermore, the energy of the secondary neutrons and photons is given as
|
||||
:math:`E_{n, p}` and :math:`E_{\gamma, p}`, respectively.
|
||||
|
||||
NJOY computes the fission KERMA coefficient using this energy-balance method to be
|
||||
|
||||
.. math::
|
||||
|
||||
k_{i, f}(E) = \left[E + Q(E) - \bar{E}(E)\right]\sigma_{i, f}(E)
|
||||
= \left[E_{fr} + E_{\gamma, p}\right]\sigma_{i, j}(E)
|
||||
|
||||
.. note::
|
||||
|
||||
The energy from delayed neutrons and photons and beta particles is intentionally
|
||||
left out from the NJOY calculations.
|
||||
|
||||
---------------------
|
||||
OpenMC Implementation
|
||||
---------------------
|
||||
|
||||
For fissile isotopes, OpenMC makes modifications to the heating reaction to
|
||||
include all relevant components of fission energy release. These modifications
|
||||
are made to the total heating reaction, MT=301. Breaking the total heating
|
||||
KERMA into a fission and non-fission section, one can write
|
||||
|
||||
.. math::
|
||||
|
||||
k_i(E) = k_{i, nf}(E) + \left[E_{fr}(E) + E_{\gamma, p}\right]\sigma_{i, f}(E)
|
||||
|
||||
OpenMC seeks to modify the total heating data to include energy from
|
||||
:math:`\beta` particles and, conditionally, delayed photons. This conditional
|
||||
inclusion depends on the simulation mode: neutron transport, or coupled
|
||||
neutron-photon transport. The heating due to fission is removed using MT=318
|
||||
data, and then re-built using the desired components of fission energy release
|
||||
from MF=1,MT=458 data.
|
||||
|
||||
Neutron Transport
|
||||
-----------------
|
||||
|
||||
For this case, OpenMC instructs ``heatr`` to produce heating coefficients
|
||||
assuming that energy from photons, :math:`E_{\gamma, p}` and
|
||||
:math:`E_{\gamma, d}`, is deposited at the fission site.
|
||||
Let :math:`N901` represent the total heating number returned from this ``heatr``
|
||||
run with :math:`N918` reflecting fission heating computed from NJOY.
|
||||
:math:`M901` represent the following modification
|
||||
|
||||
.. math::
|
||||
|
||||
M901_{i}(E)\equiv N901_{i}(E) - N918_{i}(E)
|
||||
+ \left[E_{i, fr} + E_{i, \beta} + E_{i, \gamma, p}
|
||||
+ E_{i, \gamma, d}\right]\sigma_{i, f}(E).
|
||||
|
||||
This modified heating data is stored as the MT=901 reaction and will be scored
|
||||
if ``heating-local`` is included in :attr:`openmc.Tally.scores`.
|
||||
|
||||
Coupled neutron-photon transport
|
||||
--------------------------------
|
||||
|
||||
Here, OpenMC instructs ``heatr`` to assume that energy from photons is not
|
||||
deposited locally. However, the definitions provided in the NJOY manual
|
||||
indicate that, regardless of this mode, the prompt photon energy is still
|
||||
included in :math:`k_{i, f}`, and therefore must be manually removed.
|
||||
Let :math:`N301` represent the total heating number returned from this
|
||||
``heatr`` run and :math:`M301` be
|
||||
|
||||
.. math::
|
||||
|
||||
M301_{i}(E)\equiv N301_{i}(E) - N318_{i}(E)
|
||||
+ \left[E_{i, fr}(E) + E_{i, \beta}(E)\right]\sigma_{i, f}(E).
|
||||
|
||||
This modified heating data is stored as the MT=301 reaction and will be scored
|
||||
if ``heating`` is included in :attr:`openmc.Tally.scores`.
|
||||
|
||||
----------
|
||||
References
|
||||
----------
|
||||
|
||||
.. [Mack97] Abdou, M.A., Maynard, C.W., and Wright, R.Q. MACK: computer
|
||||
program to calculate neutron energy release parameters (fluence-to-kerma
|
||||
factors) and multigroup neutron reaction cross sections from nuclear data
|
||||
in ENDF Format. Oak Ridge National Laboratory report ORNL-TM-3994.
|
||||
|
|
@ -617,6 +617,10 @@ condition has been applied, the particle is killed and any surface current
|
|||
tallies are scored to as needed. If a reflective boundary condition has been
|
||||
applied to the surface, surface current tallies are scored to and then the
|
||||
particle's direction is changed according to the procedure in :ref:`reflection`.
|
||||
Note that the white boundary condition can be considered as the special case of
|
||||
reflective boundary condition, where the same processing method will be applied to
|
||||
deal with the surface current tallies scoring, except for determining the
|
||||
changes of particle's direction according to the procedures in :ref:`white`.
|
||||
|
||||
Next, we need to determine what cell is beyond the surface in the direction of
|
||||
travel of the particle so that we can evaluate cross sections based on its
|
||||
|
|
@ -892,8 +896,72 @@ Dxy + Eyz + Fxz + Gx + Hy + Jz + K = 0`. Thus, the gradient to the surface is
|
|||
\\ 2Cz + Ey + Fx + J \end{array} \right ).
|
||||
|
||||
|
||||
.. _constructive solid geometry: http://en.wikipedia.org/wiki/Constructive_solid_geometry
|
||||
.. _surfaces: http://en.wikipedia.org/wiki/Surface
|
||||
.. _white:
|
||||
|
||||
-------------------------
|
||||
White Boundary Conditions
|
||||
-------------------------
|
||||
|
||||
The `white boundary condition <https://doi.org/10.1016/j.anucene.2019.05.006>`_
|
||||
is usually applied in deterministic codes, where the particle will hit the
|
||||
surface and travel back with isotropic angular distribution. The change in
|
||||
particle's direction is sampled from a cosine distribution instead of uniform.
|
||||
Figure :num:`fig-cosine-dist` shows an example of cosine-distribution reflection
|
||||
on the arbitrary surface relative to the surface normal.
|
||||
|
||||
.. _fig-cosine-dist:
|
||||
|
||||
.. figure:: ../_images/cosine-dist.png
|
||||
:align: center
|
||||
:figclass: align-center
|
||||
|
||||
Cosine-distribution reflection on an arbitrary surface.
|
||||
|
||||
The probability density function (pdf) for the reflected direction can be
|
||||
expressed as follows,
|
||||
|
||||
.. math::
|
||||
:label: white-reflection-pdf
|
||||
|
||||
f(\mu, \phi) d\mu d\phi = \frac{\mu}{\pi} d\mu d\phi = 2\mu d\mu \frac{d\phi}{2\pi}
|
||||
|
||||
where :math:`\mu = \cos \theta` is the cosine of the polar angle between
|
||||
reflected direction and the normal to the surface; and :math:`\theta` is the
|
||||
azimuthal angle in :math:`[0,2\pi]`. We can separate the multivariate
|
||||
probability density into two separate univariate density functions, one for
|
||||
the cosine of the polar angle,
|
||||
|
||||
.. math::
|
||||
:label: white-reflection-cosine
|
||||
|
||||
f(\mu) = 2\mu
|
||||
|
||||
and one for the azimuthal angle,
|
||||
|
||||
.. math::
|
||||
:label: white-reflection-uniform
|
||||
|
||||
f(\phi) = \frac{1}{2\pi}.
|
||||
|
||||
Each of these density functions can be sampled by analytical inversion of the
|
||||
cumulative distribution distribution, resulting in the following sampling
|
||||
scheme:
|
||||
|
||||
.. math::
|
||||
:label: white-reflection-sqrt-prn
|
||||
|
||||
\mu = \sqrt{\xi_1} \\
|
||||
\phi = 2\pi\xi_2
|
||||
|
||||
where :math:`\xi_1` and :math:`\xi_2` are uniform random numbers on
|
||||
:math:`[0,1)`. With the sampled values of :math:`\mu` and :math:`\phi`, the
|
||||
final reflected direction vector can be computed via rotation of the surface
|
||||
normal using the equations from :ref:`transform-coordinates`. The white boundary
|
||||
condition can be applied to any kind of surface, as long as the normal to the
|
||||
surface is known as in :ref:`reflection`.
|
||||
|
||||
.. _constructive solid geometry: https://en.wikipedia.org/wiki/Constructive_solid_geometry
|
||||
.. _surfaces: https://en.wikipedia.org/wiki/Surface
|
||||
.. _MCNP: http://mcnp.lanl.gov
|
||||
.. _Serpent: http://montecarlo.vtt.fi
|
||||
.. _Monte Carlo Performance benchmark: https://github.com/mit-crpg/benchmarks/tree/master/mc-performance/openmc
|
||||
|
|
|
|||
|
|
@ -18,3 +18,4 @@ Theory and Methodology
|
|||
eigenvalue
|
||||
parallelization
|
||||
cmfd
|
||||
energy_deposition
|
||||
|
|
|
|||
|
|
@ -139,9 +139,9 @@ be performed before the run is finished. This include the following:
|
|||
|
||||
- If requested, a source file is written to disk.
|
||||
|
||||
- All allocatable arrays are deallocated.
|
||||
- Dynamically-allocated memory should be freed.
|
||||
|
||||
.. _probability distributions: http://en.wikipedia.org/wiki/Probability_distribution
|
||||
.. _Monte Carlo: http://en.wikipedia.org/wiki/Monte_Carlo_method
|
||||
.. _central limit theorem: http://en.wikipedia.org/wiki/Central_limit_theorem
|
||||
.. _pseudorandom number: http://en.wikipedia.org/wiki/Pseudorandom_number_generator
|
||||
.. _probability distributions: https://en.wikipedia.org/wiki/Probability_distribution
|
||||
.. _Monte Carlo: https://en.wikipedia.org/wiki/Monte_Carlo_method
|
||||
.. _central limit theorem: https://en.wikipedia.org/wiki/Central_limit_theorem
|
||||
.. _pseudorandom number: https://en.wikipedia.org/wiki/Pseudorandom_number_generator
|
||||
|
|
|
|||
|
|
@ -1298,11 +1298,10 @@ section over the range of velocities considered:
|
|||
where it should be noted that the maximum is taken over the range :math:`[v_n -
|
||||
4/\beta, 4_n + 4\beta]`. This method is known as Doppler broadening rejection
|
||||
correction (DBRC) and was first introduced by `Becker et al.`_. OpenMC has an
|
||||
implementation of DBRC as well as an accelerated sampling method that are
|
||||
described fully in `Walsh et al.`_
|
||||
implementation of DBRC as well as an accelerated sampling method that samples the `relative velocity`_ directly.
|
||||
|
||||
.. _Becker et al.: http://dx.doi.org/10.1016/j.anucene.2008.12.001
|
||||
.. _Walsh et al.: http://dx.doi.org/10.1016/j.anucene.2014.01.017
|
||||
.. _Becker et al.: https://doi.org/10.1016/j.anucene.2008.12.001
|
||||
.. _relative velocity: https://doi.org/10.1016/j.anucene.2017.12.044
|
||||
|
||||
.. _sab_tables:
|
||||
|
||||
|
|
@ -1645,23 +1644,23 @@ another.
|
|||
|
||||
.. |sab| replace:: S(:math:`\alpha,\beta,T`)
|
||||
|
||||
.. _SIGMA1 method: http://dx.doi.org/10.13182/NSE76-1
|
||||
.. _SIGMA1 method: https://doi.org/10.13182/NSE76-1
|
||||
|
||||
.. _scaled interpolation: http://www.ans.org/pubs/journals/nse/a_26575
|
||||
|
||||
.. _probability table method: http://dx.doi.org/10.13182/NSE72-3
|
||||
.. _probability table method: https://doi.org/10.13182/NSE72-3
|
||||
|
||||
.. _Watt fission spectrum: http://dx.doi.org/10.1103/PhysRev.87.1037
|
||||
.. _Watt fission spectrum: https://doi.org/10.1103/PhysRev.87.1037
|
||||
|
||||
.. _Foderaro: http://hdl.handle.net/1721.1/1716
|
||||
|
||||
.. _OECD: http://www.oecd-nea.org/dbprog/MMRW-BOOKS.html
|
||||
.. _OECD: http://www.oecd-nea.org/tools/abstract/detail/NEA-1792
|
||||
|
||||
.. _NJOY: https://njoy.github.io/NJOY2016/
|
||||
.. _NJOY: https://www.njoy21.io/NJOY2016/
|
||||
|
||||
.. _PREPRO: http://www-nds.iaea.org/ndspub/endf/prepro/
|
||||
|
||||
.. _ENDF-6 Format: http://www-nds.iaea.org/ndspub/documents/endf/endf102/endf102.pdf
|
||||
.. _ENDF-6 Format: https://www.oecd-nea.org/dbdata/data/manual-endf/endf102.pdf
|
||||
|
||||
.. _Monte Carlo Sampler: https://laws.lanl.gov/vhosts/mcnp.lanl.gov/pdf_files/la-9721.pdf
|
||||
|
||||
|
|
@ -1669,7 +1668,7 @@ another.
|
|||
|
||||
.. _MC21: http://www.osti.gov/bridge/servlets/purl/903083-HT5p1o/903083.pdf
|
||||
|
||||
.. _Romano: http://dx.doi.org/10.1016/j.cpc.2014.11.001
|
||||
.. _Romano: https://doi.org/10.1016/j.cpc.2014.11.001
|
||||
|
||||
.. _Sutton and Brown: http://www.osti.gov/bridge/product.biblio.jsp?osti_id=307911
|
||||
|
||||
|
|
|
|||
|
|
@ -607,33 +607,33 @@ is actually independent of the number of nodes:
|
|||
Radiation Penetration Calculations on a Parallel Computer,"
|
||||
*Trans. Am. Nucl. Soc.*, **17**, 260 (1973).
|
||||
|
||||
.. _first paper: http://www.jstor.org/stable/2280232
|
||||
.. _first paper: https://doi.org/10.2307/2280232
|
||||
|
||||
.. _work of Forrest Brown: http://hdl.handle.net/2027.42/24996
|
||||
|
||||
.. _Brissenden and Garlick: http://dx.doi.org/10.1016/0306-4549(86)90095-2
|
||||
.. _Brissenden and Garlick: https://doi.org/10.1016/0306-4549(86)90095-2
|
||||
|
||||
.. _MPICH2: http://www.mcs.anl.gov/mpi/mpich
|
||||
|
||||
.. _binomial tree: http://www.cs.auckland.ac.nz/~jmor159/PLDS210/trees.html
|
||||
.. _binomial tree: https://www.mcs.anl.gov/~thakur/papers/ijhpca-coll.pdf
|
||||
|
||||
.. _Geary: http://www.jstor.org/stable/10.2307/2342070
|
||||
.. _Geary: https://doi.org/10.2307/2342070
|
||||
|
||||
.. _Barnett: http://citeseerx.ist.psu.edu/viewdoc/summary?doi=10.1.1.51.7772
|
||||
|
||||
.. _single-instruction multiple-data: http://en.wikipedia.org/wiki/SIMD
|
||||
.. _single-instruction multiple-data: https://en.wikipedia.org/wiki/SIMD
|
||||
|
||||
.. _vector computers: http://en.wikipedia.org/wiki/Vector_processor
|
||||
.. _vector computers: https://en.wikipedia.org/wiki/Vector_processor
|
||||
|
||||
.. _single program multiple data: http://en.wikipedia.org/wiki/SPMD
|
||||
.. _single program multiple data: https://en.wikipedia.org/wiki/SPMD
|
||||
|
||||
.. _message-passing interface: http://en.wikipedia.org/wiki/Message_Passing_Interface
|
||||
.. _message-passing interface: https://en.wikipedia.org/wiki/Message_Passing_Interface
|
||||
|
||||
.. _PVM: http://www.csm.ornl.gov/pvm/pvm_home.html
|
||||
|
||||
.. _MPI: http://www.mcs.anl.gov/research/projects/mpi/
|
||||
|
||||
.. _embarrassingly parallel: http://en.wikipedia.org/wiki/Embarrassingly_parallel
|
||||
.. _embarrassingly parallel: https://en.wikipedia.org/wiki/Embarrassingly_parallel
|
||||
|
||||
.. _sends: http://www.mcs.anl.gov/research/projects/mpi/www/www3/MPI_Send.html
|
||||
|
||||
|
|
@ -643,8 +643,8 @@ is actually independent of the number of nodes:
|
|||
|
||||
.. _allgather: http://www.mcs.anl.gov/research/projects/mpi/www/www3/MPI_Allgather.html
|
||||
|
||||
.. _Cauchy distribution: http://en.wikipedia.org/wiki/Cauchy_distribution
|
||||
.. _Cauchy distribution: https://en.wikipedia.org/wiki/Cauchy_distribution
|
||||
|
||||
.. _latency: http://en.wikipedia.org/wiki/Latency_(engineering)#Packet-switched_networks
|
||||
.. _latency: https://en.wikipedia.org/wiki/Latency_(engineering)#Packet-switched_networks
|
||||
|
||||
.. _bandwidth: http://en.wikipedia.org/wiki/Bandwidth_(computing)
|
||||
.. _bandwidth: https://en.wikipedia.org/wiki/Bandwidth_(computing)
|
||||
|
|
|
|||
|
|
@ -579,7 +579,7 @@ sampled using the leading order term of the Sauter–Gluckstern–Hull
|
|||
distribution,
|
||||
|
||||
.. math::
|
||||
:label: sauter–gluckstern–hull
|
||||
:label: sauter-gluckstern-hull
|
||||
|
||||
p(\mu_{\pm}) = C(1 - \beta_{\pm}\mu_{\pm})^{-2},
|
||||
|
||||
|
|
@ -588,7 +588,7 @@ ratio of the velocity of the charged particle to the speed of light given in
|
|||
:eq:`beta-2`.
|
||||
|
||||
The inverse transform method is used to sample :math:`\mu_{-}` and
|
||||
:math:`\mu_{+}` from :eq:`sauter–gluckstern–hull`, using the sampling formula
|
||||
:math:`\mu_{+}` from :eq:`sauter-gluckstern-hull`, using the sampling formula
|
||||
|
||||
.. math::
|
||||
:label: sample-mu
|
||||
|
|
|
|||
|
|
@ -67,6 +67,6 @@ the idea is to determine the new multiplicative and additive constants in
|
|||
.. rubric:: References
|
||||
|
||||
|
||||
.. _L'Ecuyer: http://dx.doi.org/10.1090/S0025-5718-99-00996-5
|
||||
.. _L'Ecuyer: https://doi.org/10.1090/S0025-5718-99-00996-5
|
||||
.. _Brown: https://laws.lanl.gov/vhosts/mcnp.lanl.gov/pdf_files/anl-rn-arb-stride.pdf
|
||||
.. _linear congruential generator: http://en.wikipedia.org/wiki/Linear_congruential_generator
|
||||
.. _linear congruential generator: https://en.wikipedia.org/wiki/Linear_congruential_generator
|
||||
|
|
|
|||
|
|
@ -484,31 +484,31 @@ improve the estimate of the percentile.
|
|||
|
||||
.. rubric:: References
|
||||
|
||||
.. _following approximation: http://dx.doi.org/10.1080/03610918708812641
|
||||
.. _following approximation: https://doi.org/10.1080/03610918708812641
|
||||
|
||||
.. _Bessel's correction: http://en.wikipedia.org/wiki/Bessel's_correction
|
||||
.. _Bessel's correction: https://en.wikipedia.org/wiki/Bessel's_correction
|
||||
|
||||
.. _random variable: http://en.wikipedia.org/wiki/Random_variable
|
||||
.. _random variable: https://en.wikipedia.org/wiki/Random_variable
|
||||
|
||||
.. _stochastic process: http://en.wikipedia.org/wiki/Stochastic_process
|
||||
.. _stochastic process: https://en.wikipedia.org/wiki/Stochastic_process
|
||||
|
||||
.. _independent, identically-distributed random variables: http://en.wikipedia.org/wiki/Independent_and_identically_distributed_random_variables
|
||||
.. _independent, identically-distributed random variables: https://en.wikipedia.org/wiki/Independent_and_identically_distributed_random_variables
|
||||
|
||||
.. _law of large numbers: http://en.wikipedia.org/wiki/Law_of_large_numbers
|
||||
.. _law of large numbers: https://en.wikipedia.org/wiki/Law_of_large_numbers
|
||||
|
||||
.. _expected value: http://en.wikipedia.org/wiki/Expected_value
|
||||
.. _expected value: https://en.wikipedia.org/wiki/Expected_value
|
||||
|
||||
.. _converges in probability: http://en.wikipedia.org/wiki/Convergence_of_random_variables#Convergence_in_probability
|
||||
.. _converges in probability: https://en.wikipedia.org/wiki/Convergence_of_random_variables#Convergence_in_probability
|
||||
|
||||
.. _normal distribution: http://en.wikipedia.org/wiki/Normal_distribution
|
||||
.. _normal distribution: https://en.wikipedia.org/wiki/Normal_distribution
|
||||
|
||||
.. _converges in distribution: http://en.wikipedia.org/wiki/Convergence_of_random_variables#Convergence_in_distribution
|
||||
.. _converges in distribution: https://en.wikipedia.org/wiki/Convergence_of_random_variables#Convergence_in_distribution
|
||||
|
||||
.. _confidence intervals: http://en.wikipedia.org/wiki/Confidence_interval
|
||||
.. _confidence intervals: https://en.wikipedia.org/wiki/Confidence_interval
|
||||
|
||||
.. _Student's t-distribution: http://en.wikipedia.org/wiki/Student%27s_t-distribution
|
||||
.. _Student's t-distribution: https://en.wikipedia.org/wiki/Student%27s_t-distribution
|
||||
|
||||
.. _Cauchy distribution: http://en.wikipedia.org/wiki/Cauchy_distribution
|
||||
.. _Cauchy distribution: https://en.wikipedia.org/wiki/Cauchy_distribution
|
||||
|
||||
.. _unpublished rational approximation: https://web.archive.org/web/20150926021742/http://home.online.no/~pjacklam/notes/invnorm/
|
||||
|
||||
|
|
|
|||
|
|
@ -58,7 +58,8 @@ Coupling and Multi-physics
|
|||
--------------------------
|
||||
|
||||
- Miriam A. Kreher, Benoit Forget, and Kord Smith, "Single-Batch Monte Carlo
|
||||
Multiphysics Coupling," *Proc. M&C*, Portland, Oregon, Aug. 25-29 (2019).
|
||||
Multiphysics Coupling," *Proc. M&C*, 1789-1797, Portland, Oregon, Aug. 25-29
|
||||
(2019).
|
||||
|
||||
- Ze-Long Zhao, Yongwei Yang, and Shuang Hong, "`Application of FLUKA and OpenMC
|
||||
in coupled physics calculation of target and subcritical reactor for ADS
|
||||
|
|
@ -118,7 +119,7 @@ Geometry and Visualization
|
|||
|
||||
- Sterling Harper, Paul Romano, Benoit Forget, and Kord Smith, "Efficient
|
||||
dynamic threadsafe neighbor lists for Monte Carlo ray tracing," *Proc. M&C*,
|
||||
Portland, Oregon, Aug. 25-29 (2019).
|
||||
918-926, Portland, Oregon, Aug. 25-29 (2019).
|
||||
|
||||
- Jin-Yang Li, Long Gu, Hu-Shan Xu, Nadezha Korepanova, Rui Yu, Yan-Lei Zhu, and
|
||||
Chang-Ping Qin, "`CAD modeling study on FLUKA and OpenMC for accelerator
|
||||
|
|
@ -141,6 +142,10 @@ Geometry and Visualization
|
|||
Miscellaneous
|
||||
-------------
|
||||
|
||||
- Shikhar Kumar, Benoit Forget, and Kord Smith, "Analysis of fission source
|
||||
convergence for a 3-D SMR core using functional expansion tallies," *Proc.
|
||||
M&C*, 937-947, Portland, Oregon, Aug. 25-29 (2019).
|
||||
|
||||
- Faisal Qayyum, Muhammad R. Ali, Awais Zahur, and R. Khan, "`Improvements in
|
||||
methodology to determine feedback reactivity coefficients
|
||||
<https://doi.org/10.1007/s41365-019-0588-0>`_," *Nucl. Sci. Tech.*, **30**: 63
|
||||
|
|
@ -361,7 +366,7 @@ Nuclear Data
|
|||
- Jonathan A. Walsh, Benoit Forget, Kord S. Smith, and Forrest B. Brown,
|
||||
"`Uncertainty in Fast Reactor-Relevant Critical Benchmark Simulations Due to
|
||||
Unresolved Resonance Structure
|
||||
<https://www.kns.org/paper_file/paper/MC2017_2017_3/P197S03-09WalshJ.pdf>`_,"
|
||||
<https://www.kns.org/files/int_paper/paper/MC2017_2017_3/P197S03-09WalshJ.pdf>`_,"
|
||||
*Proc. Int. Conf. Mathematics & Computational Methods Applied to Nuclear
|
||||
Science and Engineering*, Jeju, Korea, Apr. 16-20, 2017.
|
||||
|
||||
|
|
@ -404,7 +409,7 @@ Parallelism
|
|||
|
||||
- Paul K. Romano and Andrew R. Siegel, "`Limits on the efficiency of event-based
|
||||
algorithms for Monte Carlo neutron transport
|
||||
<https://www.kns.org/paper_file/paper/MC2017_2017_2/P099S02-02RomanoP.pdf>`_,"
|
||||
<https://www.kns.org/files/int_paper/paper/MC2017_2017_2/P099S02-02RomanoP.pdf>`_,"
|
||||
*Proc. Int. Conf. Mathematics & Computational Methods Applied to Nuclear
|
||||
Science and Engineering*, Jeju, Korea, Apr. 16-20, 2017.
|
||||
|
||||
|
|
@ -496,7 +501,7 @@ Depletion
|
|||
|
||||
- Jose L. Salcedo-Perez, Benoit Forget, Kord Smith, and Paul Romano, "Hybrid
|
||||
tallies to improve performance in depletion Monte Carlo simulations," *Proc.
|
||||
M&C*, Aug. 25-29 (2019).
|
||||
M&C*, 927-936, Portland, Oregon, Aug. 25-29 (2019).
|
||||
|
||||
- Zhao-Qing Liu, Ze-Long Zhao, Yong-Wei Yang, Yu-Cui Gao, Hai-Yan Meng, and
|
||||
Qing-Yu Gao, "`Development and validation of depletion code system IMPC-Burnup
|
||||
|
|
@ -526,6 +531,10 @@ Depletion
|
|||
Sensitivity Analysis
|
||||
--------------------
|
||||
|
||||
- Abdulla Alhajri and Benoit Forget, "Eigenvalue Sensitivity in Monte Carlo
|
||||
Simulations to Nuclear Data Parameters using the Multipole Formalism," *Proc.
|
||||
M&C*, 1895-1906, Portland, Oregon, Aug. 25-29 (2019).
