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Sam Shaner 2016-09-11 15:15:18 -04:00
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86
docs/source/io_formats/nuclear_data.rst
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@ -16,29 +16,53 @@ Incident Neutron Data
- **metastable** (*int*) -- Metastable state (0=ground, 1=first
excited, etc.)
- **atomic_weight_ratio** (*double*) -- Mass in units of neutron masses
- **temperature** (*double*) -- Temperature in MeV
- **n_reaction** (*int*) -- Number of reactions
:Datasets: - **energy** (*double[]*) -- Energy points at which cross sections are tabulated
**/<nuclide name>/kTs/**
<TTT>K is the temperature in Kelvin, rounded to the nearest integer, of the
temperature-dependent data set. For example, the data set corresponding to
300 Kelvin would be located at `300K`.
:Datasets:
- **<TTT>K** (*double*) -- kT values (in MeV) for each Temperature
TTT (in Kelvin)
**/<nuclide name>/reactions/reaction_<mt>/**
:Attributes: - **mt** (*int*) -- ENDF MT reaction number
- **label** (*char[]*) -- Name of the reaction
- **Q_value** (*double*) -- Q value in MeV
- **threshold_idx** (*int*) -- Index on the energy grid that the
reaction threshold corresponds to
- **center_of_mass** (*int*) -- Whether the reference frame for
scattering is center-of-mass (1) or laboratory (0)
- **n_product** (*int*) -- Number of reaction products
:Datasets: - **xs** (*double[]*) -- Cross section values tabulated against the nuclide energy grid
**/<nuclide name>/reactions/reaction_<mt>/<TTT>K/**
<TTT>K is the temperature in Kelvin, rounded to the nearest integer, of the
temperature-dependent data set. For example, the data set corresponding to
300 Kelvin would be located at `300K`.
:Datasets:
- **xs** (*double[]*) -- Cross section values tabulated against the
nuclide energy grid for temperature TTT (in Kelvin)
:Attributes:
- **threshold_idx** (*int*) -- Index on the energy
grid that the reaction threshold corresponds to for
temperature TTT (in Kelvin)
**/<nuclide name>/reactions/reaction_<mt>/product_<j>/**
Reaction product data is described in :ref:`product`.
**/<nuclide name>/urr**
**/<nuclide name>/urr/<TTT>K/**
<TTT>K is the temperature in Kelvin, rounded to the nearest integer, of the
temperature-dependent data set. For example, the data set corresponding to
300 Kelvin would be located at `300K`.
:Attributes: - **interpolation** (*int*) -- interpolation scheme
- **inelastic** (*int*) -- flag indicating inelastic scattering
@ -92,32 +116,48 @@ Thermal Neutron Scattering Data
**/<thermal name>/**
:Attributes: - **atomic_weight_ratio** (*double*) -- Mass in units of neutron masses
- **temperature** (*double*) -- Temperature in MeV
- **zaids** (*int[]*) -- ZAID identifiers for which the thermal
- **nuclides** (*char[][]*) -- Names of nuclides for which the thermal
scattering data applies to
**/<thermal name>/elastic/**
:Datasets: - **xs** (:ref:`tabulated <1d_tabulated>`) -- Thermal inelastic
scattering cross section
- **mu_out** (*double[][]*) -- Distribution of outgoing energies
and angles for coherent elastic scattering
**/<thermal name>/inelastic/**
:Attributes:
- **secondary_mode** (*char[]*) -- Indicates how the inelastic
outgoing angle-energy distributions are represented ('equal',
'skewed', or 'continuous').
**/<thermal name>/kTs/**
<TTT>K is the temperature in Kelvin, rounded to the nearest integer, of the
temperature-dependent data set. For example, the data set corresponding to
300 Kelvin would be located at `300K`.
:Datasets:
- **<TTT>K** (*double*) -- kT values (in MeV) for each Temperature
TTT (in Kelvin)
**/<thermal name>/elastic/<TTT>K/**
<TTT>K is the temperature in Kelvin, rounded to the nearest integer, of the
temperature-dependent data set. For example, the data set corresponding to
300 Kelvin would be located at `300K`.
:Datasets: - **xs** (:ref:`tabulated <1d_tabulated>`) -- Thermal inelastic
scattering cross section
scattering cross section for temperature TTT (in Kelvin)
- **mu_out** (*double[][]*) -- Distribution of outgoing energies
and angles for coherent elastic scattering for temperature TTT
(in Kelvin)
**/<thermal name>/inelastic/<TTT>K/**
<TTT>K is the temperature in Kelvin, rounded to the nearest integer, of the
temperature-dependent data set. For example, the data set corresponding to
300 Kelvin would be located at `300K`.
:Datasets: - **xs** (:ref:`tabulated <1d_tabulated>`) -- Thermal inelastic
scattering cross section for temperature TTT (in Kelvin)
- **energy_out** (*double[][]*) -- Distribution of outgoing
energies for each incoming energy. Only present if secondary mode
is not continuous.
energies for each incoming energy for temperature TTT (in Kelvin).
Only present if secondary mode is not continuous.
- **mu_out** (*double[][][]*) -- Distribution of scattering cosines
for each pair of incoming and outgoing energies. Only present if
secondary mode is not continuous.
for each pair of incoming and outgoing energies. for temperature
TTT (in Kelvin). Only present if secondary mode is not continuous.
If the secondary mode is continuous, the outgoing energy-angle distribution is
given as a :ref:`correlated angle-energy distribution

37
docs/source/methods/cross_sections.rst
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@ -53,12 +53,12 @@ speed up the calculation.
Logarithmic Mapping
+++++++++++++++++++
To speed up energy grid searches, OpenMC uses logarithmic mapping technique
[Brown]_ to limit the range of energies that must be searched for each
nuclide. The entire energy range is divided up into equal-lethargy segments, and
the bounding energies of each segment are mapped to bounding indices on each of
the nuclide energy grids. By default, OpenMC uses 8000 equal-lethargy segments
as recommended by Brown.
To speed up energy grid searches, OpenMC uses a `logarithmic mapping technique`_
to limit the range of energies that must be searched for each nuclide. The
entire energy range is divided up into equal-lethargy segments, and the bounding
energies of each segment are mapped to bounding indices on each of the nuclide
energy grids. By default, OpenMC uses 8000 equal-lethargy segments as
recommended by Brown.
Other Methods
+++++++++++++
@ -74,9 +74,9 @@ 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.
The multipole method was introduced by [Hwang]_ and the faster windowed
multipole method by [Josey]_. In the multipole format, cross section resonances
are represented by poles, :math:`p_j`, and residues, :math:`r_j`, in the complex
The multipole method was introduced by Hwang_ and the faster windowed multipole
method by Josey_. In the multipole format, cross section resonances are
represented by poles, :math:`p_j`, and residues, :math:`r_j`, in the complex
plane. The 0K cross sections in the resolved resonance region can be computed
by summing up a contribution from each pole:
@ -232,21 +232,10 @@ sections. This allows flexibility for the model to use highly anisotropic
scattering information in the water while the fuel can be simulated with linear
or even isotropic scattering.
.. only:: html
.. rubric:: References
.. [Brown] Forrest B. Brown, "New Hash-based Energy Lookup Algorithm for Monte
Carlo codes," LA-UR-14-24530, Los Alamos National Laboratory (2014).
.. [Hwang] R. N. Hwang, "A Rigorous Pole Representation of Multilevel Cross
Sections and Its Practical Application," *Nucl. Sci. Eng.*, **96**,
192-209 (1987