|
||||
|
||||
- Xingjie Peng, Jingang Liang, Benoit Forget, and Kord Smith, "`Calculation of
|
||||
adjoint-weighted reactor kinetics parameters in OpenMC
|
||||
<https://doi.org/10.1016/j.anucene.2019.01.007>`_", *Ann. Nucl. Energy*,
|
||||
|
|
|
|||
|
|
@ -1,8 +1,8 @@
|
|||
--------------------------------------------------
|
||||
:mod:`openmc.capi` -- Python bindings to the C API
|
||||
--------------------------------------------------
|
||||
------------------------------------------------------
|
||||
:mod:`openmc.lib` -- Python bindings to the C/C++ API
|
||||
------------------------------------------------------
|
||||
|
||||
.. automodule:: openmc.capi
|
||||
.. automodule:: openmc.lib
|
||||
|
||||
Functions
|
||||
---------
|
||||
|
|
|
|||
|
|
@ -2,6 +2,8 @@
|
|||
:mod:`openmc.data` -- Nuclear Data Interface
|
||||
--------------------------------------------
|
||||
|
||||
.. module:: openmc.data
|
||||
|
||||
Core Classes
|
||||
------------
|
||||
|
||||
|
|
@ -13,15 +15,15 @@ and product yields.
|
|||
:nosignatures:
|
||||
:template: myclass.rst
|
||||
|
||||
openmc.data.IncidentNeutron
|
||||
openmc.data.Reaction
|
||||
openmc.data.Product
|
||||
openmc.data.FissionEnergyRelease
|
||||
openmc.data.DataLibrary
|
||||
openmc.data.Decay
|
||||
openmc.data.FissionProductYields
|
||||
openmc.data.WindowedMultipole
|
||||
openmc.data.ProbabilityTables
|
||||
IncidentNeutron
|
||||
Reaction
|
||||
Product
|
||||
FissionEnergyRelease
|
||||
DataLibrary
|
||||
Decay
|
||||
FissionProductYields
|
||||
WindowedMultipole
|
||||
ProbabilityTables
|
||||
|
||||
The following classes are used for storing atomic data (incident photon cross
|
||||
sections, atomic relaxation):
|
||||
|
|
@ -31,9 +33,9 @@ sections, atomic relaxation):
|
|||
:nosignatures:
|
||||
:template: myclass.rst
|
||||
|
||||
openmc.data.IncidentPhoton
|
||||
openmc.data.PhotonReaction
|
||||
openmc.data.AtomicRelaxation
|
||||
IncidentPhoton
|
||||
PhotonReaction
|
||||
AtomicRelaxation
|
||||
|
||||
|
||||
The following classes are used for storing thermal neutron scattering data:
|
||||
|
|
@ -43,10 +45,10 @@ The following classes are used for storing thermal neutron scattering data:
|
|||
:nosignatures:
|
||||
:template: myclass.rst
|
||||
|
||||
openmc.data.ThermalScattering
|
||||
openmc.data.ThermalScatteringReaction
|
||||
openmc.data.CoherentElastic
|
||||
openmc.data.IncoherentElastic
|
||||
ThermalScattering
|
||||
ThermalScatteringReaction
|
||||
CoherentElastic
|
||||
IncoherentElastic
|
||||
|
||||
|
||||
Core Functions
|
||||
|
|
@ -57,12 +59,12 @@ Core Functions
|
|||
:nosignatures:
|
||||
:template: myfunction.rst
|
||||
|
||||
openmc.data.atomic_mass
|
||||
openmc.data.gnd_name
|
||||
openmc.data.linearize
|
||||
openmc.data.thin
|
||||
openmc.data.water_density
|
||||
openmc.data.zam
|
||||
atomic_mass
|
||||
gnd_name
|
||||
linearize
|
||||
thin
|
||||
water_density
|
||||
zam
|
||||
|
||||
One-dimensional Functions
|
||||
-------------------------
|
||||
|
|
@ -72,13 +74,13 @@ One-dimensional Functions
|
|||
:nosignatures:
|
||||
:template: myclass.rst
|
||||
|
||||
openmc.data.Function1D
|
||||
openmc.data.Tabulated1D
|
||||
openmc.data.Polynomial
|
||||
openmc.data.Combination
|
||||
openmc.data.Sum
|
||||
openmc.data.Regions1D
|
||||
openmc.data.ResonancesWithBackground
|
||||
Function1D
|
||||
Tabulated1D
|
||||
Polynomial
|
||||
Combination
|
||||
Sum
|
||||
Regions1D
|
||||
ResonancesWithBackground
|
||||
|
||||
Angle-Energy Distributions
|
||||
--------------------------
|
||||
|
|
@ -88,27 +90,27 @@ Angle-Energy Distributions
|
|||
:nosignatures:
|
||||
:template: myclass.rst
|
||||
|
||||
openmc.data.AngleEnergy
|
||||
openmc.data.KalbachMann
|
||||
openmc.data.CorrelatedAngleEnergy
|
||||
openmc.data.UncorrelatedAngleEnergy
|
||||
openmc.data.NBodyPhaseSpace
|
||||
openmc.data.LaboratoryAngleEnergy
|
||||
openmc.data.AngleDistribution
|
||||
openmc.data.EnergyDistribution
|
||||
openmc.data.ArbitraryTabulated
|
||||
openmc.data.GeneralEvaporation
|
||||
openmc.data.MaxwellEnergy
|
||||
openmc.data.Evaporation
|
||||
openmc.data.WattEnergy
|
||||
openmc.data.MadlandNix
|
||||
openmc.data.DiscretePhoton
|
||||
openmc.data.LevelInelastic
|
||||
openmc.data.ContinuousTabular
|
||||
openmc.data.CoherentElasticAE
|
||||
openmc.data.IncoherentElasticAE
|
||||
openmc.data.IncoherentElasticAEDiscrete
|
||||
openmc.data.IncoherentInelasticAEDiscrete
|
||||
AngleEnergy
|
||||
KalbachMann
|
||||
CorrelatedAngleEnergy
|
||||
UncorrelatedAngleEnergy
|
||||
NBodyPhaseSpace
|
||||
LaboratoryAngleEnergy
|
||||
AngleDistribution
|
||||
EnergyDistribution
|
||||
ArbitraryTabulated
|
||||
GeneralEvaporation
|
||||
MaxwellEnergy
|
||||
Evaporation
|
||||
WattEnergy
|
||||
MadlandNix
|
||||
DiscretePhoton
|
||||
LevelInelastic
|
||||
ContinuousTabular
|
||||
CoherentElasticAE
|
||||
IncoherentElasticAE
|
||||
IncoherentElasticAEDiscrete
|
||||
IncoherentInelasticAEDiscrete
|
||||
|
||||
Resonance Data
|
||||
--------------
|
||||
|
|
@ -118,20 +120,20 @@ Resonance Data
|
|||
:nosignatures:
|
||||
:template: myclass.rst
|
||||
|
||||
openmc.data.Resonances
|
||||
openmc.data.ResonanceRange
|
||||
openmc.data.SingleLevelBreitWigner
|
||||
openmc.data.MultiLevelBreitWigner
|
||||
openmc.data.ReichMoore
|
||||
openmc.data.RMatrixLimited
|
||||
openmc.data.ResonanceCovariances
|
||||
openmc.data.ResonanceCovarianceRange
|
||||
openmc.data.SingleLevelBreitWignerCovariance
|
||||
openmc.data.MultiLevelBreitWignerCovariance
|
||||
openmc.data.ReichMooreCovariance
|
||||
openmc.data.ParticlePair
|
||||
openmc.data.SpinGroup
|
||||
openmc.data.Unresolved
|
||||
Resonances
|
||||
ResonanceRange
|
||||
SingleLevelBreitWigner
|
||||
MultiLevelBreitWigner
|
||||
ReichMoore
|
||||
RMatrixLimited
|
||||
ResonanceCovariances
|
||||
ResonanceCovarianceRange
|
||||
SingleLevelBreitWignerCovariance
|
||||
MultiLevelBreitWignerCovariance
|
||||
ReichMooreCovariance
|
||||
ParticlePair
|
||||
SpinGroup
|
||||
Unresolved
|
||||
|
||||
ACE Format
|
||||
----------
|
||||
|
|
@ -144,8 +146,8 @@ Classes
|
|||
:nosignatures:
|
||||
:template: myclass.rst
|
||||
|
||||
openmc.data.ace.Library
|
||||
openmc.data.ace.Table
|
||||
ace.Library
|
||||
ace.Table
|
||||
|
||||
Functions
|
||||
+++++++++
|
||||
|
|
@ -155,7 +157,7 @@ Functions
|
|||
:nosignatures:
|
||||
:template: myfunction.rst
|
||||
|
||||
openmc.data.ace.ascii_to_binary
|
||||
ace.ascii_to_binary
|
||||
|
||||
ENDF Format
|
||||
-----------
|
||||
|
|
@ -168,7 +170,7 @@ Classes
|
|||
:nosignatures:
|
||||
:template: myclass.rst
|
||||
|
||||
openmc.data.endf.Evaluation
|
||||
endf.Evaluation
|
||||
|
||||
Functions
|
||||
+++++++++
|
||||
|
|
@ -178,13 +180,13 @@ Functions
|
|||
:nosignatures:
|
||||
:template: myfunction.rst
|
||||
|
||||
openmc.data.endf.float_endf
|
||||
openmc.data.endf.get_cont_record
|
||||
openmc.data.endf.get_evaluations
|
||||
openmc.data.endf.get_head_record
|
||||
openmc.data.endf.get_tab1_record
|
||||
openmc.data.endf.get_tab2_record
|
||||
openmc.data.endf.get_text_record
|
||||
endf.float_endf
|
||||
endf.get_cont_record
|
||||
endf.get_evaluations
|
||||
endf.get_head_record
|
||||
endf.get_tab1_record
|
||||
endf.get_tab2_record
|
||||
endf.get_text_record
|
||||
|
||||
NJOY Interface
|
||||
--------------
|
||||
|
|
@ -194,7 +196,7 @@ NJOY Interface
|
|||
:nosignatures:
|
||||
:template: myfunction.rst
|
||||
|
||||
openmc.data.njoy.run
|
||||
openmc.data.njoy.make_pendf
|
||||
openmc.data.njoy.make_ace
|
||||
openmc.data.njoy.make_ace_thermal
|
||||
njoy.run
|
||||
njoy.make_pendf
|
||||
njoy.make_ace
|
||||
njoy.make_ace_thermal
|
||||
|
|
|
|||
|
|
@ -1,12 +1,27 @@
|
|||
.. _pythonapi_deplete:
|
||||
|
||||
.. module:: openmc.deplete
|
||||
|
||||
----------------------------------
|
||||
:mod:`openmc.deplete` -- Depletion
|
||||
----------------------------------
|
||||
|
||||
.. module:: openmc.deplete
|
||||
Primary API
|
||||
-----------
|
||||
|
||||
Several classes are provided that implement different time-integration
|
||||
The two primary requirements to perform depletion with :mod:`openmc.deplete`
|
||||
are:
|
||||
|
||||
1) A transport operator
|
||||
2) A time-integration scheme
|
||||
|
||||
The former is responsible for executing a transport code, like OpenMC,
|
||||
and retaining important information required for depletion. The most common examples
|
||||
are reaction rates and power normalization data. The latter is responsible for
|
||||
projecting reaction rates and compositions forward in calendar time across
|
||||
some step size :math:`\Delta t`, and obtaining new compositions given a power
|
||||
or power density. The :class:`Operator` is provided to handle communicating with
|
||||
OpenMC. Several classes are provided that implement different time-integration
|
||||
algorithms for depletion calculations, which are described in detail in Colin
|
||||
Josey's thesis, `Development and analysis of high order neutron
|
||||
transport-depletion coupling algorithms <http://hdl.handle.net/1721.1/113721>`_.
|
||||
|
|
@ -31,14 +46,46 @@ specific to OpenMC is available using the following class:
|
|||
.. autosummary::
|
||||
:toctree: generated
|
||||
:nosignatures:
|
||||
:template: myclass.rst
|
||||
:template: mycallable.rst
|
||||
|
||||
Operator
|
||||
|
||||
When running in parallel using `mpi4py <http://mpi4py.scipy.org>`_, the MPI
|
||||
intercommunicator used can be changed by modifying the following module
|
||||
variable. If it is not explicitly modified, it defaults to
|
||||
``mpi4py.MPI.COMM_WORLD``.
|
||||
The :class:`Operator` must also have some knowledge of how nuclides transmute
|
||||
and decay. This is handled by the :class:`Chain`.
|
||||
|
||||
Minimal Example
|
||||
---------------
|
||||
|
||||
A minimal example for performing depletion would be:
|
||||
|
||||
.. code::
|
||||
|
||||
>>> import openmc
|
||||
>>> import openmc.deplete
|
||||
>>> geometry = openmc.Geometry.from_xml()
|
||||
>>> settings = openmc.Settings.from_xml()
|
||||
|
||||
# Representation of a depletion chain
|
||||
>>> chain_file = "chain_casl.xml"
|
||||
>>> operator = openmc.deplete.Operator(
|
||||
... geometry, settings, chain_file)
|
||||
|
||||
# Set up 5 time steps of one day each
|
||||
>>> dt = [24 * 60 * 60] * 5
|
||||
>>> power = 1e6 # constant power of 1 MW
|
||||
|
||||
# Deplete using mid-point predictor-corrector
|
||||
>>> cecm = openmc.deplete.CECMIntegrator(
|
||||
... operator, dt, power)
|
||||
>>> cecm.integrate()
|
||||
|
||||
Internal Classes and Functions
|
||||
------------------------------
|
||||
|
||||
When running in parallel using `mpi4py
|
||||
<https://mpi4py.readthedocs.io/en/stable/>`_, the MPI intercommunicator used can
|
||||
be changed by modifying the following module variable. If it is not explicitly
|
||||
modified, it defaults to ``mpi4py.MPI.COMM_WORLD``.
|
||||
|
||||
.. data:: comm
|
||||
|
||||
|
|
@ -46,9 +93,6 @@ variable. If it is not explicitly modified, it defaults to
|
|||
|
||||
:type: mpi4py.MPI.Comm
|
||||
|
||||
Internal Classes and Functions
|
||||
------------------------------
|
||||
|
||||
During a depletion calculation, the depletion chain, reaction rates, and number
|
||||
densities are managed through a series of internal classes that are not normally
|
||||
visible to a user. However, should you find yourself wondering about these
|
||||
|
|
@ -82,6 +126,26 @@ data, such as number densities and reaction rates for each material.
|
|||
Results
|
||||
ResultsList
|
||||
|
||||
The following class and functions are used to solve the depletion equations,
|
||||
with :func:`cram.CRAM48` being the default.
|
||||
|
||||
.. autosummary::
|
||||
:toctree: generated
|
||||
:nosignatures:
|
||||
:template: myintegrator.rst
|
||||
|
||||
cram.IPFCramSolver
|
||||
|
||||
.. autosummary::
|
||||
:toctree: generated
|
||||
:nosignatures:
|
||||
:template: myfunction.rst
|
||||
|
||||
cram.CRAM16
|
||||
cram.CRAM48
|
||||
cram.deplete
|
||||
cram.timed_deplete
|
||||
|
||||
The following classes are used to help the :class:`openmc.deplete.Operator`
|
||||
compute quantities like effective fission yields, reaction rates, and
|
||||
total system energy.
|
||||
|
|
@ -95,40 +159,47 @@ total system energy.
|
|||
helpers.ChainFissionHelper
|
||||
helpers.ConstantFissionYieldHelper
|
||||
helpers.DirectReactionRateHelper
|
||||
helpers.EnergyScoreHelper
|
||||
helpers.FissionYieldCutoffHelper
|
||||
|
||||
The following classes are abstract classes that can be used to extend the
|
||||
:mod:`openmc.deplete` capabilities:
|
||||
|
||||
Abstract Base Classes
|
||||
---------------------
|
||||
|
||||
A good starting point for extending capabilities in :mod:`openmc.deplete` is
|
||||
to examine the following abstract base classes. Custom classes can
|
||||
inherit from :class:`abc.TransportOperator` to implement alternative
|
||||
schemes for collecting reaction rates and other data from a transport code
|
||||
prior to depleting materials
|
||||
|
||||
.. autosummary::
|
||||
:toctree: generated
|
||||
:nosignatures:
|
||||
:template: mycallable.rst
|
||||
|
||||
abc.TransportOperator
|
||||
|
||||
The following classes are abstract classes used to pass information from
|
||||
OpenMC simulations back on to the :class:`abc.TransportOperator`
|
||||
|
||||
.. autosummary::
|
||||
:toctree: generated
|
||||
:nosignatures:
|
||||
:template: myclass.rst
|
||||
|
||||
EnergyHelper
|
||||
FissionYieldHelper
|
||||
ReactionRateHelper
|
||||
TalliedFissionYieldHelper
|
||||
TransportOperator
|
||||
abc.EnergyHelper
|
||||
abc.FissionYieldHelper
|
||||
abc.ReactionRateHelper
|
||||
abc.TalliedFissionYieldHelper
|
||||
|
||||
Custom integrators can be developed by subclassing from the following abstract
|
||||
base classes:
|
||||
Custom integrators or depletion solvers can be developed by subclassing from
|
||||
the following abstract base classes:
|
||||
|
||||
.. autosummary::
|
||||
:toctree: generated
|
||||
:nosignatures:
|
||||
:template: myintegrator.rst
|
||||
|
||||
Integrator
|
||||
SIIntegrator
|
||||
|
||||
Each of the integrator classes also relies on a number of "helper" functions
|
||||
as follows:
|
||||
|
||||
.. autosummary::
|
||||
:toctree: generated
|
||||
:nosignatures:
|
||||
:template: myfunction.rst
|
||||
|
||||
cram.CRAM16
|
||||
cram.CRAM48
|
||||
abc.Integrator
|
||||
abc.SIIntegrator
|
||||
abc.DepSystemSolver
|
||||
|
|
|
|||
|
|
@ -27,7 +27,7 @@ there are many substantial benefits to using the Python API, including:
|
|||
|
||||
For those new to Python, there are many good tutorials available online. We
|
||||
recommend going through the modules from `Codecademy
|
||||
<https://www.codecademy.com/tracks/python>`_ and/or the `Scipy lectures
|
||||
<https://www.codecademy.com/learn/learn-python-3>`_ and/or the `Scipy lectures
|
||||
<https://scipy-lectures.github.io/>`_.
|
||||
|
||||
The full API documentation serves to provide more information on a given module
|
||||
|
|
|
|||
|
|
@ -2,11 +2,6 @@
|
|||
What's New in 0.11.0
|
||||
====================
|
||||
|
||||
.. note::
|
||||
These release notes are for a future release of OpenMC and are still subject
|
||||
to change. The new features and bug fixes documented here reflect the
|
||||
current status of the ``develop`` branch of OpenMC.
|
||||
|
||||
.. currentmodule:: openmc
|
||||
|
||||
-------
|
||||
|
|
@ -17,7 +12,7 @@ This release of OpenMC adds several major new features: :ref:`depletion
|
|||
<usersguide_depletion>`, photon transport, and support for CAD geometries
|
||||
through DAGMC. In addition, the core codebase has been rewritten in C++14 (it
|
||||
was previously written in Fortran 2008). This makes compiling the code
|
||||
cosiderably simpler as no Fortran compiler is needed.
|
||||
considerably simpler as no Fortran compiler is needed.
|
||||
|
||||
Functional expansion tallies are now supported through several new tally filters
|
||||
that can be arbitrarily combined:
|
||||
|
|
@ -40,13 +35,16 @@ random, non-overlapping configuration of spheres within the region.
|
|||
New Features
|
||||
------------
|
||||
|
||||
- White boundary conditions can be applied to surfaces
|
||||
- Support for rectilinear meshes through :class:`openmc.RectilinearMesh`.
|
||||
- The :class:`Geometry`, :class:`Materials`, and :class:`Settings` classes now
|
||||
have a ``from_xml`` method that will build an instance from an existing XML
|
||||
file.
|
||||
- Predefined energy group structures can be found in
|
||||
:data:`openmc.mgxs.GROUP_STRUCTURES`.
|
||||
- New tally scores: ``H1-production``, ``H2-production``, ``H3-production``,
|
||||
``He3-production``, ``He4-production``, ``heating``, and ``damage-energy``
|
||||
``He3-production``, ``He4-production``, ``heating``, ``heating-local``, and
|
||||
``damage-energy``.
|
||||
- Switched to cell-based neighor lists (`PR 1140
|
||||
<https://github.com/openmc-dev/openmc/pull/1140>`_)
|
||||
- Two new probability distributions that can be used for source distributions:
|
||||
|
|
@ -54,11 +52,40 @@ New Features
|
|||
- The :mod:`openmc.data` module now supports reading and sampling from ENDF File
|
||||
32 resonance covariance data (`PR 1024
|
||||
<https://github.com/openmc-dev/openmc/pull/1024>`_).
|
||||
- Several new convenience functions/methods have been added:
|
||||
|
||||
- The :func:`openmc.model.cylinder_from_points` function creates a cylinder
|
||||
given two points passing through its center and a radius.
|
||||
- The :meth:`openmc.Plane.from_points` function creates a plane given three
|
||||
points that pass through it.
|
||||
- The :func:`openmc.model.pin` function creates a pin cell universe given a
|
||||
sequence of concentric cylinders and materials.
|
||||
|
||||
------------------
|
||||
Python API Changes
|
||||
------------------
|
||||
|
||||
- All surface classes now have coefficient arguments given as lowercase names.
|
||||
- The order of arguments in surface classes has been changed so that
|
||||
coefficients are the first arguments (rather than the optional surface ID).
|
||||
This means you can now write::
|
||||
|
||||
x = openmc.XPlane(5.0, 'reflective')
|
||||
zc = openmc.ZCylinder(0., 0., 10.)
|
||||
|
||||
- The ``Mesh`` class has been renamed :class:`openmc.RegularMesh`.
|
||||
- The ``get_rectangular_prism`` function has been renamed
|
||||
:func:`openmc.model.rectangular_prism`.
|
||||
- The ``get_hexagonal_prism`` function has been renamed
|
||||
:func:`openmc.model.hexagonal_prism`.
|
||||
- Python bindings to the C/C++ API have been move from ``openmc.capi`` to
|
||||
:mod:`openmc.lib`.
|
||||
|
||||
---------
|
||||
Bug Fixes
|
||||
---------
|
||||
|
||||
- `Rotate azimuthal distributions correctly for source sampling <https://github.com/openmc-dev/openmc/pull/1363>`_
|
||||
- `Fix reading ASCII ACE tables in Python 3 <https://github.com/openmc-dev/openmc/pull/1176>`_
|
||||
- `Fix bug for distributed temperatures <https://github.com/openmc-dev/openmc/pull/1178>`_
|
||||
- `Fix bug for distance to boundary in complex cells <https://github.com/openmc-dev/openmc/pull/1172>`_
|
||||
|
|
@ -77,6 +104,7 @@ This release contains new contributions from the following people:
|
|||
- `Brody Bassett <https://github.com/brbass>`_
|
||||
- `Will Boyd <https://github.com/wbinventor>`_
|
||||
- `Andrew Davis <https://github.com/makeclean>`_
|
||||
- `Iurii Drobyshev <https://github.com/dryuri92>`_
|
||||
- `Guillaume Giudicelli <https://github.com/GiudGiud>`_
|
||||
- `Brittany Grayson <https://github.com/graybri3>`_
|
||||
- `Zhuoran Han <https://github.com/hanzhuoran>`_
|
||||
|
|
@ -94,9 +122,12 @@ This release contains new contributions from the following people:
|
|||
- `Isaac Meyer <https://github.com/icmeyer>`_
|
||||
- `April Novak <https://github.com/aprilnovak>`_
|
||||
- `Adam Nelson <https://github.com/nelsonag>`_
|
||||
- `Gavin Ridley <https://github.com/gridley>`_
|
||||
- `Jose Salcedo Perez <https://github.com/salcedop>`_
|
||||
- `Paul Romano <https://github.com/paulromano>`_
|
||||
- `Sam Shaner <https://github.com/samuelshaner>`_
|
||||
- `Jonathan Shimwell <https://github.com/Shimwell>`_
|
||||
- `Patrick Shriwise <https://github.com/pshriwise>`_
|
||||
- `John Tramm <https://github.com/jtramm>`_
|
||||
- `Jiankai Yu <https://github.com/rockfool>`_
|
||||
- `Xiaokang Zhang <https://github.com/zxkjack123>`_
|
||||
|
|
|
|||
|
|
@ -45,9 +45,9 @@ Bug Fixes
|
|||
- `95cfac`_: Fixed error in cell neighbor searches.
|
||||
- `83a803`_: Fixed bug related to probability tables.
|
||||
|
||||
.. _b206a8: https://github.com/mit-crpg/openmc/commit/b206a8
|
||||
.. _800742: https://github.com/mit-crpg/openmc/commit/800742
|
||||
.. _a07c08: https://github.com/mit-crpg/openmc/commit/a07c08
|
||||
.. _a75283: https://github.com/mit-crpg/openmc/commit/a75283
|
||||
.. _95cfac: https://github.com/mit-crpg/openmc/commit/95cfac
|
||||
.. _83a803: https://github.com/mit-crpg/openmc/commit/83a803
|
||||
.. _b206a8: https://github.com/openmc-dev/openmc/commit/b206a8
|
||||
.. _800742: https://github.com/openmc-dev/openmc/commit/800742
|
||||
.. _a07c08: https://github.com/openmc-dev/openmc/commit/a07c08
|
||||
.. _a75283: https://github.com/openmc-dev/openmc/commit/a75283
|
||||
.. _95cfac: https://github.com/openmc-dev/openmc/commit/95cfac
|
||||
.. _83a803: https://github.com/openmc-dev/openmc/commit/83a803
|
||||
|
|
|
|||
|
|
@ -42,13 +42,13 @@ Bug Fixes
|
|||
- d050c7_: Added Bessel's correction to make estimate of variance unbiased.
|
||||
- 2a5b9c_: Fixed regression in plotting.
|
||||
|
||||
.. _a27f8f: https://github.com/mit-crpg/openmc/commit/a27f8f
|
||||
.. _afe121: https://github.com/mit-crpg/openmc/commit/afe121
|
||||
.. _e0968e: https://github.com/mit-crpg/openmc/commit/e0968e
|
||||
.. _298db8: https://github.com/mit-crpg/openmc/commit/298db8
|
||||
.. _2f3bbe: https://github.com/mit-crpg/openmc/commit/2f3bbe
|
||||
.. _671f30: https://github.com/mit-crpg/openmc/commit/671f30
|
||||
.. _b2c40e: https://github.com/mit-crpg/openmc/commit/b2c40e
|
||||
.. _5524fd: https://github.com/mit-crpg/openmc/commit/5524fd
|
||||
.. _d050c7: https://github.com/mit-crpg/openmc/commit/d050c7
|
||||
.. _2a5b9c: https://github.com/mit-crpg/openmc/commit/2a5b9c
|
||||
.. _a27f8f: https://github.com/openmc-dev/openmc/commit/a27f8f
|
||||
.. _afe121: https://github.com/openmc-dev/openmc/commit/afe121
|
||||
.. _e0968e: https://github.com/openmc-dev/openmc/commit/e0968e
|
||||
.. _298db8: https://github.com/openmc-dev/openmc/commit/298db8
|
||||
.. _2f3bbe: https://github.com/openmc-dev/openmc/commit/2f3bbe
|
||||
.. _671f30: https://github.com/openmc-dev/openmc/commit/671f30
|
||||
.. _b2c40e: https://github.com/openmc-dev/openmc/commit/b2c40e
|
||||
.. _5524fd: https://github.com/openmc-dev/openmc/commit/5524fd
|
||||
.. _d050c7: https://github.com/openmc-dev/openmc/commit/d050c7
|
||||
.. _2a5b9c: https://github.com/openmc-dev/openmc/commit/2a5b9c
|
||||
|
|
|
|||
|
|
@ -40,12 +40,12 @@ Bug Fixes
|
|||
- 3212f5_: Fixed issue with blank line at beginning of XML files.
|
||||
|
||||
.. _nelsonag: https://github.com/nelsonag
|
||||
.. _33f29a: https://github.com/mit-crpg/openmc/commit/33f29a
|
||||
.. _1c472d: https://github.com/mit-crpg/openmc/commit/1c472d
|
||||
.. _3c6e80: https://github.com/mit-crpg/openmc/commit/3c6e80
|
||||
.. _3bd35b: https://github.com/mit-crpg/openmc/commit/3bd35b
|
||||
.. _0069d5: https://github.com/mit-crpg/openmc/commit/0069d5
|
||||
.. _7af2cf: https://github.com/mit-crpg/openmc/commit/7af2cf
|
||||
.. _460ef1: https://github.com/mit-crpg/openmc/commit/460ef1
|
||||
.. _85a60e: https://github.com/mit-crpg/openmc/commit/85a60e
|
||||
.. _3212f5: https://github.com/mit-crpg/openmc/commit/3212f5
|
||||
.. _33f29a: https://github.com/openmc-dev/openmc/commit/33f29a
|
||||
.. _1c472d: https://github.com/openmc-dev/openmc/commit/1c472d
|
||||
.. _3c6e80: https://github.com/openmc-dev/openmc/commit/3c6e80
|
||||
.. _3bd35b: https://github.com/openmc-dev/openmc/commit/3bd35b
|
||||
.. _0069d5: https://github.com/openmc-dev/openmc/commit/0069d5
|
||||
.. _7af2cf: https://github.com/openmc-dev/openmc/commit/7af2cf
|
||||
.. _460ef1: https://github.com/openmc-dev/openmc/commit/460ef1
|
||||
.. _85a60e: https://github.com/openmc-dev/openmc/commit/85a60e
|
||||
.. _3212f5: https://github.com/openmc-dev/openmc/commit/3212f5
|
||||
|
|
|
|||
|
|
@ -36,8 +36,8 @@ Bug Fixes
|
|||
- 7fd617_: Fixed bug with restart runs in parallel.
|
||||
- dc4a8f_: Fixed bug with fixed source restart runs.
|
||||
|
||||
.. _4654ee: https://github.com/mit-crpg/openmc/commit/4654ee
|
||||
.. _7ee461: https://github.com/mit-crpg/openmc/commit/7ee461
|
||||
.. _792eb3: https://github.com/mit-crpg/openmc/commit/792eb3
|
||||
.. _7fd617: https://github.com/mit-crpg/openmc/commit/7fd617
|
||||
.. _dc4a8f: https://github.com/mit-crpg/openmc/commit/dc4a8f
|
||||
.. _4654ee: https://github.com/openmc-dev/openmc/commit/4654ee
|
||||
.. _7ee461: https://github.com/openmc-dev/openmc/commit/7ee461
|
||||
.. _792eb3: https://github.com/openmc-dev/openmc/commit/792eb3
|
||||
.. _7fd617: https://github.com/openmc-dev/openmc/commit/7fd617
|
||||
.. _dc4a8f: https://github.com/openmc-dev/openmc/commit/dc4a8f
|
||||
|
|
|
|||
|
|
@ -39,11 +39,11 @@ Bug Fixes
|
|||
- 6f8d9d_: Set default tally labels.
|
||||
- 6a3a5e_: Fix problem with corner-crossing in lattices.
|
||||
|
||||
.. _737b90: https://github.com/mit-crpg/openmc/commit/737b90
|
||||
.. _a819b4: https://github.com/mit-crpg/openmc/commit/a819b4
|
||||
.. _b11696: https://github.com/mit-crpg/openmc/commit/b11696
|
||||
.. _2bd46a: https://github.com/mit-crpg/openmc/commit/2bd46a
|
||||
.. _7a1f08: https://github.com/mit-crpg/openmc/commit/7a1f08
|
||||
.. _c0e3ec: https://github.com/mit-crpg/openmc/commit/c0e3ec
|
||||
.. _6f8d9d: https://github.com/mit-crpg/openmc/commit/6f8d9d
|
||||
.. _6a3a5e: https://github.com/mit-crpg/openmc/commit/6a3a5e
|
||||
.. _737b90: https://github.com/openmc-dev/openmc/commit/737b90
|
||||
.. _a819b4: https://github.com/openmc-dev/openmc/commit/a819b4
|
||||
.. _b11696: https://github.com/openmc-dev/openmc/commit/b11696
|
||||
.. _2bd46a: https://github.com/openmc-dev/openmc/commit/2bd46a
|
||||
.. _7a1f08: https://github.com/openmc-dev/openmc/commit/7a1f08
|
||||
.. _c0e3ec: https://github.com/openmc-dev/openmc/commit/c0e3ec
|
||||
.. _6f8d9d: https://github.com/openmc-dev/openmc/commit/6f8d9d
|
||||
.. _6a3a5e: https://github.com/openmc-dev/openmc/commit/6a3a5e
|
||||
|
|
|
|||
|
|
@ -36,8 +36,8 @@ Bug Fixes
|
|||
- 63bfd2_: Fix tracklength tallies with cell filter and universes.
|
||||
- 88daf7_: Fix analog tallies with survival biasing.
|
||||
|
||||
.. _94103e: https://github.com/mit-crpg/openmc/commit/94103e
|
||||
.. _e77059: https://github.com/mit-crpg/openmc/commit/e77059
|
||||
.. _b0fe88: https://github.com/mit-crpg/openmc/commit/b0fe88
|
||||
.. _63bfd2: https://github.com/mit-crpg/openmc/commit/63bfd2
|
||||
.. _88daf7: https://github.com/mit-crpg/openmc/commit/88daf7
|
||||
.. _94103e: https://github.com/openmc-dev/openmc/commit/94103e
|
||||
.. _e77059: https://github.com/openmc-dev/openmc/commit/e77059
|
||||
.. _b0fe88: https://github.com/openmc-dev/openmc/commit/b0fe88
|
||||
.. _63bfd2: https://github.com/openmc-dev/openmc/commit/63bfd2
|
||||
.. _88daf7: https://github.com/openmc-dev/openmc/commit/88daf7
|
||||
|
|
|
|||
|
|
@ -41,15 +41,15 @@ Bug Fixes
|
|||
- ab0793_: Corrected PETSC_NULL references to their correct types.
|
||||
- 182ebd_: Use analog estimator with energyout filter.
|
||||
|
||||
.. _7632f3: https://github.com/mit-crpg/openmc/commit/7632f3
|
||||
.. _f85ac4: https://github.com/mit-crpg/openmc/commit/f85ac4
|
||||
.. _49c36b: https://github.com/mit-crpg/openmc/commit/49c36b
|
||||
.. _5ccc78: https://github.com/mit-crpg/openmc/commit/5ccc78
|
||||
.. _b1f52f: https://github.com/mit-crpg/openmc/commit/b1f52f
|
||||
.. _eae7e5: https://github.com/mit-crpg/openmc/commit/eae7e5
|
||||
.. _10c1cc: https://github.com/mit-crpg/openmc/commit/10c1cc
|
||||
.. _afdb50: https://github.com/mit-crpg/openmc/commit/afdb50
|
||||
.. _a3c593: https://github.com/mit-crpg/openmc/commit/a3c593
|
||||
.. _3a66e3: https://github.com/mit-crpg/openmc/commit/3a66e3
|
||||
.. _ab0793: https://github.com/mit-crpg/openmc/commit/ab0793
|
||||
.. _182ebd: https://github.com/mit-crpg/openmc/commit/182ebd
|
||||
.. _7632f3: https://github.com/openmc-dev/openmc/commit/7632f3
|
||||
.. _f85ac4: https://github.com/openmc-dev/openmc/commit/f85ac4
|
||||
.. _49c36b: https://github.com/openmc-dev/openmc/commit/49c36b
|
||||
.. _5ccc78: https://github.com/openmc-dev/openmc/commit/5ccc78
|
||||
.. _b1f52f: https://github.com/openmc-dev/openmc/commit/b1f52f
|
||||
.. _eae7e5: https://github.com/openmc-dev/openmc/commit/eae7e5
|
||||
.. _10c1cc: https://github.com/openmc-dev/openmc/commit/10c1cc
|
||||
.. _afdb50: https://github.com/openmc-dev/openmc/commit/afdb50
|
||||
.. _a3c593: https://github.com/openmc-dev/openmc/commit/a3c593
|
||||
.. _3a66e3: https://github.com/openmc-dev/openmc/commit/3a66e3
|
||||
.. _ab0793: https://github.com/openmc-dev/openmc/commit/ab0793
|
||||
.. _182ebd: https://github.com/openmc-dev/openmc/commit/182ebd
|
||||
|
|
|
|||
|
|
@ -40,8 +40,8 @@ Bug Fixes
|
|||
- c18a6e_: Check for valid secondary mode on S(a,b) tables.
|
||||
- 82c456_: Fix bug where last process could have zero particles.
|
||||
|
||||
.. _2b1e8a: https://github.com/mit-crpg/openmc/commit/2b1e8a
|
||||
.. _5853d2: https://github.com/mit-crpg/openmc/commit/5853d2
|
||||
.. _e178c7: https://github.com/mit-crpg/openmc/commit/e178c7
|
||||
.. _c18a6e: https://github.com/mit-crpg/openmc/commit/c18a6e
|
||||
.. _82c456: https://github.com/mit-crpg/openmc/commit/82c456
|
||||
.. _2b1e8a: https://github.com/openmc-dev/openmc/commit/2b1e8a
|
||||
.. _5853d2: https://github.com/openmc-dev/openmc/commit/5853d2
|
||||
.. _e178c7: https://github.com/openmc-dev/openmc/commit/e178c7
|
||||
.. _c18a6e: https://github.com/openmc-dev/openmc/commit/c18a6e
|
||||
.. _82c456: https://github.com/openmc-dev/openmc/commit/82c456
|
||||
|
|
|
|||
|
|
@ -39,13 +39,13 @@ Bug Fixes
|
|||
- cf567c_: ENDF/B-VI data checked for compatibility
|
||||
- 6b9461_: Fix p_valid sampling inside of sample_energy
|
||||
|
||||
.. _32c03c: https://github.com/mit-crpg/openmc/commit/32c03c
|
||||
.. _c71ef5: https://github.com/mit-crpg/openmc/commit/c71ef5
|
||||
.. _8884fb: https://github.com/mit-crpg/openmc/commit/8884fb
|
||||
.. _b38af0: https://github.com/mit-crpg/openmc/commit/b38af0
|
||||
.. _d28750: https://github.com/mit-crpg/openmc/commit/d28750
|
||||
.. _cf567c: https://github.com/mit-crpg/openmc/commit/cf567c
|
||||
.. _6b9461: https://github.com/mit-crpg/openmc/commit/6b9461
|
||||
.. _32c03c: https://github.com/openmc-dev/openmc/commit/32c03c
|
||||
.. _c71ef5: https://github.com/openmc-dev/openmc/commit/c71ef5
|
||||
.. _8884fb: https://github.com/openmc-dev/openmc/commit/8884fb
|
||||
.. _b38af0: https://github.com/openmc-dev/openmc/commit/b38af0
|
||||
.. _d28750: https://github.com/openmc-dev/openmc/commit/d28750
|
||||
.. _cf567c: https://github.com/openmc-dev/openmc/commit/cf567c
|
||||
.. _6b9461: https://github.com/openmc-dev/openmc/commit/6b9461
|
||||
|
||||
------------
|
||||
Contributors
|
||||
|
|
|
|||
|
|
@ -35,13 +35,13 @@ Bug Fixes
|
|||
- d7a7d0_: Fix bug with <element> specifying xs attribute
|
||||
- 85b3cb_: Fix out-of-bounds error with OpenMP threading
|
||||
|
||||
.. _41f7ca: https://github.com/mit-crpg/openmc/commit/41f7ca
|
||||
.. _038736: https://github.com/mit-crpg/openmc/commit/038736
|
||||
.. _46f9e8: https://github.com/mit-crpg/openmc/commit/46f9e8
|
||||
.. _d1ca35: https://github.com/mit-crpg/openmc/commit/d1ca35
|
||||
.. _0291c0: https://github.com/mit-crpg/openmc/commit/0291c0
|
||||
.. _d7a7d0: https://github.com/mit-crpg/openmc/commit/d7a7d0
|
||||
.. _85b3cb: https://github.com/mit-crpg/openmc/commit/85b3cb
|
||||
.. _41f7ca: https://github.com/openmc-dev/openmc/commit/41f7ca
|
||||
.. _038736: https://github.com/openmc-dev/openmc/commit/038736
|
||||
.. _46f9e8: https://github.com/openmc-dev/openmc/commit/46f9e8
|
||||
.. _d1ca35: https://github.com/openmc-dev/openmc/commit/d1ca35
|
||||
.. _0291c0: https://github.com/openmc-dev/openmc/commit/0291c0
|
||||
.. _d7a7d0: https://github.com/openmc-dev/openmc/commit/d7a7d0
|
||||
.. _85b3cb: https://github.com/openmc-dev/openmc/commit/85b3cb
|
||||
|
||||
------------
|
||||
Contributors
|
||||
|
|
|
|||
|
|
@ -38,16 +38,16 @@ Bug Fixes
|
|||
- 2a95ef_: Prevent segmentation fault on "current" score without mesh filter
|
||||
- 93e482_: Check for negative values in probability tables
|
||||
|
||||
.. _03e890: https://github.com/mit-crpg/openmc/commit/03e890
|
||||
.. _4439de: https://github.com/mit-crpg/openmc/commit/4439de
|
||||
.. _5808ed: https://github.com/mit-crpg/openmc/commit/5808ed
|
||||
.. _2e60c0: https://github.com/mit-crpg/openmc/commit/2e60c0
|
||||
.. _3e0870: https://github.com/mit-crpg/openmc/commit/3e0870
|
||||
.. _dc4776: https://github.com/mit-crpg/openmc/commit/dc4776
|
||||
.. _01178b: https://github.com/mit-crpg/openmc/commit/01178b
|
||||
.. _62ec43: https://github.com/mit-crpg/openmc/commit/62ec43
|
||||
.. _2a95ef: https://github.com/mit-crpg/openmc/commit/2a95ef
|
||||
.. _93e482: https://github.com/mit-crpg/openmc/commit/93e482
|
||||
.. _03e890: https://github.com/openmc-dev/openmc/commit/03e890
|
||||
.. _4439de: https://github.com/openmc-dev/openmc/commit/4439de
|
||||
.. _5808ed: https://github.com/openmc-dev/openmc/commit/5808ed
|
||||
.. _2e60c0: https://github.com/openmc-dev/openmc/commit/2e60c0
|
||||
.. _3e0870: https://github.com/openmc-dev/openmc/commit/3e0870
|
||||
.. _dc4776: https://github.com/openmc-dev/openmc/commit/dc4776
|
||||
.. _01178b: https://github.com/openmc-dev/openmc/commit/01178b
|
||||
.. _62ec43: https://github.com/openmc-dev/openmc/commit/62ec43
|
||||
.. _2a95ef: https://github.com/openmc-dev/openmc/commit/2a95ef
|
||||
.. _93e482: https://github.com/openmc-dev/openmc/commit/93e482
|
||||
|
||||
------------
|
||||
Contributors
|
||||
|
|
|
|||
|
|
@ -33,10 +33,10 @@ Bug Fixes
|
|||
- e6abb9_: Fix segfault when tallying in a void material
|
||||
- 291b45_: Handle metastable nuclides in NNDC data and multiplicities in MT=5 data
|
||||
|
||||
.. _26fb93: https://github.com/mit-crpg/openmc/commit/26fb93
|
||||
.. _2f07c0: https://github.com/mit-crpg/openmc/commit/2f07c0
|
||||
.. _e6abb9: https://github.com/mit-crpg/openmc/commit/e6abb9
|
||||
.. _291b45: https://github.com/mit-crpg/openmc/commit/291b45
|
||||
.. _26fb93: https://github.com/openmc-dev/openmc/commit/26fb93
|
||||
.. _2f07c0: https://github.com/openmc-dev/openmc/commit/2f07c0
|
||||
.. _e6abb9: https://github.com/openmc-dev/openmc/commit/e6abb9
|
||||
.. _291b45: https://github.com/openmc-dev/openmc/commit/291b45
|
||||
|
||||
------------
|
||||
Contributors
|
||||
|
|
|
|||
|
|
@ -40,11 +40,11 @@ Bug Fixes
|
|||
- 6121d9_: Fix bugs related to particle track files
|
||||
- 2f0e89_: Fixes for nuclide specification in tallies
|
||||
|
||||
.. _b5f712: https://github.com/mit-crpg/openmc/commit/b5f712
|
||||
.. _e6675b: https://github.com/mit-crpg/openmc/commit/e6675b
|
||||
.. _04e2c1: https://github.com/mit-crpg/openmc/commit/04e2c1
|
||||
.. _6121d9: https://github.com/mit-crpg/openmc/commit/6121d9
|
||||
.. _2f0e89: https://github.com/mit-crpg/openmc/commit/2f0e89
|
||||
.. _b5f712: https://github.com/openmc-dev/openmc/commit/b5f712
|
||||
.. _e6675b: https://github.com/openmc-dev/openmc/commit/e6675b
|
||||
.. _04e2c1: https://github.com/openmc-dev/openmc/commit/04e2c1
|
||||
.. _6121d9: https://github.com/openmc-dev/openmc/commit/6121d9
|
||||
.. _2f0e89: https://github.com/openmc-dev/openmc/commit/2f0e89
|
||||
|
||||
------------
|
||||
Contributors
|
||||
|
|
|
|||
|
|
@ -62,15 +62,15 @@ Bug Fixes
|
|||
- 441fd4_: Fix bug in kappa-fission score
|
||||
- 7e5974_: Allow fixed source simulations from Python API
|
||||
|
||||
.. _299322: https://github.com/mit-crpg/openmc/commit/299322
|
||||
.. _d74840: https://github.com/mit-crpg/openmc/commit/d74840
|
||||
.. _c29a81: https://github.com/mit-crpg/openmc/commit/c29a81
|
||||
.. _3edc23: https://github.com/mit-crpg/openmc/commit/3edc23
|
||||
.. _629e3b: https://github.com/mit-crpg/openmc/commit/629e3b
|
||||
.. _5dbe8b: https://github.com/mit-crpg/openmc/commit/5dbe8b
|
||||
.. _ff66f4: https://github.com/mit-crpg/openmc/commit/ff66f4
|
||||
.. _441fd4: https://github.com/mit-crpg/openmc/commit/441fd4
|
||||
.. _7e5974: https://github.com/mit-crpg/openmc/commit/7e5974
|
||||
.. _299322: https://github.com/openmc-dev/openmc/commit/299322
|
||||
.. _d74840: https://github.com/openmc-dev/openmc/commit/d74840
|
||||
.. _c29a81: https://github.com/openmc-dev/openmc/commit/c29a81
|
||||
.. _3edc23: https://github.com/openmc-dev/openmc/commit/3edc23
|
||||
.. _629e3b: https://github.com/openmc-dev/openmc/commit/629e3b
|
||||
.. _5dbe8b: https://github.com/openmc-dev/openmc/commit/5dbe8b
|
||||
.. _ff66f4: https://github.com/openmc-dev/openmc/commit/ff66f4
|
||||
.. _441fd4: https://github.com/openmc-dev/openmc/commit/441fd4
|
||||
.. _7e5974: https://github.com/openmc-dev/openmc/commit/7e5974
|
||||
|
||||
------------
|
||||
Contributors
|
||||
|
|
|
|||
|
|
@ -65,17 +65,17 @@ Bug Fixes
|
|||
- 8467ae_: Better threshold for allowable lost particles
|
||||
- 493c6f_: Fix type of return argument for h5pget_driver_f
|
||||
|
||||
.. _70daa7: https://github.com/mit-crpg/openmc/commit/70daa7
|
||||
.. _40b05f: https://github.com/mit-crpg/openmc/commit/40b05f
|
||||
.. _9586ed: https://github.com/mit-crpg/openmc/commit/9586ed
|
||||
.. _a855e8: https://github.com/mit-crpg/openmc/commit/a855e8
|
||||
.. _7294a1: https://github.com/mit-crpg/openmc/commit/7294a1
|
||||
.. _12f246: https://github.com/mit-crpg/openmc/commit/12f246
|
||||
.. _0227f4: https://github.com/mit-crpg/openmc/commit/0227f4
|
||||
.. _51deaa: https://github.com/mit-crpg/openmc/commit/51deaa
|
||||
.. _fed74b: https://github.com/mit-crpg/openmc/commit/fed74b
|
||||
.. _8467ae: https://github.com/mit-crpg/openmc/commit/8467ae
|
||||
.. _493c6f: https://github.com/mit-crpg/openmc/commit/493c6f
|
||||
.. _70daa7: https://github.com/openmc-dev/openmc/commit/70daa7
|
||||
.. _40b05f: https://github.com/openmc-dev/openmc/commit/40b05f
|
||||
.. _9586ed: https://github.com/openmc-dev/openmc/commit/9586ed
|
||||
.. _a855e8: https://github.com/openmc-dev/openmc/commit/a855e8
|
||||
.. _7294a1: https://github.com/openmc-dev/openmc/commit/7294a1
|
||||
.. _12f246: https://github.com/openmc-dev/openmc/commit/12f246
|
||||
.. _0227f4: https://github.com/openmc-dev/openmc/commit/0227f4
|
||||
.. _51deaa: https://github.com/openmc-dev/openmc/commit/51deaa
|
||||
.. _fed74b: https://github.com/openmc-dev/openmc/commit/fed74b
|
||||
.. _8467ae: https://github.com/openmc-dev/openmc/commit/8467ae
|
||||
.. _493c6f: https://github.com/openmc-dev/openmc/commit/493c6f
|
||||
|
||||
------------
|
||||
Contributors
|
||||
|
|
|
|||
|
|
@ -111,25 +111,25 @@ Bug Fixes
|
|||
- 489540_: Check for void materials in tracklength tallies
|
||||
- f0214f_: Fixes/improvements to the ARES algorithm
|
||||
|
||||
.. _c5df6c: https://github.com/mit-crpg/openmc/commit/c5df6c
|
||||
.. _1cfa39: https://github.com/mit-crpg/openmc/commit/1cfa39
|
||||
.. _335359: https://github.com/mit-crpg/openmc/commit/335359
|
||||
.. _17c678: https://github.com/mit-crpg/openmc/commit/17c678
|
||||
.. _23ec0b: https://github.com/mit-crpg/openmc/commit/23ec0b
|
||||
.. _7eefb7: https://github.com/mit-crpg/openmc/commit/7eefb7
|
||||
.. _7880d4: https://github.com/mit-crpg/openmc/commit/7880d4
|
||||
.. _ad2d9f: https://github.com/mit-crpg/openmc/commit/ad2d9f
|
||||
.. _59fdca: https://github.com/mit-crpg/openmc/commit/59fdca
|
||||
.. _9eff5b: https://github.com/mit-crpg/openmc/commit/9eff5b
|
||||
.. _7848a9: https://github.com/mit-crpg/openmc/commit/7848a9
|
||||
.. _f139ce: https://github.com/mit-crpg/openmc/commit/f139ce
|
||||
.. _b8ddfa: https://github.com/mit-crpg/openmc/commit/b8ddfa
|
||||
.. _ec3cfb: https://github.com/mit-crpg/openmc/commit/ec3cfb
|
||||
.. _5e9b06: https://github.com/mit-crpg/openmc/commit/5e9b06
|
||||
.. _c39990: https://github.com/mit-crpg/openmc/commit/c39990
|
||||
.. _c6b67e: https://github.com/mit-crpg/openmc/commit/c6b67e
|
||||
.. _489540: https://github.com/mit-crpg/openmc/commit/489540
|
||||
.. _f0214f: https://github.com/mit-crpg/openmc/commit/f0214f
|
||||
.. _c5df6c: https://github.com/openmc-dev/openmc/commit/c5df6c
|
||||
.. _1cfa39: https://github.com/openmc-dev/openmc/commit/1cfa39
|
||||
.. _335359: https://github.com/openmc-dev/openmc/commit/335359
|
||||
.. _17c678: https://github.com/openmc-dev/openmc/commit/17c678
|
||||
.. _23ec0b: https://github.com/openmc-dev/openmc/commit/23ec0b
|
||||
.. _7eefb7: https://github.com/openmc-dev/openmc/commit/7eefb7
|
||||
.. _7880d4: https://github.com/openmc-dev/openmc/commit/7880d4
|
||||
.. _ad2d9f: https://github.com/openmc-dev/openmc/commit/ad2d9f
|
||||
.. _59fdca: https://github.com/openmc-dev/openmc/commit/59fdca
|
||||
.. _9eff5b: https://github.com/openmc-dev/openmc/commit/9eff5b
|
||||
.. _7848a9: https://github.com/openmc-dev/openmc/commit/7848a9
|
||||
.. _f139ce: https://github.com/openmc-dev/openmc/commit/f139ce
|
||||
.. _b8ddfa: https://github.com/openmc-dev/openmc/commit/b8ddfa
|
||||
.. _ec3cfb: https://github.com/openmc-dev/openmc/commit/ec3cfb
|
||||
.. _5e9b06: https://github.com/openmc-dev/openmc/commit/5e9b06
|
||||
.. _c39990: https://github.com/openmc-dev/openmc/commit/c39990
|
||||
.. _c6b67e: https://github.com/openmc-dev/openmc/commit/c6b67e
|
||||
.. _489540: https://github.com/openmc-dev/openmc/commit/489540
|
||||
.. _f0214f: https://github.com/openmc-dev/openmc/commit/f0214f
|
||||
|
||||
------------
|
||||
Contributors
|
||||
|
|
|
|||
|
|
@ -141,13 +141,13 @@ and `Volume II`_. You may also find it helpful to review the following terms:
|
|||
- `Effective multiplication factor`_
|
||||
- `Flux`_
|
||||
|
||||
.. _nuclear reactor: http://en.wikipedia.org/wiki/Nuclear_reactor
|
||||
.. _Monte Carlo: http://en.wikipedia.org/wiki/Monte_Carlo_method
|
||||
.. _fission: http://en.wikipedia.org/wiki/Nuclear_fission
|
||||
.. _deterministic: http://en.wikipedia.org/wiki/Deterministic_algorithm
|
||||
.. _neutron transport: http://en.wikipedia.org/wiki/Neutron_transport
|
||||
.. _discretization: http://en.wikipedia.org/wiki/Discretization
|
||||
.. _constructive solid geometry: http://en.wikipedia.org/wiki/Constructive_solid_geometry
|
||||
.. _nuclear reactor: https://en.wikipedia.org/wiki/Nuclear_reactor
|
||||
.. _Monte Carlo: https://en.wikipedia.org/wiki/Monte_Carlo_method
|
||||
.. _fission: https://en.wikipedia.org/wiki/Nuclear_fission
|
||||
.. _deterministic: https://en.wikipedia.org/wiki/Deterministic_algorithm
|
||||
.. _neutron transport: https://en.wikipedia.org/wiki/Neutron_transport
|
||||
.. _discretization: https://en.wikipedia.org/wiki/Discretization
|
||||
.. _constructive solid geometry: https://en.wikipedia.org/wiki/Constructive_solid_geometry
|
||||
.. _git: http://git-scm.com/
|
||||
.. _git tutorials: http://git-scm.com/documentation
|
||||
.. _Reactor Concepts Manual: http://www.tayloredge.com/periodic/trivia/ReactorConcepts.pdf
|
||||
|
|
@ -156,6 +156,6 @@ and `Volume II`_. You may also find it helpful to review the following terms:
|
|||
.. _OpenMC source code: https://github.com/openmc-dev/openmc
|
||||
.. _GitHub: https://github.com/
|
||||
.. _bug reports: https://github.com/openmc-dev/openmc/issues
|
||||
.. _Neutron cross section: http://en.wikipedia.org/wiki/Neutron_cross_section
|
||||
.. _Neutron cross section: https://en.wikipedia.org/wiki/Neutron_cross_section
|
||||
.. _Effective multiplication factor: https://en.wikipedia.org/wiki/Nuclear_chain_reaction#Effective_neutron_multiplication_factor
|
||||
.. _Flux: http://en.wikipedia.org/wiki/Neutron_flux
|
||||
.. _Flux: https://en.wikipedia.org/wiki/Neutron_flux
|
||||
|
|
|
|||
|
|
@ -16,10 +16,10 @@ recommended to use one of the pregenerated libraries. Alternatively, if you have
|
|||
ACE format data that was produced with NJOY_, such as that distributed with
|
||||
MCNP_ or Serpent_, it can be converted to the HDF5 format using the :ref:`using
|
||||
the Python API <create_xs_library>`. Several sources provide openly available
|
||||
ACE data including the `ENDF/B`_, JEFF_, and TENDL_
|
||||
libraries. In addition to tabulated cross sections in the HDF5 files, OpenMC
|
||||
relies on :ref:`windowed multipole <windowed_multipole>` data to perform
|
||||
on-the-fly Doppler broadening.
|
||||
ACE data including the `ENDF/B`_, JEFF_, and TENDL_ libraries as well as the
|
||||
`LANL Nuclear Data Team <https://nucleardata.lanl.gov/>`_. In addition to
|
||||
tabulated cross sections in the HDF5 files, OpenMC relies on :ref:`windowed
|
||||
multipole <windowed_multipole>` data to perform on-the-fly Doppler broadening.
|
||||
|
||||
In multi-group mode, OpenMC utilizes an HDF5-based library format which can be
|
||||
used to describe nuclide- or material-specific quantities.
|
||||
|
|
@ -30,11 +30,11 @@ Environment Variables
|
|||
|
||||
When :ref:`scripts_openmc` is run, it will look for several environment
|
||||
variables that indicate where cross sections can be found. While the location of
|
||||
cross sections can also be indicated through the :class:`openmc.Materials` class
|
||||
(or in the :ref:`materials.xml <io_materials>` file), if you always use the same
|
||||
set of cross section data, it is often easier to just set an environment
|
||||
variable that will be picked up by default every time OpenMC is run. The
|
||||
following environment variables are used:
|
||||
cross sections can also be indicated through the
|
||||
:attr:`openmc.Materials.cross_setion` attribute (or in the :ref:`materials.xml
|
||||
<io_materials>` file), if you always use the same set of cross section data, it
|
||||
is often easier to just set an environment variable that will be picked up by
|
||||
default every time OpenMC is run. The following environment variables are used:
|
||||
|
||||
:envvar:`OPENMC_CROSS_SECTIONS`
|
||||
Indicates the path to the :ref:`cross_sections.xml <io_cross_sections>`
|
||||
|
|
|
|||
|
|
@ -29,8 +29,8 @@ operator class requires a :class:`openmc.Geometry` instance and a
|
|||
op = openmc.deplete.Operator(geom, settings)
|
||||
|
||||
:mod:`openmc.deplete` supports multiple time-integration methods for determining
|
||||
material compositions over time. Each method appears as a different function.
|
||||
For example, :func:`openmc.deplete.integrator.cecm` runs a depletion calculation
|
||||
material compositions over time. Each method appears as a different class.
|
||||
For example, :class:`openmc.deplete.CECMIntegrator` runs a depletion calculation
|
||||
using the CE/CM algorithm (deplete over a timestep using the middle-of-step
|
||||
reaction rates). An instance of :class:`openmc.deplete.Operator` is passed to
|
||||
one of these functions along with the power level and timesteps::
|
||||
|
|
@ -38,7 +38,7 @@ one of these functions along with the power level and timesteps::
|
|||
power = 1200.0e6
|
||||
days = 24*60*60
|
||||
timesteps = [10.0*days, 10.0*days, 10.0*days]
|
||||
openmc.deplete.cecm(op, power, timesteps)
|
||||
openmc.deplete.CECMIntegrator(op, power, timesteps).integrate()
|
||||
|
||||
The coupled transport-depletion problem is executed, and once it is done a
|
||||
``depletion_results.h5`` file is written. The results can be analyzed using the
|
||||
|
|
@ -46,8 +46,92 @@ The coupled transport-depletion problem is executed, and once it is done a
|
|||
easy retrieval of k-effective, nuclide concentrations, and reaction rates over
|
||||
time::
|
||||
|
||||
results = openmc.deplete.ResultsList("depletion_results.h5")
|
||||
results = openmc.deplete.ResultsList.from_hdf5("depletion_results.h5")
|
||||
time, keff = results.get_eigenvalue()
|
||||
|
||||
Note that the coupling between the transport solver and the transmutation solver
|
||||
happens in-memory rather than by reading/writing files on disk.
|
||||
|
||||
Caveats
|
||||
=======
|
||||
|
||||
Energy Deposition
|
||||
-----------------
|
||||
|
||||
The default energy deposition mode, ``"fission-q"``, instructs the
|
||||
:class:`openmc.deplete.Operator` to normalize reaction rates using the product
|
||||
of fission reaction rates and fission Q values taken from the depletion chain.
|
||||
This approach does not consider indirect contributions to energy deposition,
|
||||
such as neutron heating and energy from secondary photons. In doing this,
|
||||
the energy deposited during a transport calculation will be lower than expected.
|
||||
This causes the reaction rates to be over-adjusted to hit the user-specific power,
|
||||
or power density, leading to an over-depletion of burnable materials.
|
||||
|
||||
There are some remedies. First, the fission Q values can be directly set in a
|
||||
variety of ways. This requires knowing what the total fission energy release should
|
||||
be, including indirect components. Some examples are provided below::
|
||||
|
||||
# use a dictionary of fission_q values
|
||||
fission_q = {"U235": 202} # energy in MeV
|
||||
|
||||
# create a modified chain and write it to a new file
|
||||
chain = openmc.deplete.Chain.from_xml("chain.xml", fission_q)
|
||||
chain.export_to_xml("chain_mod_q.xml")
|
||||
op = openmc.deplete.Operator(geometry, setting, "chain_mod_q.xml")
|
||||
|
||||
# alternatively, pass the modified fission Q directly to the operator
|
||||
op = openmc.deplete.Operator(geometry, setting, "chain.xml",
|
||||
fission_q=fission_q)
|
||||
|
||||
|
||||
A more complete way to model the energy deposition is to use the modified heating
|
||||
reactions described in :ref:`methods_heating`. These values can be used to normalize
|
||||
reaction rates instead of using the fission reaction rates with::
|
||||
|
||||
op = openmc.deplete.Operator(geometry, settings, "chain.xml",
|
||||
energy_mode="energy-deposition")
|
||||
|
||||
These modified heating libraries can be generated by running the latest version
|
||||
of :meth:`openmc.data.IncidentNeutron.from_njoy`, and will eventually be bundled into
|
||||
the distributed libraries.
|
||||
|
||||
Local Spectra and Repeated Materials
|
||||
------------------------------------
|
||||
|
||||
It is not uncommon to explicitly create a single burnable material across many locations.
|
||||
From a pure transport perspective, there is nothing wrong with creating a single
|
||||
3.5 wt.% enriched fuel ``fuel_3``, and placing that fuel in every fuel pin in an assembly
|
||||
or even full core problem. This certainly expedites the model making process, but can pose
|
||||
issues with depletion.
|
||||
Under this setup, :mod:`openmc.deplete` will deplete a single ``fuel_3`` material using
|
||||
a single set of reaction rates, and produce a single new composition for the next time
|
||||
step. This can be problematic if the same ``fuel_3`` is used in very different regions
|
||||
of the problem.
|
||||
|
||||
As an example, consider a full-scale power reactor core with vacuum boundary
|
||||
conditions, and with fuel pins solely composed of the same ``fuel_3`` material.
|
||||
The fuel pins towards the center of the problem will surely experience a more intense
|
||||
neutron flux and greater reaction rates than those towards the edge of the domain.
|
||||
This indicates that the fuel in the center should be at a more depleted state than
|
||||
periphery pins, at least for the fist depletion step.
|
||||
However, without any other instructions, OpenMC will deplete ``fuel_3`` as a single
|
||||
material, and all of the fuel pins will have an identical composition at the next
|
||||
transport step.
|
||||
|
||||
This can be countered by instructing the operator to treat repeated instances
|
||||
of the same material as a unique material definition with::
|
||||
|
||||
op = openmc.deplete.Operator(geometry, settings, chain_file,
|
||||
diff_burnable_mats=True)
|
||||
|
||||
For our example problem, this would deplete fuel on the outer region of the problem
|
||||
with different reaction rates than those in the center. Materials will be depleted
|
||||
corresponding to their local neutron spectra, and have unique compositions at each
|
||||
transport step.
|
||||
|
||||
|
||||
.. note::
|
||||
|
||||
This will increase the total memory usage and run time due to an increased
|
||||
number of tallies and material definitions.
|
||||
|
||||
|
|
|
|||
|
|
@ -121,11 +121,11 @@ For many regions, a bounding-box can be determined automatically::
|
|||
While a bounding box can be determined for regions involving half-spaces of
|
||||
spheres, cylinders, and axis-aligned planes, it generally cannot be determined
|
||||
if the region involves cones, non-axis-aligned planes, or other exotic
|
||||
second-order surfaces. For example, the :func:`openmc.get_hexagonal_prism`
|
||||
second-order surfaces. For example, the :func:`openmc.model.hexagonal_prism`
|
||||
function returns the interior region of a hexagonal prism; because it is bounded
|
||||
by a :class:`openmc.Plane`, trying to get its bounding box won't work::
|
||||
|
||||
>>> hex = openmc.get_hexagonal_prism()
|
||||
>>> hex = openmc.model.hexagonal_prism()
|
||||
>>> hex.bounding_box
|
||||
(array([-0.8660254, -inf, -inf]),
|
||||
array([ 0.8660254, inf, inf]))
|
||||
|
|
@ -374,7 +374,7 @@ code would work::
|
|||
hexlat.universes = [outer_ring, middle_ring, inner_ring]
|
||||
|
||||
If you need to create a hexagonal boundary (composed of six planar surfaces) for
|
||||
a hexagonal lattice, :func:`openmc.get_hexagonal_prism` can be used.
|
||||
a hexagonal lattice, :func:`openmc.model.hexagonal_prism` can be used.
|
||||
|
||||
.. _usersguide_geom_export:
|
||||
|
||||
|
|
@ -396,8 +396,15 @@ if needed, lattices, the last step is to create an instance of
|
|||
geom.root_universe = root_univ
|
||||
geom.export_to_xml()
|
||||
|
||||
.. _constructive solid geometry: http://en.wikipedia.org/wiki/Constructive_solid_geometry
|
||||
.. _quadratic surfaces: http://en.wikipedia.org/wiki/Quadric
|
||||
Note that it's not strictly required to manually create a root universe. You can
|
||||
also pass a list of cells to the :class:`openmc.Geometry` constructor and it
|
||||
will handle creating the unverse::
|
||||
|
||||
geom = openmc.Geometry([cell1, cell2, cell3])
|
||||
geom.export_to_xml()
|
||||
|
||||
.. _constructive solid geometry: https://en.wikipedia.org/wiki/Constructive_solid_geometry
|
||||
.. _quadratic surfaces: https://en.wikipedia.org/wiki/Quadric
|
||||
|
||||
--------------------------
|
||||
Using CAD-based Geometry
|
||||
|
|
|
|||
|
|
@ -17,7 +17,8 @@ system for installing multiple versions of software packages and their
|
|||
dependencies and switching easily between them. `conda-forge
|
||||
<https://conda-forge.github.io/>`_ is a community-led conda channel of
|
||||
installable packages. For instructions on installing conda, please consult their
|
||||
`documentation <http://conda.pydata.org/docs/install/quick.html>`_.
|
||||
`documentation
|
||||
<https://docs.conda.io/projects/conda/en/latest/user-guide/install/>`_.
|
||||
|
||||
Once you have `conda` installed on your system, add the `conda-forge` channel to
|
||||
your configuration with:
|
||||
|
|
@ -444,7 +445,7 @@ as for OpenMC.
|
|||
.. admonition:: Optional
|
||||
:class: note
|
||||
|
||||
`mpi4py <http://mpi4py.scipy.org/>`_
|
||||
`mpi4py <https://mpi4py.readthedocs.io/en/stable/>`_
|
||||
mpi4py provides Python bindings to MPI for running distributed-memory
|
||||
parallel runs. This package is needed if you plan on running depletion
|
||||
simulations in parallel using MPI.
|
||||
|
|
@ -483,9 +484,9 @@ Make sure to replace the last string on the second line with the path to the
|
|||
schemas.xml file in your own OpenMC source directory.
|
||||
|
||||
.. _GNU Emacs: http://www.gnu.org/software/emacs/
|
||||
.. _validation: http://en.wikipedia.org/wiki/XML_validation
|
||||
.. _validation: https://en.wikipedia.org/wiki/XML_validation
|
||||
.. _RELAX NG: http://relaxng.org/
|
||||
.. _NNDC: http://www.nndc.bnl.gov/endf/b7.1/acefiles.html
|
||||
.. _ctest: http://www.cmake.org/cmake/help/v2.8.12/ctest.html
|
||||
.. _Conda: https://conda.io/docs/
|
||||
.. _Conda: https://docs.conda.io/en/latest/
|
||||
.. _pip: https://pip.pypa.io/en/stable/
|
||||
|
|
|
|||
|
|
@ -66,7 +66,7 @@ particular cells/materials should be given colors of your choosing::
|
|||
}
|
||||
|
||||
Note that colors can be given as RGB tuples or by a string indicating a valid
|
||||
`SVG color <https://www.w3.org/TR/SVG/types.html#ColorKeywords>`_.
|
||||
`SVG color <https://www.w3.org/TR/SVG11/types.html#ColorKeywords>`_.
|
||||
|
||||
When you're done creating your :class:`openmc.Plot` instances, you need to then
|
||||
assign them to a :class:`openmc.Plots` collection and export it to XML::
|
||||
|
|
|
|||
|
|
@ -221,26 +221,11 @@ selected::
|
|||
|
||||
settings.electron_treatment = 'led'
|
||||
|
||||
.. warning::
|
||||
Currently, collision stopping powers used in the TTB approximation come from
|
||||
the `NIST ESTAR database`_, which provides data for each element calculated
|
||||
using by default the material density at standard temperature and pressure.
|
||||
In OpenMC, stopping powers for compounds are calculated from this elemental
|
||||
data using Bragg's additivity rule. However, this is not a good
|
||||
approximation --- the collision stopping power is a function of certain
|
||||
quantities, such as the mean excitation energy and particularly the density
|
||||
effect correction, that depend on material properties. Data for constituent
|
||||
elements in a compound cannot simply be summed together, but rather these
|
||||
quantities should be calculated for the material. This treatment will be
|
||||
especially poor when the density of a material is different from the
|
||||
densities used in the NIST data.
|
||||
|
||||
.. note::
|
||||
Some features related to photon transport are not currently implemented,
|
||||
including:
|
||||
|
||||
* Tallying photon energy deposition.
|
||||
* Properly accounting for energy deposition in coupled n-p calculations.
|
||||
* Generating a photon source from a neutron calculation that can be used
|
||||
for a later fixed source photon calculation.
|
||||
* Photoneutron reactions.
|
||||
|
|
|
|||
|
|
@ -261,7 +261,13 @@ The following tables show all valid scores:
|
|||
| |produced by NJOY's HEATR module while for photons, |
|
||||
| |this is tallied from either direct photon energy |
|
||||
| |deposition (analog estimator) or pre-generated |
|
||||
| |photon heating number. |
|
||||
| |photon heating number. See :ref:`methods_heating` |
|
||||
+----------------------+---------------------------------------------------+
|
||||
|heating-local |Total nuclear heating in units of eV per source |
|
||||
| |particle assuming energy from secondary photons is |
|
||||
| |deposited locally. Note that this score should only|
|
||||
| |be used for incident neutrons. See |
|
||||
| |:ref:`methods_heating`. |
|
||||
+----------------------+---------------------------------------------------+
|
||||
|kappa-fission |The recoverable energy production rate due to |
|
||||
| |fission. The recoverable energy is defined as the |
|
||||
|
|
|
|||
|
|
@ -37,6 +37,16 @@ arguments are not necessary. For example,
|
|||
Of course, the volumes that you *need* this capability for are often the ones
|
||||
with complex definitions.
|
||||
|
||||
A threshold can be applied for the calculation's variance, standard deviation,
|
||||
or relative error of volume estimates using :meth:`openmc.VolumeCalculation.set_trigger`::
|
||||
|
||||
vol_calc.set_trigger(1e-05, 'std_dev')
|
||||
|
||||
If a threshold is provided, calculations will be performed iteratively using the
|
||||
number of samples specified on the calculation until all volume uncertainties are below
|
||||
the threshold value. If no threshold is provided, the calculation will run the number of
|
||||
samples specified once and return the result.
|
||||
|
||||
Once you have one or more :class:`openmc.VolumeCalculation` objects created, you
|
||||
can then assign then to :attr:`Settings.volume_calculations`::
|
||||
|
||||
|
|
|
|||
1
examples/jupyter/chain_simple.xml
Symbolic link
1
examples/jupyter/chain_simple.xml
Symbolic link
|
|
@ -0,0 +1 @@
|
|||
/home/romano/openmc/tests/chain_simple.xml
|
||||
File diff suppressed because one or more lines are too long
996
examples/jupyter/pincell_depletion.ipynb
Normal file
996
examples/jupyter/pincell_depletion.ipynb
Normal file
File diff suppressed because one or more lines are too long
|
|
@ -61,14 +61,15 @@ op = openmc.deplete.Operator(geometry, settings_file, chain_file,
|
|||
previous_results)
|
||||
|
||||
# Perform simulation using the predictor algorithm
|
||||
openmc.deplete.integrator.predictor(op, time_steps, power)
|
||||
integrator = openmc.deplete.PredictorIntegrator(op, time_steps, power)
|
||||
integrator.integrate()
|
||||
|
||||
###############################################################################
|
||||
# Read depletion calculation results
|
||||
###############################################################################
|
||||
|
||||
# Open results file
|
||||
results = openmc.deplete.ResultsList("depletion_results.h5")
|
||||
results = openmc.deplete.ResultsList.from_hdf5("depletion_results.h5")
|
||||
|
||||
# Obtain K_eff as a function of time
|
||||
time, keff = results.get_eigenvalue()
|
||||
|
|
|
|||
|
|
@ -132,14 +132,15 @@ settings_file.entropy_mesh = entropy_mesh
|
|||
op = openmc.deplete.Operator(geometry, settings_file, chain_file)
|
||||
|
||||
# Perform simulation using the predictor algorithm
|
||||
openmc.deplete.integrator.predictor(op, time_steps, power)
|
||||
integrator = openmc.deplete.PredictorIntegrator(op, time_steps, power)
|
||||
integrator.integrate()
|
||||
|
||||
###############################################################################
|
||||
# Read depletion calculation results
|
||||
###############################################################################
|
||||
|
||||
# Open results file
|
||||
results = openmc.deplete.ResultsList("depletion_results.h5")
|
||||
results = openmc.deplete.ResultsList.from_hdf5("depletion_results.h5")
|
||||
|
||||
# Obtain K_eff as a function of time
|
||||
time, keff = results.get_eigenvalue()
|
||||
|
|
|
|||
|
|
@ -110,6 +110,7 @@ extern "C" {
|
|||
int openmc_tally_get_nuclides(int32_t index, int** nuclides, int* n);
|
||||
int openmc_tally_get_scores(int32_t index, int** scores, int* n);
|
||||
int openmc_tally_get_type(int32_t index, int32_t* type);
|
||||
int openmc_tally_get_writable(int32_t index, bool* writable);
|
||||
int openmc_tally_reset(int32_t index);
|
||||
int openmc_tally_results(int32_t index, double** ptr, size_t shape_[3]);
|
||||
int openmc_tally_set_active(int32_t index, bool active);
|
||||
|
|
@ -119,6 +120,7 @@ extern "C" {
|
|||
int openmc_tally_set_nuclides(int32_t index, int n, const char** nuclides);
|
||||
int openmc_tally_set_scores(int32_t index, int n, const char** scores);
|
||||
int openmc_tally_set_type(int32_t index, const char* type);
|
||||
int openmc_tally_set_writable(int32_t index, bool writable);
|
||||
int openmc_zernike_filter_get_order(int32_t index, int* order);
|
||||
int openmc_zernike_filter_get_params(int32_t index, double* x, double* y, double* r);
|
||||
int openmc_zernike_filter_set_order(int32_t index, int order);
|
||||
|
|
|
|||
|
|
@ -179,10 +179,10 @@ public:
|
|||
|
||||
//! \brief Rotational tranfsormation of the filled universe.
|
||||
//
|
||||
//! The vector is empty if there is no rotation. Otherwise, the first three
|
||||
//! values are the rotation angles respectively about the x-, y-, and z-, axes
|
||||
//! in degrees. The next 9 values give the rotation matrix in row-major
|
||||
//! order.
|
||||
//! The vector is empty if there is no rotation. Otherwise, the first 9 values
|
||||
//! give the rotation matrix in row-major order. When the user specifies
|
||||
//! rotation angles about the x-, y- and z- axes in degrees, these values are
|
||||
//! also present at the end of the vector, making it of length 12.
|
||||
std::vector<double> rotation_;
|
||||
|
||||
std::vector<int32_t> offset_; //!< Distribcell offset table
|
||||
|
|
@ -212,7 +212,26 @@ protected:
|
|||
bool contains_complex(Position r, Direction u, int32_t on_surface) const;
|
||||
BoundingBox bounding_box_simple() const;
|
||||
static BoundingBox bounding_box_complex(std::vector<int32_t> rpn);
|
||||
static void apply_demorgan(std::vector<int32_t>& rpn);
|
||||
|
||||
//! Applies DeMorgan's laws to a section of the RPN
|
||||
//! \param start Starting point for token modification
|
||||
//! \param stop Stopping point for token modification
|
||||
static void apply_demorgan(std::vector<int32_t>::iterator start,
|
||||
std::vector<int32_t>::iterator stop);
|
||||
|
||||
//! Removes complement operators from the RPN
|
||||
//! \param rpn The rpn to remove complement operators from.
|
||||
static void remove_complement_ops(std::vector<int32_t>& rpn);
|
||||
|
||||
//! Returns the beginning position of a parenthesis block (immediately before
|
||||
//! two surface tokens) in the RPN given a starting position at the end of
|
||||
//! that block (immediately after two surface tokens)
|
||||
//! \param start Starting position of the search
|
||||
//! \param rpn The rpn being searched
|
||||
static std::vector<int32_t>::iterator
|
||||
find_left_parenthesis(std::vector<int32_t>::iterator start,
|
||||
const std::vector<int32_t>& rpn);
|
||||
|
||||
};
|
||||
|
||||
//==============================================================================
|
||||
|
|
|
|||
|
|
@ -20,7 +20,7 @@ using double_4dvec = std::vector<std::vector<std::vector<std::vector<double>>>>;
|
|||
|
||||
// OpenMC major, minor, and release numbers
|
||||
constexpr int VERSION_MAJOR {0};
|
||||
constexpr int VERSION_MINOR {11};
|
||||
constexpr int VERSION_MINOR {12};
|
||||
constexpr int VERSION_RELEASE {0};
|
||||
constexpr bool VERSION_DEV {true};
|
||||
constexpr std::array<int, 3> VERSION {VERSION_MAJOR, VERSION_MINOR, VERSION_RELEASE};
|
||||
|
|
@ -232,7 +232,7 @@ constexpr int N_XD {204};
|
|||
constexpr int N_XT {205};
|
||||
constexpr int N_X3HE {206};
|
||||
constexpr int N_XA {207};
|
||||
constexpr int NEUTRON_HEATING {301};
|
||||
constexpr int HEATING {301};
|
||||
constexpr int DAMAGE_ENERGY {444};
|
||||
constexpr int COHERENT {502};
|
||||
constexpr int INCOHERENT {504};
|
||||
|
|
@ -252,6 +252,7 @@ constexpr int N_A0 {800};
|
|||
constexpr int N_AC {849};
|
||||
constexpr int N_2N0 {875};
|
||||
constexpr int N_2NC {891};
|
||||
constexpr int HEATING_LOCAL {901};
|
||||
|
||||
constexpr std::array<int, 6> DEPLETION_RX {N_GAMMA, N_P, N_A, N_2N, N_3N, N_4N};
|
||||
|
||||
|
|
@ -369,7 +370,6 @@ constexpr int SCORE_INVERSE_VELOCITY {-13}; // flux-weighted inverse velocity
|
|||
constexpr int SCORE_FISS_Q_PROMPT {-14}; // prompt fission Q-value
|
||||
constexpr int SCORE_FISS_Q_RECOV {-15}; // recoverable fission Q-value
|
||||
constexpr int SCORE_DECAY_RATE {-16}; // delayed neutron precursor decay rate
|
||||
constexpr int SCORE_HEATING {-17}; // nuclear heating (neutron or photon)
|
||||
|
||||
// Tally map bin finding
|
||||
constexpr int NO_BIN_FOUND {-1};
|
||||
|
|
|
|||
|
|
@ -132,7 +132,7 @@ public:
|
|||
|
||||
//----------------------------------------------------------------------------
|
||||
// Data
|
||||
int32_t id_; //!< Unique ID
|
||||
int32_t id_ {-1}; //!< Unique ID
|
||||
std::string name_; //!< Name of material
|
||||
std::vector<int> nuclide_; //!< Indices in nuclides vector
|
||||
std::vector<int> element_; //!< Indices in elements vector
|
||||
|
|
|
|||
|
|
@ -33,9 +33,10 @@ extern std::unordered_map<int32_t, int32_t> mesh_map;
|
|||
class Mesh
|
||||
{
|
||||
public:
|
||||
// Constructors
|
||||
// Constructors and destructor
|
||||
Mesh() = default;
|
||||
Mesh(pugi::xml_node node);
|
||||
virtual ~Mesh() = default;
|
||||
|
||||
// Methods
|
||||
|
||||
|
|
|
|||
|
|
@ -93,7 +93,7 @@ public:
|
|||
std::vector<UrrData> urr_data_;
|
||||
|
||||
std::vector<std::unique_ptr<Reaction>> reactions_; //!< Reactions
|
||||
std::array<size_t, 892> reaction_index_; //!< Index of each reaction
|
||||
std::array<size_t, 902> reaction_index_; //!< Index of each reaction
|
||||
std::vector<int> index_inelastic_scatter_;
|
||||
|
||||
private:
|
||||
|
|
|
|||
|
|
@ -25,6 +25,7 @@ extern "C" const int BC_TRANSMIT;
|
|||
extern "C" const int BC_VACUUM;
|
||||
extern "C" const int BC_REFLECT;
|
||||
extern "C" const int BC_PERIODIC;
|
||||
extern "C" const int BC_WHITE;
|
||||
|
||||
//==============================================================================
|
||||
// Global variables
|
||||
|
|
@ -115,6 +116,8 @@ public:
|
|||
//! \return Outgoing direction of the ray
|
||||
virtual Direction reflect(Position r, Direction u) const;
|
||||
|
||||
virtual Direction diffuse_reflect(Position r, Direction u) const;
|
||||
|
||||
//! Evaluate the equation describing the surface.
|
||||
//!
|
||||
//! Surfaces can be described by some function f(x, y, z) = 0. This member
|
||||
|
|
|
|||
|
|
@ -37,6 +37,8 @@ public:
|
|||
|
||||
void set_active(bool active) { active_ = active; }
|
||||
|
||||
void set_writable(bool writable) { writable_ = writable; }
|
||||
|
||||
void set_scores(pugi::xml_node node);
|
||||
|
||||
void set_scores(const std::vector<std::string>& scores);
|
||||
|
|
@ -55,6 +57,8 @@ public:
|
|||
|
||||
int32_t n_filter_bins() const {return n_filter_bins_;}
|
||||
|
||||
bool writable() const { return writable_;}
|
||||
|
||||
//----------------------------------------------------------------------------
|
||||
// Other methods.
|
||||
|
||||
|
|
@ -98,6 +102,9 @@ public:
|
|||
//! (e.g. specific cell, specific energy group, etc.)
|
||||
xt::xtensor<double, 3> results_;
|
||||
|
||||
//! True if this tally should be written to statepoint files
|
||||
bool writable_ {true};
|
||||
|
||||
//----------------------------------------------------------------------------
|
||||
// Miscellaneous public members.
|
||||
|
||||
|
|
|
|||
|
|
@ -76,11 +76,6 @@ private:
|
|||
std::unique_ptr<AngleEnergy> distribution; //!< Secondary angle-energy distribution
|
||||
};
|
||||
|
||||
//! Upper threshold for incoherent inelastic scattering (usually ~4 eV)
|
||||
double threshold_inelastic_;
|
||||
//! Upper threshold for coherent/incoherent elastic scattering
|
||||
double threshold_elastic_ {0.0};
|
||||
|
||||
// Inelastic scattering data
|
||||
Reaction elastic_;
|
||||
Reaction inelastic_;
|
||||
|
|
|
|||
|
|
@ -2,12 +2,14 @@
|
|||
#define OPENMC_VOLUME_CALC_H
|
||||
|
||||
#include "openmc/position.h"
|
||||
#include "openmc/tallies/trigger.h"
|
||||
|
||||
#include "pugixml.hpp"
|
||||
#include "xtensor/xtensor.hpp"
|
||||
|
||||
#include <string>
|
||||
#include <vector>
|
||||
#include <gsl/gsl>
|
||||
|
||||
namespace openmc {
|
||||
|
||||
|
|
@ -16,6 +18,7 @@ namespace openmc {
|
|||
//==============================================================================
|
||||
|
||||
class VolumeCalculation {
|
||||
|
||||
public:
|
||||
// Aliases, types
|
||||
struct Result {
|
||||
|
|
@ -23,6 +26,7 @@ public:
|
|||
std::vector<int> nuclides; //!< Index of nuclides
|
||||
std::vector<double> atoms; //!< Number of atoms for each nuclide
|
||||
std::vector<double> uncertainty; //!< Uncertainty on number of atoms
|
||||
int iterations; //!< Number of iterations needed to obtain the results
|
||||
}; // Results for a single domain
|
||||
|
||||
// Constructors
|
||||
|
|
@ -44,7 +48,9 @@ public:
|
|||
|
||||
// Data members
|
||||
int domain_type_; //!< Type of domain (cell, material, etc.)
|
||||
int n_samples_; //!< Number of samples to use
|
||||
size_t n_samples_; //!< Number of samples to use
|
||||
double threshold_ {-1.0}; //!< Error threshold for domain volumes
|
||||
TriggerMetric trigger_type_ {TriggerMetric::not_active}; //!< Trigger metric for the volume calculation
|
||||
Position lower_left_; //!< Lower-left position of bounding box
|
||||
Position upper_right_; //!< Upper-right position of bounding box
|
||||
std::vector<int> domain_ids_; //!< IDs of domains to find volumes of
|
||||
|
|
|
|||
|
|
@ -34,4 +34,4 @@ from . import examples
|
|||
# Import a few convencience functions that used to be here
|
||||
from openmc.model import rectangular_prism, hexagonal_prism
|
||||
|
||||
__version__ = '0.10.0'
|
||||
__version__ = '0.12.0-dev'
|
||||
|
|
|
|||
|
|
@ -63,6 +63,10 @@ class Cell(IDManagerMixin):
|
|||
\sin\phi \sin\theta \sin\psi & -\sin\phi \cos\psi + \cos\phi
|
||||
\sin\theta \sin\psi \\ -\sin\theta & \sin\phi \cos\theta & \cos\phi
|
||||
\cos\theta \end{array} \right ]
|
||||
|
||||
A rotation matrix can also be specified directly by setting this
|
||||
attribute to a nested list (or 2D numpy array) that specifies each
|
||||
element of the matrix.
|
||||
rotation_matrix : numpy.ndarray
|
||||
The rotation matrix defined by the angles specified in the
|
||||
:attr:`Cell.rotation` property.
|
||||
|
|
@ -227,21 +231,24 @@ class Cell(IDManagerMixin):
|
|||
|
||||
@rotation.setter
|
||||
def rotation(self, rotation):
|
||||
cv.check_type('cell rotation', rotation, Iterable, Real)
|
||||
cv.check_length('cell rotation', rotation, 3)
|
||||
self._rotation = np.asarray(rotation)
|
||||
|
||||
# Save rotation matrix -- the reason we do this instead of having it be
|
||||
# automatically calculated when the rotation_matrix property is accessed
|
||||
# is so that plotting on a rotated geometry can be done faster.
|
||||
phi, theta, psi = self.rotation*(-pi/180.)
|
||||
c3, s3 = cos(phi), sin(phi)
|
||||
c2, s2 = cos(theta), sin(theta)
|
||||
c1, s1 = cos(psi), sin(psi)
|
||||
self._rotation_matrix = np.array([
|
||||
[c1*c2, c1*s2*s3 - c3*s1, s1*s3 + c1*c3*s2],
|
||||
[c2*s1, c1*c3 + s1*s2*s3, c3*s1*s2 - c1*s3],
|
||||
[-s2, c2*s3, c2*c3]])
|
||||
if self._rotation.ndim == 2:
|
||||
# User specified rotation matrix directly
|
||||
self._rotation_matrix = self._rotation
|
||||
else:
|
||||
phi, theta, psi = self.rotation*(-pi/180.)
|
||||
c3, s3 = cos(phi), sin(phi)
|
||||
c2, s2 = cos(theta), sin(theta)
|
||||
c1, s1 = cos(psi), sin(psi)
|
||||
self._rotation_matrix = np.array([
|
||||
[c1*c2, c1*s2*s3 - c3*s1, s1*s3 + c1*c3*s2],
|
||||
[c2*s1, c1*c3 + s1*s2*s3, c3*s1*s2 - c1*s3],
|
||||
[-s2, c2*s3, c2*c3]])
|
||||
|
||||
@translation.setter
|
||||
def translation(self, translation):
|
||||
|
|
@ -516,7 +523,7 @@ class Cell(IDManagerMixin):
|
|||
element.set("translation", ' '.join(map(str, self.translation)))
|
||||
|
||||
if self.rotation is not None:
|
||||
element.set("rotation", ' '.join(map(str, self.rotation)))
|
||||
element.set("rotation", ' '.join(map(str, self.rotation.ravel())))
|
||||
|
||||
return element
|
||||
|
||||
|
|
|
|||
128
openmc/cmfd.py
128
openmc/cmfd.py
|
|
@ -22,7 +22,7 @@ import numpy as np
|
|||
from scipy import sparse
|
||||
import h5py
|
||||
|
||||
import openmc.capi
|
||||
import openmc.lib
|
||||
from openmc.checkvalue import (check_type, check_length, check_value,
|
||||
check_greater_than, check_less_than)
|
||||
from openmc.exceptions import OpenMCError
|
||||
|
|
@ -700,7 +700,7 @@ class CMFDRun(object):
|
|||
----------
|
||||
**kwargs
|
||||
All keyword arguments are passed to
|
||||
:func:`openmc.capi.run_in_memory`.
|
||||
:func:`openmc.lib.run_in_memory`.
|
||||
|
||||
"""
|
||||
with self.run_in_memory(**kwargs):
|
||||
|
|
@ -725,7 +725,7 @@ class CMFDRun(object):
|
|||
Parameters
|
||||
----------
|
||||
**kwargs
|
||||
All keyword arguments passed to :func:`openmc.capi.run_in_memory`.
|
||||
All keyword arguments passed to :func:`openmc.lib.run_in_memory`.
|
||||
|
||||
"""
|
||||
# Store intracomm for part of CMFD routine where MPI reduce and
|
||||
|
|
@ -736,7 +736,7 @@ class CMFDRun(object):
|
|||
self._intracomm = MPI.COMM_WORLD
|
||||
|
||||
# Run and pass arguments to C API run_in_memory function
|
||||
with openmc.capi.run_in_memory(**kwargs):
|
||||
with openmc.lib.run_in_memory(**kwargs):
|
||||
self.init()
|
||||
yield
|
||||
self.finalize()
|
||||
|
|
@ -758,7 +758,7 @@ class CMFDRun(object):
|
|||
|
||||
def init(self):
|
||||
""" Initialize CMFDRun instance by setting up CMFD parameters and
|
||||
calling :func:`openmc.capi.simulation_init`
|
||||
calling :func:`openmc.lib.simulation_init`
|
||||
|
||||
"""
|
||||
# Configure CMFD parameters
|
||||
|
|
@ -767,7 +767,7 @@ class CMFDRun(object):
|
|||
# Create tally objects
|
||||
self._create_cmfd_tally()
|
||||
|
||||
if openmc.capi.master():
|
||||
if openmc.lib.master():
|
||||
# Compute and store array indices used to build cross section
|
||||
# arrays
|
||||
self._precompute_array_indices()
|
||||
|
|
@ -780,10 +780,10 @@ class CMFDRun(object):
|
|||
self._initialize_linsolver()
|
||||
|
||||
# Initialize simulation
|
||||
openmc.capi.simulation_init()
|
||||
openmc.lib.simulation_init()
|
||||
|
||||
# Set cmfd_run variable to True through C API
|
||||
openmc.capi.settings.cmfd_run = True
|
||||
openmc.lib.settings.cmfd_run = True
|
||||
|
||||
def next_batch(self):
|
||||
""" Run next batch for CMFDRun.
|
||||
|
|
@ -799,26 +799,26 @@ class CMFDRun(object):
|
|||
self._cmfd_init_batch()
|
||||
|
||||
# Run next batch
|
||||
status = openmc.capi.next_batch()
|
||||
status = openmc.lib.next_batch()
|
||||
|
||||
# Perform CMFD calculations
|
||||
self._execute_cmfd()
|
||||
|
||||
# Write CMFD data to statepoint
|
||||
if openmc.capi.is_statepoint_batch():
|
||||
if openmc.lib.is_statepoint_batch():
|
||||
self.statepoint_write()
|
||||
return status
|
||||
|
||||
def finalize(self):
|
||||
""" Finalize simulation by calling
|
||||
:func:`openmc.capi.simulation_finalize` and print out CMFD timing
|
||||
:func:`openmc.lib.simulation_finalize` and print out CMFD timing
|
||||
information.
|
||||
|
||||
"""
|
||||
# Finalize simuation
|
||||
openmc.capi.simulation_finalize()
|
||||
openmc.lib.simulation_finalize()
|
||||
|
||||
if openmc.capi.master():
|
||||
if openmc.lib.master():
|
||||
# Print out CMFD timing statistics
|
||||
self._write_cmfd_timing_stats()
|
||||
|
||||
|
|
@ -832,13 +832,13 @@ class CMFDRun(object):
|
|||
|
||||
"""
|
||||
if filename is None:
|
||||
batch_str_len = len(str(openmc.capi.settings.batches))
|
||||
batch_str = str(openmc.capi.current_batch()).zfill(batch_str_len)
|
||||
batch_str_len = len(str(openmc.lib.settings.batches))
|
||||
batch_str = str(openmc.lib.current_batch()).zfill(batch_str_len)
|
||||
filename = 'statepoint.{}.h5'.format(batch_str)
|
||||
|
||||
# Call C API statepoint_write to save source distribution with CMFD
|
||||
# feedback
|
||||
openmc.capi.statepoint_write(filename=filename)
|
||||
openmc.lib.statepoint_write(filename=filename)
|
||||
|
||||
# Append CMFD data to statepoint file using h5py
|
||||
self._write_cmfd_statepoint(filename)
|
||||
|
|
@ -852,10 +852,10 @@ class CMFDRun(object):
|
|||
Filename of statepoint
|
||||
|
||||
"""
|
||||
if openmc.capi.master():
|
||||
if openmc.lib.master():
|
||||
with h5py.File(filename, 'a') as f:
|
||||
if 'cmfd' not in f:
|
||||
if openmc.capi.settings.verbosity >= 5:
|
||||
if openmc.lib.settings.verbosity >= 5:
|
||||
print(' Writing CMFD data to {}...'.format(filename))
|
||||
sys.stdout.flush()
|
||||
cmfd_group = f.create_group("cmfd")
|
||||
|
|
@ -918,7 +918,7 @@ class CMFDRun(object):
|
|||
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
|
||||
return openmc.capi._dll.openmc_initialize_linsolver(*args)
|
||||
return openmc.lib._dll.openmc_initialize_linsolver(*args)
|
||||
|
||||
def _write_cmfd_output(self):
|
||||
"""Write CMFD output to buffer at the end of each batch"""
|
||||
|
|
@ -956,13 +956,13 @@ class CMFDRun(object):
|
|||
def _configure_cmfd(self):
|
||||
"""Initialize CMFD parameters and set CMFD input variables"""
|
||||
# Check if restarting simulation from statepoint file
|
||||
if not openmc.capi.settings.restart_run:
|
||||
if not openmc.lib.settings.restart_run:
|
||||
# Define all variables necessary for running CMFD
|
||||
self._initialize_cmfd()
|
||||
|
||||
else:
|
||||
# Reset CMFD parameters from statepoint file
|
||||
path_statepoint = openmc.capi.settings.path_statepoint
|
||||
path_statepoint = openmc.lib.settings.path_statepoint
|
||||
self._reset_cmfd(path_statepoint)
|
||||
|
||||
def _initialize_cmfd(self):
|
||||
|
|
@ -972,7 +972,7 @@ class CMFDRun(object):
|
|||
|
||||
"""
|
||||
# Print message to user and flush output to stdout
|
||||
if openmc.capi.settings.verbosity >= 7 and openmc.capi.master():
|
||||
if openmc.lib.settings.verbosity >= 7 and openmc.lib.master():
|
||||
print(' Configuring CMFD parameters for simulation')
|
||||
sys.stdout.flush()
|
||||
|
||||
|
|
@ -986,7 +986,7 @@ class CMFDRun(object):
|
|||
self._indices[i] = n
|
||||
|
||||
# Check if in continuous energy mode
|
||||
if not openmc.capi.settings.run_CE:
|
||||
if not openmc.lib.settings.run_CE:
|
||||
raise OpenMCError('CMFD must be run in continuous energy mode')
|
||||
|
||||
# Set number of energy groups
|
||||
|
|
@ -1004,10 +1004,10 @@ class CMFDRun(object):
|
|||
if self._mesh.map is not None:
|
||||
check_length('CMFD coremap', self._mesh.map,
|
||||
np.product(self._indices[0:3]))
|
||||
if openmc.capi.master():
|
||||
if openmc.lib.master():
|
||||
self._coremap = np.array(self._mesh.map)
|
||||
else:
|
||||
if openmc.capi.master():
|
||||
if openmc.lib.master():
|
||||
self._coremap = np.ones((np.product(self._indices[0:3])),
|
||||
dtype=int)
|
||||
|
||||
|
|
@ -1020,7 +1020,7 @@ class CMFDRun(object):
|
|||
self._set_tally_window()
|
||||
|
||||
# Define all variables that will exist only on master process
|
||||
if openmc.capi.master():
|
||||
if openmc.lib.master():
|
||||
# Set global albedo
|
||||
if self._mesh.albedo is not None:
|
||||
self._albedo = np.array(self._mesh.albedo)
|
||||
|
|
@ -1062,8 +1062,8 @@ class CMFDRun(object):
|
|||
'file {}'.format(filename))
|
||||
else:
|
||||
# Overwrite CMFD values from statepoint
|
||||
if (openmc.capi.master() and
|
||||
openmc.capi.settings.verbosity >= 5):
|
||||
if (openmc.lib.master() and
|
||||
openmc.lib.settings.verbosity >= 5):
|
||||
print(' Loading CMFD data from {}...'.format(filename))
|
||||
sys.stdout.flush()
|
||||
cmfd_group = f['cmfd']
|
||||
|
|
@ -1099,7 +1099,7 @@ class CMFDRun(object):
|
|||
self._mesh.width = cmfd_mesh['width'][()]
|
||||
|
||||
# Define variables that exist only on master process
|
||||
if openmc.capi.master():
|
||||
if openmc.lib.master():
|
||||
self._time_cmfd = cmfd_group.attrs['time_cmfd']
|
||||
self._time_cmfdbuild = cmfd_group.attrs['time_cmfdbuild']
|
||||
self._time_cmfdsolve = cmfd_group.attrs['time_cmfdsolve']
|
||||
|
|
@ -1132,7 +1132,7 @@ class CMFDRun(object):
|
|||
"""Handles CMFD options at the beginning of each batch"""
|
||||
# Get current batch through C API
|
||||
# Add 1 as next_batch has not been called yet
|
||||
current_batch = openmc.capi.current_batch() + 1
|
||||
current_batch = openmc.lib.current_batch() + 1
|
||||
|
||||
# Check to activate CMFD solver and possible feedback
|
||||
if self._solver_begin == current_batch:
|
||||
|
|
@ -1145,18 +1145,18 @@ class CMFDRun(object):
|
|||
|
||||
def _execute_cmfd(self):
|
||||
"""Runs CMFD calculation on master node"""
|
||||
if openmc.capi.master():
|
||||
if openmc.lib.master():
|
||||
# Start CMFD timer
|
||||
time_start_cmfd = time.time()
|
||||
|
||||
if openmc.capi.current_batch() >= self._tally_begin:
|
||||
if openmc.lib.current_batch() >= self._tally_begin:
|
||||
# Calculate all cross sections based on tally window averages
|
||||
self._compute_xs()
|
||||
|
||||
# Execute CMFD algorithm if CMFD on for current batch
|
||||
if self._cmfd_on:
|
||||
# Run CMFD on single processor on master
|
||||
if openmc.capi.master():
|
||||
if openmc.lib.master():
|
||||
# Create CMFD data based on OpenMC tallies
|
||||
self._set_up_cmfd()
|
||||
|
||||
|
|
@ -1167,7 +1167,7 @@ class CMFDRun(object):
|
|||
self._k_cmfd.append(self._keff)
|
||||
|
||||
# Check to perform adjoint on last batch
|
||||
if (openmc.capi.current_batch() == openmc.capi.settings.batches
|
||||
if (openmc.lib.current_batch() == openmc.lib.settings.batches
|
||||
and self._run_adjoint):
|
||||
self._cmfd_solver_execute(adjoint=True)
|
||||
|
||||
|
|
@ -1178,7 +1178,7 @@ class CMFDRun(object):
|
|||
self._cmfd_reweight()
|
||||
|
||||
# Stop CMFD timer
|
||||
if openmc.capi.master():
|
||||
if openmc.lib.master():
|
||||
time_stop_cmfd = time.time()
|
||||
self._time_cmfd += time_stop_cmfd - time_start_cmfd
|
||||
if self._cmfd_on:
|
||||
|
|
@ -1189,13 +1189,13 @@ class CMFDRun(object):
|
|||
def _cmfd_tally_reset(self):
|
||||
"""Resets all CMFD tallies in memory"""
|
||||
# Print message
|
||||
if (openmc.capi.settings.verbosity >= 6 and openmc.capi.master() and
|
||||
if (openmc.lib.settings.verbosity >= 6 and openmc.lib.master() and
|
||||
not self._reset_every):
|
||||
print(' CMFD tallies reset')
|
||||
sys.stdout.flush()
|
||||
|
||||
# Reset CMFD tallies
|
||||
tallies = openmc.capi.tallies
|
||||
tallies = openmc.lib.tallies
|
||||
for tally_id in self._tally_ids:
|
||||
tallies[tally_id].reset()
|
||||
|
||||
|
|
@ -1379,7 +1379,7 @@ class CMFDRun(object):
|
|||
self._cmfd_src = cmfd_src / np.sum(cmfd_src)
|
||||
|
||||
# Compute entropy
|
||||
if openmc.capi.settings.entropy_on:
|
||||
if openmc.lib.settings.entropy_on:
|
||||
# Compute source times log_2(source)
|
||||
source = self._cmfd_src[self._cmfd_src > 0] \
|
||||
* np.log(self._cmfd_src[self._cmfd_src > 0])/np.log(2)
|
||||
|
|
@ -1403,12 +1403,12 @@ class CMFDRun(object):
|
|||
outside = self._count_bank_sites()
|
||||
|
||||
# Check and raise error if source sites exist outside of CMFD mesh
|
||||
if openmc.capi.master() and outside:
|
||||
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.capi.master():
|
||||
if openmc.lib.master():
|
||||
# Compute normalization factor
|
||||
norm = np.sum(self._sourcecounts) / np.sum(self._cmfd_src)
|
||||
|
||||
|
|
@ -1440,13 +1440,13 @@ class CMFDRun(object):
|
|||
self._weightfactors = self._intracomm.bcast(
|
||||
self._weightfactors)
|
||||
|
||||
m = openmc.capi.meshes[self._mesh_id]
|
||||
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.capi.source_bank()['r']
|
||||
source_energies = openmc.capi.source_bank()['E']
|
||||
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)
|
||||
|
|
@ -1464,13 +1464,13 @@ class CMFDRun(object):
|
|||
|
||||
# Determine weight factor of each particle based on its mesh index
|
||||
# and energy bin and updates its weight
|
||||
openmc.capi.source_bank()['wgt'] *= self._weightfactors[
|
||||
openmc.lib.source_bank()['wgt'] *= self._weightfactors[
|
||||
mesh_ijk[:,0], mesh_ijk[:,1], mesh_ijk[:,2], energy_bins]
|
||||
|
||||
if openmc.capi.master() and np.any(source_energies < energy[0]):
|
||||
if openmc.lib.master() and np.any(source_energies < energy[0]):
|
||||
print(' WARNING: Source point below energy grid')
|
||||
sys.stdout.flush()
|
||||
if openmc.capi.master() and np.any(source_energies > energy[-1]):
|
||||
if openmc.lib.master() and np.any(source_energies > energy[-1]):
|
||||
print(' WARNING: Source point above energy grid')
|
||||
sys.stdout.flush()
|
||||
|
||||
|
|
@ -1484,8 +1484,8 @@ class CMFDRun(object):
|
|||
|
||||
"""
|
||||
# Initialize variables
|
||||
m = openmc.capi.meshes[self._mesh_id]
|
||||
bank = openmc.capi.source_bank()
|
||||
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])
|
||||
|
|
@ -1496,8 +1496,8 @@ class CMFDRun(object):
|
|||
count = np.zeros(self._sourcecounts.shape)
|
||||
|
||||
# Get location and energy of each particle in source bank
|
||||
source_xyz = openmc.capi.source_bank()['r']
|
||||
source_energies = openmc.capi.source_bank()['E']
|
||||
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)
|
||||
|
|
@ -1721,7 +1721,7 @@ class CMFDRun(object):
|
|||
s_o = np.zeros((n,))
|
||||
|
||||
# Set initial guess
|
||||
k_n = openmc.capi.keff()[0]
|
||||
k_n = openmc.lib.keff()[0]
|
||||
k_o = k_n
|
||||
dw = self._w_shift
|
||||
k_s = k_o + dw
|
||||
|
|
@ -1752,7 +1752,7 @@ class CMFDRun(object):
|
|||
s_o /= k_lo
|
||||
|
||||
# Compute new flux with C++ solver
|
||||
innerits = openmc.capi._dll.openmc_run_linsolver(loss.data, s_o,
|
||||
innerits = openmc.lib._dll.openmc_run_linsolver(loss.data, s_o,
|
||||
phi_n, toli)
|
||||
|
||||
# Compute new source vector
|
||||
|
|
@ -1824,7 +1824,7 @@ class CMFDRun(object):
|
|||
iconv = kerr < self._cmfd_ktol and serr < self._stol
|
||||
|
||||
# Print out to user
|
||||
if self._power_monitor and openmc.capi.master():
|
||||
if self._power_monitor and openmc.lib.master():
|
||||
str1 = ' {:d}:'.format(iter)
|
||||
str2 = 'k-eff: {:0.8f}'.format(k_n)
|
||||
str3 = 'k-error: {:.5e}'.format(kerr)
|
||||
|
|
@ -1865,7 +1865,7 @@ class CMFDRun(object):
|
|||
|
||||
"""
|
||||
# Update window size for expanding window if necessary
|
||||
num_cmfd_batches = openmc.capi.current_batch() - self._tally_begin + 1
|
||||
num_cmfd_batches = openmc.lib.current_batch() - self._tally_begin + 1
|
||||
if (self._window_type == 'expanding' and
|
||||
num_cmfd_batches == self._window_size * 2):
|
||||
self._window_size *= 2
|
||||
|
|
@ -1886,7 +1886,7 @@ class CMFDRun(object):
|
|||
nx, ny, nz, ng = self._indices
|
||||
|
||||
# Get tallies in-memory
|
||||
tallies = openmc.capi.tallies
|
||||
tallies = openmc.lib.tallies
|
||||
|
||||
# Set conditional numpy array as boolean vector based on coremap
|
||||
is_accel = self._coremap != _CMFD_NOACCEL
|
||||
|
|
@ -2135,7 +2135,7 @@ class CMFDRun(object):
|
|||
num_accel = self._mat_dim
|
||||
|
||||
# Get openmc k-effective
|
||||
keff = openmc.capi.keff()[0]
|
||||
keff = openmc.lib.keff()[0]
|
||||
|
||||
# Define leakage in each mesh cell and energy group
|
||||
leakage = (((self._current[:,:,:,_CURRENTS['out_right'],:] -
|
||||
|
|
@ -2186,7 +2186,7 @@ class CMFDRun(object):
|
|||
|
||||
# Allocate dimensions for each mesh cell
|
||||
self._hxyz = np.zeros((nx, ny, nz, 3))
|
||||
self._hxyz[:] = openmc.capi.meshes[self._mesh_id].width
|
||||
self._hxyz[:] = openmc.lib.meshes[self._mesh_id].width
|
||||
|
||||
# Allocate flux, cross sections and diffusion coefficient
|
||||
self._flux = np.zeros((nx, ny, nz, ng))
|
||||
|
|
@ -2953,7 +2953,7 @@ class CMFDRun(object):
|
|||
def _create_cmfd_tally(self):
|
||||
"""Creates all tallies in-memory that are used to solve CMFD problem"""
|
||||
# Create Mesh object based on CMFDMesh, stored internally
|
||||
cmfd_mesh = openmc.capi.RegularMesh()
|
||||
cmfd_mesh = openmc.lib.RegularMesh()
|
||||
# Store id of mesh object
|
||||
self._mesh_id = cmfd_mesh.id
|
||||
# Set dimension and parameters of mesh object
|
||||
|
|
@ -2963,29 +2963,29 @@ class CMFDRun(object):
|
|||
width=self._mesh.width)
|
||||
|
||||
# Create mesh Filter object, stored internally
|
||||
mesh_filter = openmc.capi.MeshFilter()
|
||||
mesh_filter = openmc.lib.MeshFilter()
|
||||
# Set mesh for Mesh Filter
|
||||
mesh_filter.mesh = cmfd_mesh
|
||||
|
||||
# Set up energy filters, if applicable
|
||||
if self._energy_filters:
|
||||
# Create Energy Filter object, stored internally
|
||||
energy_filter = openmc.capi.EnergyFilter()
|
||||
energy_filter = openmc.lib.EnergyFilter()
|
||||
# Set bins for Energy Filter
|
||||
energy_filter.bins = self._egrid
|
||||
|
||||
# Create Energy Out Filter object, stored internally
|
||||
energyout_filter = openmc.capi.EnergyoutFilter()
|
||||
energyout_filter = openmc.lib.EnergyoutFilter()
|
||||
# Set bins for Energy Filter
|
||||
energyout_filter.bins = self._egrid
|
||||
|
||||
# Create Mesh Surface Filter object, stored internally
|
||||
meshsurface_filter = openmc.capi.MeshSurfaceFilter()
|
||||
meshsurface_filter = openmc.lib.MeshSurfaceFilter()
|
||||
# Set mesh for Mesh Surface Filter
|
||||
meshsurface_filter.mesh = cmfd_mesh
|
||||
|
||||
# Create Legendre Filter object, stored internally
|
||||
legendre_filter = openmc.capi.LegendreFilter()
|
||||
legendre_filter = openmc.lib.LegendreFilter()
|
||||
# Set order for Legendre Filter
|
||||
legendre_filter.order = 1
|
||||
|
||||
|
|
@ -2993,7 +2993,7 @@ class CMFDRun(object):
|
|||
n_tallies = 4
|
||||
self._tally_ids = []
|
||||
for i in range(n_tallies):
|
||||
cmfd_tally = openmc.capi.Tally()
|
||||
cmfd_tally = openmc.lib.Tally()
|
||||
# Set nuclide bins
|
||||
cmfd_tally.nuclides = ['total']
|
||||
self._tally_ids.append(cmfd_tally.id)
|
||||
|
|
|
|||
|
|
@ -118,7 +118,12 @@ class IncidentNeutron(EqualityMixin):
|
|||
if mt in self.reactions:
|
||||
return self.reactions[mt]
|
||||
else:
|
||||
raise KeyError('No reaction with MT={}.'.format(mt))
|
||||
# Try to create a redundant cross section
|
||||
mts = self.get_reaction_components(mt)
|
||||
if len(mts) > 0:
|
||||
return self._get_redundant_reaction(mt, mts)
|
||||
else:
|
||||
raise KeyError('No reaction with MT={}.'.format(mt))
|
||||
|
||||
def __repr__(self):
|
||||
return "<IncidentNeutron: {}>".format(self.name)
|
||||
|
|
@ -452,7 +457,7 @@ class IncidentNeutron(EqualityMixin):
|
|||
if rx.redundant:
|
||||
photon_rx = any(p.particle == 'photon' for p in rx.products)
|
||||
keep_mts = (4, 16, 103, 104, 105, 106, 107,
|
||||
203, 204, 205, 206, 207, 301, 318, 444)
|
||||
203, 204, 205, 206, 207, 301, 444, 901)
|
||||
if not (photon_rx or rx.mt in keep_mts):
|
||||
continue
|
||||
|
||||
|
|
@ -553,20 +558,6 @@ class IncidentNeutron(EqualityMixin):
|
|||
fer_group = group['fission_energy_release']
|
||||
data.fission_energy = FissionEnergyRelease.from_hdf5(fer_group)
|
||||
|
||||
# Rebuild non-fission heating
|
||||
total_heating = data.reactions.get(301)
|
||||
fission_heating = data.reactions.get(318)
|
||||
if total_heating is not None and fission_heating is not None:
|
||||
non_fission_heating = Reaction(999)
|
||||
non_fission_heating.redundant = True
|
||||
for strT, total in total_heating.xs.items():
|
||||
fission = fission_heating.xs.get(strT)
|
||||
if fission is None:
|
||||
continue
|
||||
non_fission_heating.xs[strT] = Tabulated1D(
|
||||
total.x, total.y - fission(total.x))
|
||||
data.reactions[999] = non_fission_heating
|
||||
|
||||
return data
|
||||
|
||||
@classmethod
|
||||
|
|
@ -602,6 +593,9 @@ class IncidentNeutron(EqualityMixin):
|
|||
|
||||
# If mass number hasn't been specified, make an educated guess
|
||||
zaid, xs = ace.name.split('.')
|
||||
if not xs.endswith('c'):
|
||||
raise TypeError(
|
||||
"{} is not a continuous-energy neutron ACE table.".format(ace))
|
||||
name, element, Z, mass_number, metastable = \
|
||||
get_metadata(int(zaid), metastable_scheme)
|
||||
|
||||
|
|
@ -744,7 +738,7 @@ class IncidentNeutron(EqualityMixin):
|
|||
|
||||
# Instantiate incident neutron data
|
||||
data = cls(name, atomic_number, mass_number, metastable,
|
||||
atomic_weight_ratio, temperature)
|
||||
atomic_weight_ratio, [temperature])
|
||||
|
||||
if (2, 151) in ev.section:
|
||||
data.resonances = res.Resonances.from_endf(ev)
|
||||
|
|
@ -777,9 +771,10 @@ class IncidentNeutron(EqualityMixin):
|
|||
for mt, rx in data.reactions.items():
|
||||
if mt in (19, 20, 21, 38):
|
||||
if (5, mt) not in ev.section:
|
||||
neutron = data.reactions[18].products[0]
|
||||
rx.products[0].applicability = neutron.applicability
|
||||
rx.products[0].distribution = neutron.distribution
|
||||
if rx.products:
|
||||
neutron = data.reactions[18].products[0]
|
||||
rx.products[0].applicability = neutron.applicability
|
||||
rx.products[0].distribution = neutron.distribution
|
||||
|
||||
# Read fission energy release (requires that we already know nu for
|
||||
# fission)
|
||||
|
|
@ -826,34 +821,6 @@ class IncidentNeutron(EqualityMixin):
|
|||
for table in lib.tables[1:]:
|
||||
data.add_temperature_from_ace(table)
|
||||
|
||||
# Add fission energy release data
|
||||
ev = evaluation if evaluation is not None else Evaluation(filename)
|
||||
if (1, 458) in ev.section:
|
||||
data.fission_energy = FissionEnergyRelease.from_endf(ev, data)
|
||||
# Add 318 fission heating data from heatr
|
||||
non_fission_heating = Reaction(999)
|
||||
non_fission_heating.redundant = True
|
||||
fission_heating = Reaction(318)
|
||||
|
||||
heatr_evals = get_evaluations(kwargs["heatr"])
|
||||
for heatr in heatr_evals:
|
||||
temp = "{}K".format(round(heatr.target["temperature"]))
|
||||
f318 = StringIO(heatr.section[3, 318])
|
||||
get_head_record(f318)
|
||||
_params, fission_kerma = get_tab1_record(f318)
|
||||
fission_heating.xs[temp] = fission_kerma
|
||||
total_heating_xs = data.reactions[301].xs.get(temp)
|
||||
if total_heating_xs is None:
|
||||
continue
|
||||
non_fission_heating.xs[temp] = Tabulated1D(
|
||||
fission_kerma.x,
|
||||
total_heating_xs(fission_kerma.x) - fission_kerma.y,
|
||||
breakpoints=fission_kerma.breakpoints,
|
||||
interpolation=fission_kerma.interpolation)
|
||||
|
||||
data.reactions[318] = fission_heating
|
||||
data.reactions[999] = non_fission_heating
|
||||
|
||||
# Add 0K elastic scattering cross section
|
||||
if '0K' not in data.energy:
|
||||
pendf = Evaluation(kwargs['pendf'])
|
||||
|
|
@ -863,6 +830,74 @@ class IncidentNeutron(EqualityMixin):
|
|||
data.energy['0K'] = xs.x
|
||||
data[2].xs['0K'] = xs
|
||||
|
||||
# Add fission energy release data
|
||||
ev = evaluation if evaluation is not None else Evaluation(filename)
|
||||
if (1, 458) in ev.section:
|
||||
data.fission_energy = f = FissionEnergyRelease.from_endf(ev, data)
|
||||
else:
|
||||
f = None
|
||||
|
||||
# For energy deposition, we want to store two different KERMAs:
|
||||
# one calculated assuming outgoing photons deposit their energy
|
||||
# locally, and one calculated assuming they carry their energy
|
||||
# away. This requires two HEATR runs (which make_ace does by
|
||||
# default). Here, we just need to correct for the fact that NJOY
|
||||
# uses a fission heating number of h = EFR, whereas we want:
|
||||
#
|
||||
# 1) h = EFR + EGP + EGD + EB (for local case)
|
||||
# 2) h = EFR + EB (for non-local case)
|
||||
#
|
||||
# The best way to handle this is to subtract off the fission
|
||||
# KERMA that NJOY calculates and add back exactly what we want.
|
||||
|
||||
# If NJOY is not run with HEATR at all, skip everything below
|
||||
if not kwargs["heatr"]:
|
||||
return data
|
||||
|
||||
# Helper function to get a cross section from an ENDF file on a
|
||||
# given energy grid
|
||||
def get_file3_xs(ev, mt, E):
|
||||
file_obj = StringIO(ev.section[3, mt])
|
||||
get_head_record(file_obj)
|
||||
_, xs = get_tab1_record(file_obj)
|
||||
return xs(E)
|
||||
|
||||
heating_local = Reaction(901)
|
||||
heating_local.redundant = True
|
||||
|
||||
heatr_evals = get_evaluations(kwargs["heatr"])
|
||||
heatr_local_evals = get_evaluations(kwargs["heatr"] + "_local")
|
||||
for ev, ev_local in zip(heatr_evals, heatr_local_evals):
|
||||
temp = "{}K".format(round(ev.target["temperature"]))
|
||||
|
||||
# Get total KERMA (originally from ACE file) and energy grid
|
||||
kerma = data.reactions[301].xs[temp]
|
||||
E = kerma.x
|
||||
|
||||
if f is not None:
|
||||
# Replace fission KERMA with (EFR + EB)*sigma_f
|
||||
fission = data.reactions[18].xs[temp]
|
||||
kerma_fission = get_file3_xs(ev, 318, E)
|
||||
kerma.y = kerma.y - kerma_fission + (
|
||||
f.fragments(E) + f.betas(E)) * fission(E)
|
||||
|
||||
# For local KERMA, we first need to get the values from the
|
||||
# HEATR run with photon energy deposited locally and put
|
||||
# them on the same energy grid
|
||||
kerma_local = get_file3_xs(ev_local, 301, E)
|
||||
|
||||
if f is not None:
|
||||
# When photons deposit their energy locally, we replace the
|
||||
# fission KERMA with (EFR + EGP + EGD + EB)*sigma_f
|
||||
kerma_fission_local = get_file3_xs(ev_local, 318, E)
|
||||
kerma_local = kerma_local - kerma_fission_local + (
|
||||
f.fragments(E) + f.prompt_photons(E)
|
||||
+ f.delayed_photons(E) + f.betas(E))*fission(E)
|
||||
|
||||
heating_local.xs[temp] = Tabulated1D(E, kerma_local)
|
||||
|
||||
data.reactions[901] = heating_local
|
||||
|
||||
return data
|
||||
|
||||
def _get_redundant_reaction(self, mt, mts):
|
||||
|
|
@ -881,16 +916,17 @@ class IncidentNeutron(EqualityMixin):
|
|||
Redundant reaction
|
||||
|
||||
"""
|
||||
# Get energy grid
|
||||
strT = self.temperatures[0]
|
||||
energy = self.energy[strT]
|
||||
|
||||
rx = Reaction(mt)
|
||||
xss = [self.reactions[mt_i].xs[strT] for mt_i in mts]
|
||||
idx = min([xs._threshold_idx if hasattr(xs, '_threshold_idx')
|
||||
else 0 for xs in xss])
|
||||
rx.xs[strT] = Tabulated1D(energy[idx:], Sum(xss)(energy[idx:]))
|
||||
rx.xs[strT]._threshold_idx = idx
|
||||
# Get energy grid
|
||||
for strT in self.temperatures:
|
||||
energy = self.energy[strT]
|
||||
xss = [self.reactions[mt_i].xs[strT] for mt_i in mts]
|
||||
idx = min([xs._threshold_idx if hasattr(xs, '_threshold_idx')
|
||||
else 0 for xs in xss])
|
||||
rx.xs[strT] = Tabulated1D(energy[idx:], Sum(xss)(energy[idx:]))
|
||||
rx.xs[strT]._threshold_idx = idx
|
||||
|
||||
rx.redundant = True
|
||||
|
||||
return rx
|
||||
|
|
|
|||
|
|
@ -10,7 +10,7 @@ from . import endf
|
|||
|
||||
|
||||
# For a given MAT number, give a name for the ACE table and a list of ZAID
|
||||
# identifiers
|
||||
# identifiers. This is based on Appendix C in the ENDF manual.
|
||||
ThermalTuple = namedtuple('ThermalTuple', ['name', 'zaids', 'nmix'])
|
||||
_THERMAL_DATA = {
|
||||
1: ThermalTuple('hh2o', [1001], 1),
|
||||
|
|
@ -23,31 +23,77 @@ _THERMAL_DATA = {
|
|||
11: ThermalTuple('dd2o', [1002], 1),
|
||||
12: ThermalTuple('parad', [1002], 1),
|
||||
13: ThermalTuple('orthod', [1002], 1),
|
||||
14: ThermalTuple('dice', [1002], 1),
|
||||
26: ThermalTuple('be', [4009], 1),
|
||||
27: ThermalTuple('bebeo', [4009], 1),
|
||||
31: ThermalTuple('graph', [6000, 6012, 6013], 1),
|
||||
28: ThermalTuple('bebe2c', [4009], 1),
|
||||
30: ThermalTuple('graph', [6000, 6012, 6013], 1),
|
||||
31: ThermalTuple('grph10', [6000, 6012, 6013], 1),
|
||||
32: ThermalTuple('grph30', [6000, 6012, 6013], 1),
|
||||
33: ThermalTuple('lch4', [1001], 1),
|
||||
34: ThermalTuple('sch4', [1001], 1),
|
||||
35: ThermalTuple('sch4p2', [1001], 1),
|
||||
37: ThermalTuple('hch2', [1001], 1),
|
||||
38: ThermalTuple('mesi00', [1001], 1),
|
||||
39: ThermalTuple('lucite', [1001], 1),
|
||||
40: ThermalTuple('benz', [1001, 6000, 6012], 2),
|
||||
41: ThermalTuple('od2o', [8016, 8017, 8018], 1),
|
||||
42: ThermalTuple('tol00', [1001], 1),
|
||||
43: ThermalTuple('sisic', [14028, 14029, 14030], 1),
|
||||
44: ThermalTuple('csic', [6000, 6012, 6013], 1),
|
||||
45: ThermalTuple('ouo2', [8016, 8017, 8018], 1),
|
||||
46: ThermalTuple('obeo', [8016, 8017, 8018], 1),
|
||||
47: ThermalTuple('sio2-a', [8016, 8017, 8018, 14028, 14029, 14030], 3),
|
||||
48: ThermalTuple('uuo2', [92238], 1),
|
||||
48: ThermalTuple('osap00', [92238], 1),
|
||||
49: ThermalTuple('sio2-b', [8016, 8017, 8018, 14028, 14029, 14030], 3),
|
||||
50: ThermalTuple('oice', [8016, 8017, 8018], 1),
|
||||
51: ThermalTuple('od2o', [8016, 8017, 8018], 1),
|
||||
52: ThermalTuple('mg24', [12024], 1),
|
||||
53: ThermalTuple('al27', [13027], 1),
|
||||
55: ThermalTuple('yyh2', [39089], 1),
|
||||
56: ThermalTuple('fe56', [26056], 1),
|
||||
58: ThermalTuple('zrzrh', [40000, 40090, 40091, 40092, 40094, 40096], 1),
|
||||
59: ThermalTuple('cacah2', [20040, 20042, 20043, 20044, 20046, 20048], 1),
|
||||
75: ThermalTuple('ouo2', [8016, 8017, 8018], 1),
|
||||
59: ThermalTuple('si00', [14028], 1),
|
||||
60: ThermalTuple('asap00', [13027], 1),
|
||||
71: ThermalTuple('n-un', [7014, 7015], 1),
|
||||
72: ThermalTuple('u-un', [92238], 1),
|
||||
75: ThermalTuple('uuo2', [8016, 8017, 8018], 1),
|
||||
}
|
||||
|
||||
|
||||
def _get_thermal_data(ev, mat):
|
||||
"""Return appropriate ThermalTuple, accounting for bugs."""
|
||||
|
||||
# JEFF assigns MAT=59 to Ca in CaH2 (which is supposed to be silicon).
|
||||
if ev.info['library'][0] == 'JEFF':
|
||||
if ev.material == 59:
|
||||
if 'CaH2' in ''.join(ev.info['description']):
|
||||
zaids = [20040, 20042, 20043, 20044, 20046, 20048]
|
||||
return ThermalTuple('cacah2', zaids, 1)
|
||||
|
||||
# Before ENDF/B-VIII.0, crystalline graphite was MAT=31
|
||||
if ev.info['library'] != ('ENDF/B', 8, 0):
|
||||
if ev.material == 31:
|
||||
return _THERMAL_DATA[30]
|
||||
|
||||
# ENDF/B incorrectly assigns MAT numbers for UO2
|
||||
#
|
||||
# Material | ENDF Manual | VII.0 | VII.1 | VIII.0
|
||||
# ---------|-------------|-------|-------|-------
|
||||
# O in UO2 | 45 | 75 | 75 | 75
|
||||
# U in UO2 | 75 | 76 | 48 | 48
|
||||
if ev.info['library'][0] == 'ENDF/B':
|
||||
if ev.material == 75:
|
||||
return _THERMAL_DATA[45]
|
||||
version = ev.info['library'][1:]
|
||||
if version in ((7, 1), (8, 0)) and ev.material == 48:
|
||||
return _THERMAL_DATA[75]
|
||||
if version == (7, 0) and ev.material == 76:
|
||||
return _THERMAL_DATA[75]
|
||||
|
||||
# If not a problematic material, use the dictionary as is
|
||||
return _THERMAL_DATA[mat]
|
||||
|
||||
|
||||
_TEMPLATE_RECONR = """
|
||||
reconr / %%%%%%%%%%%%%%%%%%% Reconstruct XS for neutrons %%%%%%%%%%%%%%%%%%%%%%%
|
||||
{nendf} {npendf}
|
||||
|
|
@ -71,7 +117,14 @@ broadr / %%%%%%%%%%%%%%%%%%%%%%% Doppler broaden XS %%%%%%%%%%%%%%%%%%%%%%%%%%%%
|
|||
_TEMPLATE_HEATR = """
|
||||
heatr / %%%%%%%%%%%%%%%%%%%%%%%%% Add heating kerma %%%%%%%%%%%%%%%%%%%%%%%%%%%%
|
||||
{nendf} {nheatr_in} {nheatr} /
|
||||
{mat} 4 /
|
||||
{mat} 4 0 0 0 /
|
||||
302 318 402 444 /
|
||||
"""
|
||||
|
||||
_TEMPLATE_HEATR_LOCAL = """
|
||||
heatr / %%%%%%%%%%%%%%%%% Add heating kerma (local photons) %%%%%%%%%%%%%%%%%%%%
|
||||
{nendf} {nheatr_in} {nheatr_local} /
|
||||
{mat} 4 0 0 1 /
|
||||
302 318 402 444 /
|
||||
"""
|
||||
|
||||
|
|
@ -216,8 +269,7 @@ def make_pendf(filename, pendf='pendf', error=0.001, stdout=False):
|
|||
|
||||
def make_ace(filename, temperatures=None, acer=True, xsdir=None,
|
||||
output_dir=None, pendf=False, error=0.001, broadr=True,
|
||||
heatr=True, gaspr=True, purr=True, evaluation=None,
|
||||
**kwargs):
|
||||
heatr=True, gaspr=True, purr=True, evaluation=None, **kwargs):
|
||||
"""Generate incident neutron ACE file from an ENDF file
|
||||
|
||||
File names can be passed to
|
||||
|
|
@ -320,7 +372,11 @@ def make_ace(filename, temperatures=None, acer=True, xsdir=None,
|
|||
# heatr
|
||||
if heatr:
|
||||
nheatr_in = nlast
|
||||
nheatr = nheatr_in + 1
|
||||
nheatr_local = nheatr_in + 1
|
||||
tapeout[nheatr_local] = (output_dir / "heatr_local") if heatr is True \
|
||||
else heatr + '_local'
|
||||
commands += _TEMPLATE_HEATR_LOCAL
|
||||
nheatr = nheatr_local + 1
|
||||
tapeout[nheatr] = (output_dir / "heatr") if heatr is True else heatr
|
||||
commands += _TEMPLATE_HEATR
|
||||
nlast = nheatr
|
||||
|
|
@ -434,7 +490,8 @@ def make_ace_thermal(filename, filename_thermal, temperatures=None,
|
|||
mat_thermal = ev_thermal.material
|
||||
zsymam_thermal = ev_thermal.target['zsymam']
|
||||
|
||||
data = _THERMAL_DATA[mat_thermal]
|
||||
# Determine name, isotopes based on MAT number
|
||||
data = _get_thermal_data(ev_thermal, mat_thermal)
|
||||
zaids = ' '.join(str(zaid) for zaid in data.zaids[:3])
|
||||
|
||||
# Determine name of library
|
||||
|
|
|
|||
|
|
@ -549,7 +549,9 @@ class IncidentPhoton(EqualityMixin):
|
|||
ace = get_table(ace_or_filename)
|
||||
|
||||
# Get atomic number based on name of ACE table
|
||||
zaid = ace.name.split('.')[0]
|
||||
zaid, xs = ace.name.split('.')
|
||||
if not xs.endswith('p'):
|
||||
raise TypeError("{} is not a photoatomic transport ACE table.".format(ace))
|
||||
Z = get_metadata(int(zaid))[2]
|
||||
|
||||
# Read each reaction
|
||||
|
|
|
|||
|
|
@ -54,9 +54,8 @@ REACTION_NAME = {1: '(n,total)', 2: '(n,elastic)', 4: '(n,level)',
|
|||
198: '(n,n3p)', 199: '(n,3n2pa)', 200: '(n,5n2p)', 203: '(n,Xp)',
|
||||
204: '(n,Xd)', 205: '(n,Xt)', 206: '(n,X3He)', 207: '(n,Xa)',
|
||||
301: 'heating', 444: 'damage-energy',
|
||||
318: "fission-heating", 999: "non-fission-heating",
|
||||
649: '(n,pc)', 699: '(n,dc)', 749: '(n,tc)', 799: '(n,3Hec)',
|
||||
849: '(n,ac)', 891: '(n,2nc)'}
|
||||
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,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)})
|
||||
|
|
|
|||
|
|
@ -33,10 +33,12 @@ _THERMAL_NAMES = {
|
|||
'c_Be': ('be', 'be-metal', 'be-met', 'be00'),
|
||||
'c_BeO': ('beo',),
|
||||
'c_Be_in_BeO': ('bebeo', 'be-beo', 'be-o', 'be/o', 'bbeo00'),
|
||||
'c_Be_in_Be2C': ('bebe2c',),
|
||||
'c_C6H6': ('benz', 'c6h6'),
|
||||
'c_C_in_SiC': ('csic', 'c-sic'),
|
||||
'c_Ca_in_CaH2': ('cah', 'cah00'),
|
||||
'c_D_in_D2O': ('dd2o', 'd-d2o', 'hwtr', 'hw', 'dhw00'),
|
||||
'c_D_in_D2O_ice': ('dice',),
|
||||
'c_Fe56': ('fe', 'fe56', 'fe-56'),
|
||||
'c_Graphite': ('graph', 'grph', 'gr', 'gr00'),
|
||||
'c_Graphite_10p': ('grph10',),
|
||||
|
|
@ -45,6 +47,7 @@ _THERMAL_NAMES = {
|
|||
'c_H_in_CH2': ('hch2', 'poly', 'pol', 'h-poly', 'pol00'),
|
||||
'c_H_in_CH4_liquid': ('lch4', 'lmeth'),
|
||||
'c_H_in_CH4_solid': ('sch4', 'smeth'),
|
||||
'c_H_in_CH4_solid_phase_II': ('sch4p2',),
|
||||
'c_H_in_H2O': ('hh2o', 'h-h2o', 'lwtr', 'lw', 'lw00'),
|
||||
'c_H_in_H2O_solid': ('hice', 'h-ice', 'ice00'),
|
||||
'c_H_in_C5O2H8': ('lucite', 'c5o2h8', 'h-luci'),
|
||||
|
|
@ -600,6 +603,8 @@ class ThermalScattering(EqualityMixin):
|
|||
|
||||
# Get new name that is GND-consistent
|
||||
ace_name, xs = ace.name.split('.')
|
||||
if not xs.endswith('t'):
|
||||
raise TypeError("{} is not a thermal scattering ACE table.".format(ace))
|
||||
name = get_thermal_name(ace_name)
|
||||
|
||||
# Assign temperature to the running list
|
||||
|
|
|
|||
|
|
@ -4,12 +4,11 @@ openmc.deplete
|
|||
|
||||
A depletion front-end tool.
|
||||
"""
|
||||
from sys import exit
|
||||
import sys
|
||||
from unittest.mock import Mock
|
||||
|
||||
from h5py import get_config
|
||||
|
||||
from unittest.mock import Mock
|
||||
|
||||
from .dummy_comm import DummyCommunicator
|
||||
|
||||
try:
|
||||
|
|
@ -22,7 +21,7 @@ try:
|
|||
if not get_config().mpi and comm.size > 1:
|
||||
# Raise exception only on process 0
|
||||
if comm.rank:
|
||||
exit()
|
||||
sys.exit()
|
||||
raise RuntimeError(
|
||||
"Need parallel HDF5 installed to perform depletion with MPI"
|
||||
)
|
||||
|
|
@ -35,7 +34,10 @@ from .nuclide import *
|
|||
from .chain import *
|
||||
from .operator import *
|
||||
from .reaction_rates import *
|
||||
from .abc import *
|
||||
from .atom_number import *
|
||||
from .results import *
|
||||
from .results_list import *
|
||||
from .integrators import *
|
||||
from . import abc
|
||||
from . import cram
|
||||
from . import helpers
|
||||
|
|
|
|||
|
|
@ -5,6 +5,7 @@ to run a full depletion simulation.
|
|||
"""
|
||||
|
||||
from collections import namedtuple
|
||||
from collections import defaultdict
|
||||
from collections.abc import Iterable
|
||||
import os
|
||||
from pathlib import Path
|
||||
|
|
@ -17,12 +18,19 @@ from numpy import nonzero, empty, asarray
|
|||
from uncertainties import ufloat
|
||||
|
||||
from openmc.data import DataLibrary, JOULE_PER_EV
|
||||
from openmc.capi import MaterialFilter, Tally
|
||||
from openmc.lib import MaterialFilter, Tally
|
||||
from openmc.checkvalue import check_type, check_greater_than
|
||||
from .results import Results
|
||||
from .chain import Chain
|
||||
from .results_list import ResultsList
|
||||
|
||||
|
||||
__all__ = [
|
||||
"OperatorResult", "TransportOperator", "ReactionRateHelper",
|
||||
"EnergyHelper", "FissionYieldHelper", "TalliedFissionYieldHelper",
|
||||
"Integrator", "SIIntegrator", "DepSystemSolver"]
|
||||
|
||||
|
||||
OperatorResult = namedtuple('OperatorResult', ['k', 'rates'])
|
||||
OperatorResult.__doc__ = """\
|
||||
Result of applying transport operator
|
||||
|
|
@ -376,14 +384,17 @@ class FissionYieldHelper(ABC):
|
|||
|
||||
Attributes
|
||||
----------
|
||||
constant_yields : dict of str to :class:`openmc.deplete.FissionYield`
|
||||
constant_yields : collections.defaultdict
|
||||
Fission yields for all nuclides that only have one set of
|
||||
fission yield data. Can be accessed as ``{parent: {product: yield}}``
|
||||
fission yield data. Dictionary of form ``{str: {str: float}}``
|
||||
representing yields for ``{parent: {product: yield}}``. Default
|
||||
return object is an empty dictionary
|
||||
|
||||
"""
|
||||
|
||||
def __init__(self, chain_nuclides):
|
||||
self._chain_nuclides = {}
|
||||
self._constant_yields = {}
|
||||
self._constant_yields = defaultdict(dict)
|
||||
|
||||
# Get all nuclides with fission yield data
|
||||
for nuc in chain_nuclides:
|
||||
|
|
@ -407,14 +418,16 @@ class FissionYieldHelper(ABC):
|
|||
Parameters
|
||||
----------
|
||||
local_mat_index : int
|
||||
Index for material tracked on this process that
|
||||
exists in :attr:`local_mat_index` and fits within
|
||||
the first axis in :attr:`results`
|
||||
Index for the material with requested fission yields.
|
||||
Should correspond to the material represented in
|
||||
``mat_indexes[local_mat_index]`` during
|
||||
:meth:`generate_tallies`.
|
||||
|
||||
Returns
|
||||
-------
|
||||
library : dict
|
||||
Dictionary of ``{parent: {product: fyield}}``
|
||||
library : collections.abc.Mapping
|
||||
Dictionary-like object mapping ``{str: {str: float}``.
|
||||
This reflects fission yields for ``{parent: {product: fyield}}``.
|
||||
"""
|
||||
|
||||
@staticmethod
|
||||
|
|
@ -438,7 +451,7 @@ class FissionYieldHelper(ABC):
|
|||
Parameters
|
||||
----------
|
||||
materials : iterable of C-API materials
|
||||
Materials to be used in :class:`openmc.capi.MaterialFilter`
|
||||
Materials to be used in :class:`openmc.lib.MaterialFilter`
|
||||
mat_indexes : iterable of int
|
||||
Indices of tallied materials that will have their fission
|
||||
yields computed by this helper. Necessary as the
|
||||
|
|
@ -520,8 +533,8 @@ class TalliedFissionYieldHelper(FissionYieldHelper):
|
|||
|
||||
Parameters
|
||||
----------
|
||||
materials : iterable of :class:`openmc.capi.Material`
|
||||
Materials to be used in :class:`openmc.capi.MaterialFilter`
|
||||
materials : iterable of :class:`openmc.lib.Material`
|
||||
Materials to be used in :class:`openmc.lib.MaterialFilter`
|
||||
mat_indexes : iterable of int
|
||||
Indices of tallied materials that will have their fission
|
||||
yields computed by this helper. Necessary as the
|
||||
|
|
@ -533,6 +546,7 @@ class TalliedFissionYieldHelper(FissionYieldHelper):
|
|||
|
||||
# Tally group-wise fission reaction rates
|
||||
self._fission_rate_tally = Tally()
|
||||
self._fission_rate_tally.writable = False
|
||||
self._fission_rate_tally.scores = ['fission']
|
||||
|
||||
self._fission_rate_tally.filters = [MaterialFilter(materials)]
|
||||
|
|
@ -842,3 +856,40 @@ class SIIntegrator(Integrator):
|
|||
Results.save(self.operator, [conc], [res_list[-1]], [t, t],
|
||||
p, self._i_res + len(self), proc_time)
|
||||
self.operator.write_bos_data(self._i_res + len(self))
|
||||
|
||||
|
||||
class DepSystemSolver(ABC):
|
||||
r"""Abstract class for solving depletion equations
|
||||
|
||||
Responsible for solving
|
||||
|
||||
.. math::
|
||||
|
||||
\frac{\partial \vec{N}}{\partial t} = \bar{A}\vec{N}(t),
|
||||
|
||||
for :math:`0< t\leq t +\Delta t`, given :math:`\vec{N}(0) = \vec{N}_0`
|
||||
|
||||
"""
|
||||
|
||||
@abstractmethod
|
||||
def __call__(self, A, n0, dt):
|
||||
"""Solve the linear system of equations for depletion
|
||||
|
||||
Parameters
|
||||
----------
|
||||
A : scipy.sparse.csr_matrix
|
||||
Sparse transmutation matrix ``A[j, i]`` desribing rates at
|
||||
which isotope ``i`` transmutes to isotope ``j``
|
||||
n0 : numpy.ndarray
|
||||
Initial compositions, typically given in number of atoms in some
|
||||
material or an atom density
|
||||
dt : float
|
||||
Time [s] of the specific interval to be solved
|
||||
|
||||
Returns
|
||||
-------
|
||||
numpy.ndarray
|
||||
Final compositions after ``dt``. Should be of identical shape
|
||||
to ``n0``.
|
||||
|
||||
"""
|
||||
|
|
|
|||
|
|
@ -45,6 +45,8 @@ _REACTIONS = [
|
|||
]
|
||||
|
||||
|
||||
__all__ = ["Chain"]
|
||||
|
||||
def replace_missing(product, decay_data):
|
||||
"""Replace missing product with suitable decay daughter.
|
||||
|
||||
|
|
@ -398,7 +400,7 @@ class Chain(object):
|
|||
clean_indentation(root_elem)
|
||||
tree.write(str(filename), encoding='utf-8')
|
||||
|
||||
def get_thermal_fission_yields(self):
|
||||
def get_default_fission_yields(self):
|
||||
"""Return fission yields at lowest incident neutron energy
|
||||
|
||||
Used as the default set of fission yields for :meth:`form_matrix`
|
||||
|
|
@ -412,7 +414,7 @@ class Chain(object):
|
|||
names of nuclides with yield data and ``f_yield``
|
||||
is a float for the fission yield.
|
||||
"""
|
||||
out = {}
|
||||
out = defaultdict(dict)
|
||||
for nuc in self.nuclides:
|
||||
if nuc.yield_data is None:
|
||||
continue
|
||||
|
|
@ -440,13 +442,13 @@ class Chain(object):
|
|||
|
||||
See Also
|
||||
--------
|
||||
:meth:`get_thermal_fission_yields`
|
||||
:meth:`get_default_fission_yields`
|
||||
"""
|
||||
matrix = defaultdict(float)
|
||||
reactions = set()
|
||||
|
||||
if fission_yields is None:
|
||||
fission_yields = self.get_thermal_fission_yields()
|
||||
fission_yields = self.get_default_fission_yields()
|
||||
|
||||
for i, nuc in enumerate(self.nuclides):
|
||||
|
||||
|
|
@ -721,7 +723,7 @@ class Chain(object):
|
|||
@property
|
||||
def fission_yields(self):
|
||||
if self._fission_yields is None:
|
||||
self._fission_yields = [self.get_thermal_fission_yields()]
|
||||
self._fission_yields = [self.get_default_fission_yields()]
|
||||
return self._fission_yields
|
||||
|
||||
@fission_yields.setter
|
||||
|
|
|
|||
|
|
@ -3,6 +3,7 @@
|
|||
Implements two different forms of CRAM for use in openmc.deplete.
|
||||
"""
|
||||
|
||||
import numbers
|
||||
from itertools import repeat
|
||||
from multiprocessing import Pool
|
||||
import time
|
||||
|
|
@ -11,9 +12,12 @@ import numpy as np
|
|||
import scipy.sparse as sp
|
||||
import scipy.sparse.linalg as sla
|
||||
|
||||
from . import comm
|
||||
from openmc.checkvalue import check_type, check_length
|
||||
from .abc import DepSystemSolver
|
||||
|
||||
__all__ = ["deplete", "timed_deplete", "CRAM16", "CRAM48"]
|
||||
__all__ = [
|
||||
"deplete", "timed_deplete", "CRAM16", "CRAM48",
|
||||
"Cram16Solver", "Cram48Solver", "IPFCramSolver"]
|
||||
|
||||
|
||||
def deplete(chain, x, rates, dt, matrix_func=None):
|
||||
|
|
@ -83,147 +87,169 @@ def timed_deplete(*args, **kwargs):
|
|||
return time.time() - start, results
|
||||
|
||||
|
||||
def CRAM16(A, n0, dt):
|
||||
"""Chebyshev Rational Approximation Method, order 16
|
||||
class IPFCramSolver(DepSystemSolver):
|
||||
r"""CRAM depletion solver that uses incomplete partial factorization
|
||||
|
||||
Algorithm is the 16th order Chebyshev Rational Approximation Method,
|
||||
implemented in the more stable `incomplete partial fraction (IPF)
|
||||
<https://doi.org/10.13182/NSE15-26>`_ form.
|
||||
Provides a :meth:`__call__` that utilizes an incomplete
|
||||
partial factorization (IPF) for the Chebyshev Rational Approximation
|
||||
Method (CRAM), as described in the following paper: M. Pusa, "`Higher-Order
|
||||
Chebyshev Rational Approximation Method and Application to Burnup Equations
|
||||
<https://doi.org/10.13182/NSE15-26>`_," Nucl. Sci. Eng., 182:3, 297-318.
|
||||
|
||||
Parameters
|
||||
----------
|
||||
A : scipy.linalg.csr_matrix
|
||||
Matrix to take exponent of.
|
||||
n0 : numpy.array
|
||||
Vector to operate a matrix exponent on.
|
||||
dt : float
|
||||
Time to integrate to.
|
||||
alpha : numpy.ndarray
|
||||
Complex residues of poles used in the factorization. Must be a
|
||||
vector with even number of items.
|
||||
theta : numpy.ndarray
|
||||
Complex poles. Must have an equal size as ``alpha``.
|
||||
alpha0 : float
|
||||
Limit of the approximation at infinity
|
||||
|
||||
Returns
|
||||
-------
|
||||
numpy.array
|
||||
Results of the matrix exponent.
|
||||
|
||||
"""
|
||||
|
||||
alpha = np.array([+2.124853710495224e-16,
|
||||
+5.464930576870210e+3 - 3.797983575308356e+4j,
|
||||
+9.045112476907548e+1 - 1.115537522430261e+3j,
|
||||
+2.344818070467641e+2 - 4.228020157070496e+2j,
|
||||
+9.453304067358312e+1 - 2.951294291446048e+2j,
|
||||
+7.283792954673409e+2 - 1.205646080220011e+5j,
|
||||
+3.648229059594851e+1 - 1.155509621409682e+2j,
|
||||
+2.547321630156819e+1 - 2.639500283021502e+1j,
|
||||
+2.394538338734709e+1 - 5.650522971778156e+0j],
|
||||
dtype=np.complex128)
|
||||
theta = np.array([+0.0,
|
||||
+3.509103608414918 + 8.436198985884374j,
|
||||
+5.948152268951177 + 3.587457362018322j,
|
||||
-5.264971343442647 + 16.22022147316793j,
|
||||
+1.419375897185666 + 10.92536348449672j,
|
||||
+6.416177699099435 + 1.194122393370139j,
|
||||
+4.993174737717997 + 5.996881713603942j,
|
||||
-1.413928462488886 + 13.49772569889275j,
|
||||
-10.84391707869699 + 19.27744616718165j],
|
||||
dtype=np.complex128)
|
||||
|
||||
n = A.shape[0]
|
||||
|
||||
alpha0 = 2.124853710495224e-16
|
||||
|
||||
k = 8
|
||||
|
||||
y = np.array(n0, dtype=np.float64)
|
||||
for l in range(1, k+1):
|
||||
y = 2.0*np.real(alpha[l]*sla.spsolve(A*dt - theta[l]*sp.eye(n), y)) + y
|
||||
|
||||
y *= alpha0
|
||||
return y
|
||||
|
||||
|
||||
def CRAM48(A, n0, dt):
|
||||
"""Chebyshev Rational Approximation Method, order 48
|
||||
|
||||
Algorithm is the 48th order Chebyshev Rational Approximation Method,
|
||||
implemented in the more stable `incomplete partial fraction (IPF)
|
||||
<https://doi.org/10.13182/NSE15-26>`_ form.
|
||||
|
||||
Parameters
|
||||
Attributes
|
||||
----------
|
||||
A : scipy.linalg.csr_matrix
|
||||
Matrix to take exponent of.
|
||||
n0 : numpy.array
|
||||
Vector to operate a matrix exponent on.
|
||||
dt : float
|
||||
Time to integrate to.
|
||||
|
||||
Returns
|
||||
-------
|
||||
numpy.array
|
||||
Results of the matrix exponent.
|
||||
alpha : numpy.ndarray
|
||||
Complex residues of poles :attr:`theta` in the incomplete partial
|
||||
factorization. Denoted as :math:`\tilde{\alpha}`
|
||||
theta : numpy.ndarray
|
||||
Complex poles :math:`\theta` of the rational approximation
|
||||
alpha0 : float
|
||||
Limit of the approximation at infinity
|
||||
|
||||
"""
|
||||
|
||||
theta_r = np.array([-4.465731934165702e+1, -5.284616241568964e+0,
|
||||
-8.867715667624458e+0, +3.493013124279215e+0,
|
||||
+1.564102508858634e+1, +1.742097597385893e+1,
|
||||
-2.834466755180654e+1, +1.661569367939544e+1,
|
||||
+8.011836167974721e+0, -2.056267541998229e+0,
|
||||
+1.449208170441839e+1, +1.853807176907916e+1,
|
||||
+9.932562704505182e+0, -2.244223871767187e+1,
|
||||
+8.590014121680897e-1, -1.286192925744479e+1,
|
||||
+1.164596909542055e+1, +1.806076684783089e+1,
|
||||
+5.870672154659249e+0, -3.542938819659747e+1,
|
||||
+1.901323489060250e+1, +1.885508331552577e+1,
|
||||
-1.734689708174982e+1, +1.316284237125190e+1])
|
||||
theta_i = np.array([+6.233225190695437e+1, +4.057499381311059e+1,
|
||||
+4.325515754166724e+1, +3.281615453173585e+1,
|
||||
+1.558061616372237e+1, +1.076629305714420e+1,
|
||||
+5.492841024648724e+1, +1.316994930024688e+1,
|
||||
+2.780232111309410e+1, +3.794824788914354e+1,
|
||||
+1.799988210051809e+1, +5.974332563100539e+0,
|
||||
+2.532823409972962e+1, +5.179633600312162e+1,
|
||||
+3.536456194294350e+1, +4.600304902833652e+1,
|
||||
+2.287153304140217e+1, +8.368200580099821e+0,
|
||||
+3.029700159040121e+1, +5.834381701800013e+1,
|
||||
+1.194282058271408e+0, +3.583428564427879e+0,
|
||||
+4.883941101108207e+1, +2.042951874827759e+1])
|
||||
theta = np.array(theta_r + theta_i * 1j, dtype=np.complex128)
|
||||
def __init__(self, alpha, theta, alpha0):
|
||||
check_type("alpha", alpha, np.ndarray, numbers.Complex)
|
||||
check_type("theta", theta, np.ndarray, numbers.Complex)
|
||||
check_length("theta", theta, alpha.size)
|
||||
check_type("alpha0", alpha0, numbers.Real)
|
||||
self.alpha = alpha
|
||||
self.theta = theta
|
||||
self.alpha0 = alpha0
|
||||
|
||||
alpha_r = np.array([+6.387380733878774e+2, +1.909896179065730e+2,
|
||||
+4.236195226571914e+2, +4.645770595258726e+2,
|
||||
+7.765163276752433e+2, +1.907115136768522e+3,
|
||||
+2.909892685603256e+3, +1.944772206620450e+2,
|
||||
+1.382799786972332e+5, +5.628442079602433e+3,
|
||||
+2.151681283794220e+2, +1.324720240514420e+3,
|
||||
+1.617548476343347e+4, +1.112729040439685e+2,
|
||||
+1.074624783191125e+2, +8.835727765158191e+1,
|
||||
+9.354078136054179e+1, +9.418142823531573e+1,
|
||||
+1.040012390717851e+2, +6.861882624343235e+1,
|
||||
+8.766654491283722e+1, +1.056007619389650e+2,
|
||||
+7.738987569039419e+1, +1.041366366475571e+2])
|
||||
alpha_i = np.array([-6.743912502859256e+2, -3.973203432721332e+2,
|
||||
-2.041233768918671e+3, -1.652917287299683e+3,
|
||||
-1.783617639907328e+4, -5.887068595142284e+4,
|
||||
-9.953255345514560e+3, -1.427131226068449e+3,
|
||||
-3.256885197214938e+6, -2.924284515884309e+4,
|
||||
-1.121774011188224e+3, -6.370088443140973e+4,
|
||||
-1.008798413156542e+6, -8.837109731680418e+1,
|
||||
-1.457246116408180e+2, -6.388286188419360e+1,
|
||||
-2.195424319460237e+2, -6.719055740098035e+2,
|
||||
-1.693747595553868e+2, -1.177598523430493e+1,
|
||||
-4.596464999363902e+3, -1.738294585524067e+3,
|
||||
-4.311715386228984e+1, -2.777743732451969e+2])
|
||||
alpha = np.array(alpha_r + alpha_i * 1j, dtype=np.complex128)
|
||||
n = A.shape[0]
|
||||
def __call__(self, A, n0, dt):
|
||||
"""Solve depletion equations using IPF CRAM
|
||||
|
||||
alpha0 = 2.258038182743983e-47
|
||||
Parameters
|
||||
----------
|
||||
A : scipy.sparse.csr_matrix
|
||||
Sparse transmutation matrix ``A[j, i]`` desribing rates at
|
||||
which isotope ``i`` transmutes to isotope ``j``
|
||||
n0 : numpy.ndarray
|
||||
Initial compositions, typically given in number of atoms in some
|
||||
material or an atom density
|
||||
dt : float
|
||||
Time [s] of the specific interval to be solved
|
||||
|
||||
k = 24
|
||||
Returns
|
||||
-------
|
||||
numpy.ndarray
|
||||
Final compositions after ``dt``
|
||||
|
||||
y = np.array(n0, dtype=np.float64)
|
||||
for l in range(k):
|
||||
y = 2.0*np.real(alpha[l]*sla.spsolve(A*dt - theta[l]*sp.eye(n), y)) + y
|
||||
"""
|
||||
A = sp.csr_matrix(A * dt, dtype=np.float64)
|
||||
y = np.asarray(n0, dtype=np.float64)
|
||||
ident = sp.eye(A.shape[0])
|
||||
for alpha, theta in zip(self.alpha, self.theta):
|
||||
y += 2*np.real(alpha*sla.spsolve(A - theta*ident, y))
|
||||
return y * self.alpha0
|
||||
|
||||
y *= alpha0
|
||||
return y
|
||||
|
||||
# Coefficients for IPF Cram 16
|
||||
c16_alpha = np.array([
|
||||
+5.464930576870210e+3 - 3.797983575308356e+4j,
|
||||
+9.045112476907548e+1 - 1.115537522430261e+3j,
|
||||
+2.344818070467641e+2 - 4.228020157070496e+2j,
|
||||
+9.453304067358312e+1 - 2.951294291446048e+2j,
|
||||
+7.283792954673409e+2 - 1.205646080220011e+5j,
|
||||
+3.648229059594851e+1 - 1.155509621409682e+2j,
|
||||
+2.547321630156819e+1 - 2.639500283021502e+1j,
|
||||
+2.394538338734709e+1 - 5.650522971778156e+0j],
|
||||
dtype=np.complex128)
|
||||
|
||||
c16_theta = np.array([
|
||||
+3.509103608414918 + 8.436198985884374j,
|
||||
+5.948152268951177 + 3.587457362018322j,
|
||||
-5.264971343442647 + 16.22022147316793j,
|
||||
+1.419375897185666 + 10.92536348449672j,
|
||||
+6.416177699099435 + 1.194122393370139j,
|
||||
+4.993174737717997 + 5.996881713603942j,
|
||||
-1.413928462488886 + 13.49772569889275j,
|
||||
-10.84391707869699 + 19.27744616718165j],
|
||||
dtype=np.complex128)
|
||||
|
||||
c16_alpha0 = 2.124853710495224e-16
|
||||
Cram16Solver = IPFCramSolver(c16_alpha, c16_theta, c16_alpha0)
|
||||
CRAM16 = Cram16Solver.__call__
|
||||
|
||||
del c16_alpha, c16_alpha0, c16_theta
|
||||
|
||||
# Coefficients for 48th order IPF Cram
|
||||
|
||||
theta_r = np.array([
|
||||
-4.465731934165702e+1, -5.284616241568964e+0,
|
||||
-8.867715667624458e+0, +3.493013124279215e+0,
|
||||
+1.564102508858634e+1, +1.742097597385893e+1,
|
||||
-2.834466755180654e+1, +1.661569367939544e+1,
|
||||
+8.011836167974721e+0, -2.056267541998229e+0,
|
||||
+1.449208170441839e+1, +1.853807176907916e+1,
|
||||
+9.932562704505182e+0, -2.244223871767187e+1,
|
||||
+8.590014121680897e-1, -1.286192925744479e+1,
|
||||
+1.164596909542055e+1, +1.806076684783089e+1,
|
||||
+5.870672154659249e+0, -3.542938819659747e+1,
|
||||
+1.901323489060250e+1, +1.885508331552577e+1,
|
||||
-1.734689708174982e+1, +1.316284237125190e+1])
|
||||
|
||||
theta_i = np.array([
|
||||
+6.233225190695437e+1, +4.057499381311059e+1,
|
||||
+4.325515754166724e+1, +3.281615453173585e+1,
|
||||
+1.558061616372237e+1, +1.076629305714420e+1,
|
||||
+5.492841024648724e+1, +1.316994930024688e+1,
|
||||
+2.780232111309410e+1, +3.794824788914354e+1,
|
||||
+1.799988210051809e+1, +5.974332563100539e+0,
|
||||
+2.532823409972962e+1, +5.179633600312162e+1,
|
||||
+3.536456194294350e+1, +4.600304902833652e+1,
|
||||
+2.287153304140217e+1, +8.368200580099821e+0,
|
||||
+3.029700159040121e+1, +5.834381701800013e+1,
|
||||
+1.194282058271408e+0, +3.583428564427879e+0,
|
||||
+4.883941101108207e+1, +2.042951874827759e+1])
|
||||
|
||||
c48_theta = np.array(theta_r + theta_i * 1j, dtype=np.complex128)
|
||||
|
||||
alpha_r = np.array([
|
||||
+6.387380733878774e+2, +1.909896179065730e+2,
|
||||
+4.236195226571914e+2, +4.645770595258726e+2,
|
||||
+7.765163276752433e+2, +1.907115136768522e+3,
|
||||
+2.909892685603256e+3, +1.944772206620450e+2,
|
||||
+1.382799786972332e+5, +5.628442079602433e+3,
|
||||
+2.151681283794220e+2, +1.324720240514420e+3,
|
||||
+1.617548476343347e+4, +1.112729040439685e+2,
|
||||
+1.074624783191125e+2, +8.835727765158191e+1,
|
||||
+9.354078136054179e+1, +9.418142823531573e+1,
|
||||
+1.040012390717851e+2, +6.861882624343235e+1,
|
||||
+8.766654491283722e+1, +1.056007619389650e+2,
|
||||
+7.738987569039419e+1, +1.041366366475571e+2])
|
||||
|
||||
alpha_i = np.array([
|
||||
-6.743912502859256e+2, -3.973203432721332e+2,
|
||||
-2.041233768918671e+3, -1.652917287299683e+3,
|
||||
-1.783617639907328e+4, -5.887068595142284e+4,
|
||||
-9.953255345514560e+3, -1.427131226068449e+3,
|
||||
-3.256885197214938e+6, -2.924284515884309e+4,
|
||||
-1.121774011188224e+3, -6.370088443140973e+4,
|
||||
-1.008798413156542e+6, -8.837109731680418e+1,
|
||||
-1.457246116408180e+2, -6.388286188419360e+1,
|
||||
-2.195424319460237e+2, -6.719055740098035e+2,
|
||||
-1.693747595553868e+2, -1.177598523430493e+1,
|
||||
-4.596464999363902e+3, -1.738294585524067e+3,
|
||||
-4.311715386228984e+1, -2.777743732451969e+2])
|
||||
|
||||
c48_alpha = np.array(alpha_r + alpha_i * 1j, dtype=np.complex128)
|
||||
|
||||
c48_alpha0 = 2.258038182743983e-47
|
||||
|
||||
Cram48Solver = IPFCramSolver(c48_alpha, c48_theta, c48_alpha0)
|
||||
|
||||
del c48_alpha, c48_alpha0, c48_theta, alpha_r, alpha_i, theta_r, theta_i
|
||||
|
||||
CRAM48 = Cram48Solver.__call__
|
||||
|
|
|
|||
|
|
@ -1,3 +1,5 @@
|
|||
import sys
|
||||
|
||||
class DummyCommunicator(object):
|
||||
rank = 0
|
||||
size = 1
|
||||
|
|
@ -25,3 +27,6 @@ class DummyCommunicator(object):
|
|||
|
||||
def scatter(self, sendobj, root=0):
|
||||
return sendobj[0]
|
||||
|
||||
def Abort(self, exit_code_or_msg):
|
||||
sys.exit(exit_code_or_msg)
|
||||
|
|
|
|||
|
|
@ -5,11 +5,13 @@ from copy import deepcopy
|
|||
from itertools import product
|
||||
from numbers import Real
|
||||
import bisect
|
||||
from collections import defaultdict
|
||||
|
||||
from numpy import dot, zeros, newaxis
|
||||
|
||||
from . import comm
|
||||
from openmc.checkvalue import check_type, check_greater_than
|
||||
from openmc.capi import (
|
||||
from openmc.lib import (
|
||||
Tally, MaterialFilter, EnergyFilter, EnergyFunctionFilter)
|
||||
from .abc import (
|
||||
ReactionRateHelper, EnergyHelper, FissionYieldHelper,
|
||||
|
|
@ -44,7 +46,7 @@ class DirectReactionRateHelper(ReactionRateHelper):
|
|||
def generate_tallies(self, materials, scores):
|
||||
"""Produce one-group reaction rate tally
|
||||
|
||||
Uses the :mod:`openmc.capi` to generate a tally
|
||||
Uses the :mod:`openmc.lib` to generate a tally
|
||||
of relevant reactions across all burnable materials.
|
||||
|
||||
Parameters
|
||||
|
|
@ -57,6 +59,7 @@ class DirectReactionRateHelper(ReactionRateHelper):
|
|||
``"(n, gamma)"``, needed for the reaction rate tally.
|
||||
"""
|
||||
self._rate_tally = Tally()
|
||||
self._rate_tally.writable = False
|
||||
self._rate_tally.scores = scores
|
||||
self._rate_tally.filters = [MaterialFilter(materials)]
|
||||
|
||||
|
|
@ -156,6 +159,57 @@ class ChainFissionHelper(EnergyHelper):
|
|||
self._energy += dot(fission_rates, self._fission_q_vector)
|
||||
|
||||
|
||||
class EnergyScoreHelper(EnergyHelper):
|
||||
"""Class responsible for obtaining system energy via a tally score
|
||||
|
||||
Parameters
|
||||
----------
|
||||
score : string
|
||||
Valid score to use when obtaining system energy from OpenMC.
|
||||
Defaults to "heating-local"
|
||||
|
||||
Attributes
|
||||
----------
|
||||
nuclides : list of str
|
||||
List of nuclides with reaction rates. Not needed, but provided
|
||||
for a consistent API across other :class:`EnergyHelper`
|
||||
energy : float
|
||||
System energy [eV] computed from the tally. Will be zero for
|
||||
all MPI processes that are not the "master" process to avoid
|
||||
artificially increasing the tallied energy.
|
||||
score : str
|
||||
Score used to obtain system energy
|
||||
|
||||
"""
|
||||
|
||||
def __init__(self, score="heating-local"):
|
||||
super().__init__()
|
||||
self.score = score
|
||||
self._tally = None
|
||||
|
||||
def prepare(self, *args, **kwargs):
|
||||
"""Create a tally for system energy production
|
||||
|
||||
Input arguments are not used, as the only information needed
|
||||
is :attr:`score`
|
||||
|
||||
"""
|
||||
self._tally = Tally()
|
||||
self._tally.writable = False
|
||||
self._tally.scores = [self.score]
|
||||
|
||||
def reset(self):
|
||||
"""Obtain system energy from tally
|
||||
|
||||
Only the master process, ``comm.rank == 0`` will
|
||||
have a non-zero :attr:`energy` taken from the tally.
|
||||
This avoids accidentally scaling the system power by
|
||||
the number of MPI processes
|
||||
"""
|
||||
super().reset()
|
||||
if comm.rank == 0:
|
||||
self._energy = self._tally.results[0, 0, 1]
|
||||
|
||||
# ------------------------------------
|
||||
# Helper for collapsing fission yields
|
||||
# ------------------------------------
|
||||
|
|
@ -179,9 +233,11 @@ class ConstantFissionYieldHelper(FissionYieldHelper):
|
|||
|
||||
Attributes
|
||||
----------
|
||||
constant_yields : dict of str to :class:`openmc.deplete.FissionYield`
|
||||
constant_yields : collections.defaultdict
|
||||
Fission yields for all nuclides that only have one set of
|
||||
fission yield data. Can be accessed as ``{parent: {product: yield}}``
|
||||
fission yield data. Dictionary of form ``{str: {str: float}}``
|
||||
representing yields for ``{parent: {product: yield}}``. Default
|
||||
return object is an empty dictionary
|
||||
energy : float
|
||||
Energy of fission yield libraries.
|
||||
"""
|
||||
|
|
@ -237,7 +293,7 @@ class ConstantFissionYieldHelper(FissionYieldHelper):
|
|||
|
||||
Returns
|
||||
-------
|
||||
library : dict
|
||||
library : collections.defaultdict
|
||||
Dictionary of ``{parent: {product: fyield}}``
|
||||
"""
|
||||
return self.constant_yields
|
||||
|
|
@ -282,6 +338,11 @@ class FissionYieldCutoffHelper(TalliedFissionYieldHelper):
|
|||
fast_yields : dict
|
||||
Dictionary of the form ``{parent: {product: yield}}``
|
||||
with fast yields
|
||||
constant_yields : collections.defaultdict
|
||||
Fission yields for all nuclides that only have one set of
|
||||
fission yield data. Dictionary of form ``{str: {str: float}}``
|
||||
representing yields for ``{parent: {product: yield}}``. Default
|
||||
return object is an empty dictionary
|
||||
results : numpy.ndarray
|
||||
Array of fission rate fractions with shape
|
||||
``(n_mats, 2, n_nucs)``. ``results[:, 0]``
|
||||
|
|
@ -362,13 +423,13 @@ class FissionYieldCutoffHelper(TalliedFissionYieldHelper):
|
|||
def generate_tallies(self, materials, mat_indexes):
|
||||
"""Use C API to produce a fission rate tally in burnable materials
|
||||
|
||||
Include a :class:`openmc.capi.EnergyFilter` to tally fission rates
|
||||
Include a :class:`openmc.lib.EnergyFilter` to tally fission rates
|
||||
above and below cutoff energy.
|
||||
|
||||
Parameters
|
||||
----------
|
||||
materials : iterable of :class:`openmc.capi.Material`
|
||||
Materials to be used in :class:`openmc.capi.MaterialFilter`
|
||||
materials : iterable of :class:`openmc.lib.Material`
|
||||
Materials to be used in :class:`openmc.lib.MaterialFilter`
|
||||
mat_indexes : iterable of int
|
||||
Indices of tallied materials that will have their fission
|
||||
yields computed by this helper. Necessary as the
|
||||
|
|
@ -417,7 +478,7 @@ class FissionYieldCutoffHelper(TalliedFissionYieldHelper):
|
|||
|
||||
Returns
|
||||
-------
|
||||
library : dict
|
||||
library : collections.defaultdict
|
||||
Dictionary of ``{parent: {product: fyield}}``
|
||||
"""
|
||||
yields = self.constant_yields
|
||||
|
|
@ -469,9 +530,11 @@ class AveragedFissionYieldHelper(TalliedFissionYieldHelper):
|
|||
|
||||
Attributes
|
||||
----------
|
||||
constant_yields : dict of str to :class:`openmc.deplete.FissionYield`
|
||||
constant_yields : collections.defaultdict
|
||||
Fission yields for all nuclides that only have one set of
|
||||
fission yield data. Can be accessed as ``{parent: {product: yield}}``
|
||||
fission yield data. Dictionary of form ``{str: {str: float}}``
|
||||
representing yields for ``{parent: {product: yield}}``. Default
|
||||
return object is an empty dictionary
|
||||
results : None or numpy.ndarray
|
||||
If tallies have been generated and unpacked, then the array will
|
||||
have shape ``(n_mats, n_tnucs)``, where ``n_mats`` is the number
|
||||
|
|
@ -490,8 +553,8 @@ class AveragedFissionYieldHelper(TalliedFissionYieldHelper):
|
|||
|
||||
Parameters
|
||||
----------
|
||||
materials : iterable of :class:`openmc.capi.Material`
|
||||
Materials to be used in :class:`openmc.capi.MaterialFilter`
|
||||
materials : iterable of :class:`openmc.lib.Material`
|
||||
Materials to be used in :class:`openmc.lib.MaterialFilter`
|
||||
mat_indexes : iterable of int
|
||||
Indices of tallied materials that will have their fission
|
||||
yields computed by this helper. Necessary as the
|
||||
|
|
@ -509,6 +572,7 @@ class AveragedFissionYieldHelper(TalliedFissionYieldHelper):
|
|||
func_filter = EnergyFunctionFilter()
|
||||
func_filter.set_data((0, self._upper_energy), (0, self._upper_energy))
|
||||
weighted_tally = Tally()
|
||||
weighted_tally.writable = False
|
||||
weighted_tally.scores = ['fission']
|
||||
weighted_tally.filters = filters + [func_filter]
|
||||
self._weighted_tally = weighted_tally
|
||||
|
|
@ -569,12 +633,13 @@ class AveragedFissionYieldHelper(TalliedFissionYieldHelper):
|
|||
|
||||
Returns
|
||||
-------
|
||||
library : dict
|
||||
Dictionary of ``{parent: {product: fyield}}``
|
||||
library : collections.defaultdict
|
||||
Dictionary of ``{parent: {product: fyield}}``. Default return
|
||||
value is an empty dictionary
|
||||
"""
|
||||
if not self._tally_nucs:
|
||||
return self.constant_yields
|
||||
mat_yields = {}
|
||||
mat_yields = defaultdict(dict)
|
||||
average_energies = self.results[local_mat_index]
|
||||
for avg_e, nuc in zip(average_energies, self._tally_nucs):
|
||||
nuc_energies = nuc.yield_energies
|
||||
|
|
|
|||
|
|
@ -17,6 +17,10 @@ from numpy import empty
|
|||
|
||||
from openmc.checkvalue import check_type
|
||||
|
||||
__all__ = [
|
||||
"DecayTuple", "ReactionTuple", "Nuclide", "FissionYield",
|
||||
"FissionYieldDistribution"]
|
||||
|
||||
|
||||
DecayTuple = namedtuple('DecayTuple', 'type target branching_ratio')
|
||||
DecayTuple.__doc__ = """\
|
||||
|
|
|
|||
|
|
@ -7,19 +7,21 @@ densities is all done in-memory instead of through the filesystem.
|
|||
|
||||
"""
|
||||
|
||||
import sys
|
||||
import copy
|
||||
from collections import OrderedDict
|
||||
from itertools import chain
|
||||
import os
|
||||
import time
|
||||
import xml.etree.ElementTree as ET
|
||||
from warnings import warn
|
||||
|
||||
import h5py
|
||||
import numpy as np
|
||||
from uncertainties import ufloat
|
||||
|
||||
import openmc
|
||||
import openmc.capi
|
||||
import openmc.lib
|
||||
from . import comm
|
||||
from .abc import TransportOperator, OperatorResult
|
||||
from .atom_number import AtomNumber
|
||||
|
|
@ -27,7 +29,10 @@ from .reaction_rates import ReactionRates
|
|||
from .results_list import ResultsList
|
||||
from .helpers import (
|
||||
DirectReactionRateHelper, ChainFissionHelper, ConstantFissionYieldHelper,
|
||||
FissionYieldCutoffHelper, AveragedFissionYieldHelper)
|
||||
FissionYieldCutoffHelper, AveragedFissionYieldHelper, EnergyScoreHelper)
|
||||
|
||||
|
||||
__all__ = ["Operator", "OperatorResult"]
|
||||
|
||||
|
||||
def _distribute(items):
|
||||
|
|
@ -78,9 +83,15 @@ class Operator(TransportOperator):
|
|||
diff_burnable_mats : bool, optional
|
||||
Whether to differentiate burnable materials with multiple instances.
|
||||
Default: False.
|
||||
energy_mode : {"energy-deposition", "fission-q"}
|
||||
Indicator for computing system energy. ``"energy-deposition"`` will
|
||||
compute with a single energy deposition tally, taking fission energy
|
||||
release data and heating into consideration. ``"fission-q"`` will
|
||||
use the fission Q values from the depletion chain
|
||||
fission_q : dict, optional
|
||||
Dictionary of nuclides and their fission Q values [eV]. If not given,
|
||||
values will be pulled from the ``chain_file``.
|
||||
values will be pulled from the ``chain_file``. Only applicable
|
||||
if ``"energy_mode" == "fission-q"``
|
||||
dilute_initial : float, optional
|
||||
Initial atom density [atoms/cm^3] to add for nuclides that are zero
|
||||
in initial condition to ensure they exist in the decay chain.
|
||||
|
|
@ -128,7 +139,7 @@ class Operator(TransportOperator):
|
|||
burnable_mats : list of str
|
||||
All burnable material IDs
|
||||
heavy_metal : float
|
||||
Initial heavy metal inventory
|
||||
Initial heavy metal inventory [g]
|
||||
local_mats : list of str
|
||||
All burnable material IDs being managed by a single process
|
||||
prev_res : ResultsList or None
|
||||
|
|
@ -144,13 +155,22 @@ class Operator(TransportOperator):
|
|||
}
|
||||
|
||||
def __init__(self, geometry, settings, chain_file=None, prev_results=None,
|
||||
diff_burnable_mats=False, fission_q=None,
|
||||
dilute_initial=1.0e3, fission_yield_mode="constant",
|
||||
fission_yield_opts=None):
|
||||
diff_burnable_mats=False, energy_mode="fission-q",
|
||||
fission_q=None, dilute_initial=1.0e3,
|
||||
fission_yield_mode="constant", fission_yield_opts=None):
|
||||
if fission_yield_mode not in self._fission_helpers:
|
||||
raise KeyError(
|
||||
"fission_yield_mode must be one of {}, not {}".format(
|
||||
", ".join(self._fission_helpers), fission_yield_mode))
|
||||
if energy_mode == "energy-deposition":
|
||||
if fission_q is not None:
|
||||
warn("Fission Q dictionary not used if energy deposition "
|
||||
"is used")
|
||||
fission_q = None
|
||||
elif energy_mode != "fission-q":
|
||||
raise ValueError(
|
||||
"energy_mode {} not supported. Must be energy-deposition "
|
||||
"or fission-q".format(energy_mode))
|
||||
super().__init__(chain_file, fission_q, dilute_initial, prev_results)
|
||||
self.round_number = False
|
||||
self.prev_res = None
|
||||
|
|
@ -204,7 +224,11 @@ class Operator(TransportOperator):
|
|||
# Get classes to assist working with tallies
|
||||
self._rate_helper = DirectReactionRateHelper(
|
||||
self.reaction_rates.n_nuc, self.reaction_rates.n_react)
|
||||
self._energy_helper = ChainFissionHelper()
|
||||
if energy_mode == "fission-q":
|
||||
self._energy_helper = ChainFissionHelper()
|
||||
else:
|
||||
score = "heating" if settings.photon_transport else "heating-local"
|
||||
self._energy_helper = EnergyScoreHelper(score)
|
||||
|
||||
# Select and create fission yield helper
|
||||
fission_helper = self._fission_helpers[fission_yield_mode]
|
||||
|
|
@ -216,6 +240,10 @@ class Operator(TransportOperator):
|
|||
def __call__(self, vec, power):
|
||||
"""Runs a simulation.
|
||||
|
||||
Simulation will abort under the following circumstances:
|
||||
|
||||
1) No energy is computed using OpenMC tallies.
|
||||
|
||||
Parameters
|
||||
----------
|
||||
vec : list of numpy.ndarray
|
||||
|
|
@ -235,8 +263,6 @@ class Operator(TransportOperator):
|
|||
# Update status
|
||||
self.number.set_density(vec)
|
||||
|
||||
time_start = time.time()
|
||||
|
||||
# Update material compositions and tally nuclides
|
||||
self._update_materials()
|
||||
nuclides = self._get_tally_nuclides()
|
||||
|
|
@ -245,10 +271,8 @@ class Operator(TransportOperator):
|
|||
self._yield_helper.update_tally_nuclides(nuclides)
|
||||
|
||||
# Run OpenMC
|
||||
openmc.capi.reset()
|
||||
openmc.capi.run()
|
||||
|
||||
time_openmc = time.time()
|
||||
openmc.lib.reset()
|
||||
openmc.lib.run()
|
||||
|
||||
# Extract results
|
||||
op_result = self._unpack_tallies_and_normalize(power)
|
||||
|
|
@ -264,7 +288,7 @@ class Operator(TransportOperator):
|
|||
step : int
|
||||
Current depletion step including restarts
|
||||
"""
|
||||
openmc.capi.statepoint_write(
|
||||
openmc.lib.statepoint_write(
|
||||
"openmc_simulation_n{}.h5".format(step),
|
||||
write_source=False)
|
||||
|
||||
|
|
@ -438,10 +462,10 @@ class Operator(TransportOperator):
|
|||
|
||||
# Initialize OpenMC library
|
||||
comm.barrier()
|
||||
openmc.capi.init(intracomm=comm)
|
||||
openmc.lib.init(intracomm=comm)
|
||||
|
||||
# Generate tallies in memory
|
||||
materials = [openmc.capi.materials[int(i)]
|
||||
materials = [openmc.lib.materials[int(i)]
|
||||
for i in self.burnable_mats]
|
||||
self._rate_helper.generate_tallies(materials, self.chain.reactions)
|
||||
self._energy_helper.prepare(
|
||||
|
|
@ -456,7 +480,7 @@ class Operator(TransportOperator):
|
|||
|
||||
def finalize(self):
|
||||
"""Finalize a depletion simulation and release resources."""
|
||||
openmc.capi.finalize()
|
||||
openmc.lib.finalize()
|
||||
|
||||
def _update_materials(self):
|
||||
"""Updates material compositions in OpenMC on all processes."""
|
||||
|
|
@ -491,7 +515,7 @@ class Operator(TransportOperator):
|
|||
number_i[mat, nuc] = 0.0
|
||||
|
||||
# Update densities on C API side
|
||||
mat_internal = openmc.capi.materials[int(mat)]
|
||||
mat_internal = openmc.lib.materials[int(mat)]
|
||||
mat_internal.set_densities(nuclides, densities)
|
||||
|
||||
#TODO Update densities on the Python side, otherwise the
|
||||
|
|
@ -581,7 +605,7 @@ class Operator(TransportOperator):
|
|||
rates.fill(0.0)
|
||||
|
||||
# Get k and uncertainty
|
||||
k_combined = ufloat(*openmc.capi.keff())
|
||||
k_combined = ufloat(*openmc.lib.keff())
|
||||
|
||||
# Extract tally bins
|
||||
nuclides = self._rate_helper.nuclides
|
||||
|
|
@ -634,6 +658,15 @@ class Operator(TransportOperator):
|
|||
# J / s / source neutron
|
||||
energy = comm.allreduce(self._energy_helper.energy)
|
||||
|
||||
# Guard against divide by zero
|
||||
if energy == 0:
|
||||
if comm.rank == 0:
|
||||
sys.stderr.flush()
|
||||
print(" No energy reported from OpenMC tallies. Do your HDF5 "
|
||||
"files have heating data?\n", file=sys.stderr, flush=True)
|
||||
comm.barrier()
|
||||
comm.Abort(1)
|
||||
|
||||
# Scale reaction rates to obtain units of reactions/sec
|
||||
rates *= power / energy
|
||||
|
||||
|
|
|
|||
|
|
@ -7,6 +7,9 @@ from collections import OrderedDict
|
|||
import numpy as np
|
||||
|
||||
|
||||
__all__ = ["ReactionRates"]
|
||||
|
||||
|
||||
class ReactionRates(np.ndarray):
|
||||
"""Reaction rates resulting from a transport operator call
|
||||
|
||||
|
|
|
|||
|
|
@ -16,6 +16,9 @@ from .reaction_rates import ReactionRates
|
|||
_VERSION_RESULTS = (1, 0)
|
||||
|
||||
|
||||
__all__ = ["Results"]
|
||||
|
||||
|
||||
class Results(object):
|
||||
"""Output of a depletion run
|
||||
|
||||
|
|
|
|||
|
|
@ -5,6 +5,9 @@ from .results import Results, _VERSION_RESULTS
|
|||
from openmc.checkvalue import check_filetype_version
|
||||
|
||||
|
||||
__all__ = ["ResultsList"]
|
||||
|
||||
|
||||
class ResultsList(list):
|
||||
"""A list of openmc.deplete.Results objects
|
||||
|
||||
|
|
@ -137,7 +140,7 @@ class ResultsList(list):
|
|||
def get_depletion_time(self):
|
||||
"""Return an array of the average time to deplete a material
|
||||
|
||||
..note::
|
||||
.. note::
|
||||
|
||||
Will have one fewer row than number of other methods,
|
||||
like :meth:`get_eigenvalues`, because no depletion
|
||||
|
|
@ -145,7 +148,6 @@ class ResultsList(list):
|
|||
|
||||
Returns
|
||||
-------
|
||||
|
||||
times : :class:`numpy.ndarray`
|
||||
Vector of average time to deplete a single material
|
||||
across all processes and materials.
|
||||
|
|
|
|||
|
|
@ -1,14 +1,14 @@
|
|||
"""
|
||||
This module provides bindings to C functions defined by OpenMC shared library.
|
||||
When the :mod:`openmc` package is imported, the OpenMC shared library is
|
||||
automatically loaded. Calls to the OpenMC library can then be via functions or
|
||||
objects in the :mod:`openmc.capi` subpackage, for example:
|
||||
This module provides bindings to C/C++ functions defined by OpenMC shared
|
||||
library. When the :mod:`openmc.lib` package is imported, the OpenMC shared
|
||||
library is automatically loaded. Calls to the OpenMC library can then be via
|
||||
functions or objects in :mod:`openmc.lib`, for example:
|
||||
|
||||
.. code-block:: python
|
||||
|
||||
openmc.capi.init()
|
||||
openmc.capi.run()
|
||||
openmc.capi.finalize()
|
||||
openmc.lib.init()
|
||||
openmc.lib.run()
|
||||
openmc.lib.finalize()
|
||||
|
||||
"""
|
||||
|
||||
|
|
@ -33,7 +33,7 @@ if os.environ.get('READTHEDOCS', None) != 'True':
|
|||
else:
|
||||
# For documentation builds, we don't actually have the shared library
|
||||
# available. Instead, we create a mock object so that when the modules
|
||||
# within the openmc.capi package try to configure arguments and return
|
||||
# within the openmc.lib package try to configure arguments and return
|
||||
# values for symbols, no errors occur
|
||||
from unittest.mock import Mock
|
||||
_dll = Mock()
|
||||
|
|
@ -63,7 +63,7 @@ class Cell(_FortranObjectWithID):
|
|||
|
||||
This class exposes a cell that is stored internally in the OpenMC
|
||||
library. To obtain a view of a cell with a given ID, use the
|
||||
:data:`openmc.capi.cells` mapping.
|
||||
:data:`openmc.lib.cells` mapping.
|
||||
|
||||
Parameters
|
||||
----------
|
||||
|
|
@ -11,7 +11,7 @@ from numpy.ctypeslib import as_array
|
|||
from openmc.exceptions import AllocationError
|
||||
from . import _dll
|
||||
from .error import _error_handler
|
||||
import openmc.capi
|
||||
import openmc.lib
|
||||
|
||||
|
||||
class _Bank(Structure):
|
||||
|
|
@ -127,7 +127,7 @@ def find_cell(xyz):
|
|||
|
||||
Returns
|
||||
-------
|
||||
openmc.capi.Cell
|
||||
openmc.lib.Cell
|
||||
Cell containing the point
|
||||
int
|
||||
If the cell at the given point is repeated in the geometry, this
|
||||
|
|
@ -137,7 +137,7 @@ def find_cell(xyz):
|
|||
index = c_int32()
|
||||
instance = c_int32()
|
||||
_dll.openmc_find_cell((c_double*3)(*xyz), index, instance)
|
||||
return openmc.capi.Cell(index=index.value), instance.value
|
||||
return openmc.lib.Cell(index=index.value), instance.value
|
||||
|
||||
|
||||
def find_material(xyz):
|
||||
|
|
@ -150,7 +150,7 @@ def find_material(xyz):
|
|||
|
||||
Returns
|
||||
-------
|
||||
openmc.capi.Material or None
|
||||
openmc.lib.Material or None
|
||||
Material containing the point, or None is no material is found
|
||||
|
||||
"""
|
||||
|
|
@ -158,8 +158,8 @@ def find_material(xyz):
|
|||
instance = c_int32()
|
||||
_dll.openmc_find_cell((c_double*3)(*xyz), index, instance)
|
||||
|
||||
mats = openmc.capi.Cell(index=index.value).fill
|
||||
if isinstance(mats, (openmc.capi.Material, type(None))):
|
||||
mats = openmc.lib.Cell(index=index.value).fill
|
||||
if isinstance(mats, (openmc.lib.Material, type(None))):
|
||||
return mats
|
||||
else:
|
||||
return mats[instance.value]
|
||||
|
|
@ -225,21 +225,21 @@ def iter_batches():
|
|||
|
||||
This function returns a generator-iterator that allows Python code to be run
|
||||
between batches in an OpenMC simulation. It should be used in conjunction
|
||||
with :func:`openmc.capi.simulation_init` and
|
||||
:func:`openmc.capi.simulation_finalize`. For example:
|
||||
with :func:`openmc.lib.simulation_init` and
|
||||
:func:`openmc.lib.simulation_finalize`. For example:
|
||||
|
||||
.. code-block:: Python
|
||||
|
||||
with openmc.capi.run_in_memory():
|
||||
openmc.capi.simulation_init()
|
||||
for _ in openmc.capi.iter_batches():
|
||||
with openmc.lib.run_in_memory():
|
||||
openmc.lib.simulation_init()
|
||||
for _ in openmc.lib.iter_batches():
|
||||
# Look at convergence of tallies, for example
|
||||
...
|
||||
openmc.capi.simulation_finalize()
|
||||
openmc.lib.simulation_finalize()
|
||||
|
||||
See Also
|
||||
--------
|
||||
openmc.capi.next_batch
|
||||
openmc.lib.next_batch
|
||||
|
||||
"""
|
||||
while True:
|
||||
|
|
@ -365,11 +365,11 @@ def run_in_memory(**kwargs):
|
|||
block, all memory that was allocated during the block is freed. For
|
||||
example::
|
||||
|
||||
with openmc.capi.run_in_memory():
|
||||
with openmc.lib.run_in_memory():
|
||||
for i in range(n_iters):
|
||||
openmc.capi.reset()
|
||||
openmc.lib.reset()
|
||||
do_stuff()
|
||||
openmc.capi.run()
|
||||
openmc.lib.run()
|
||||
|
||||
Parameters
|
||||
----------
|
||||
Some files were not shown because too many files have changed in this diff Show more
Loading…
Add table
Add a link
Reference in a new issue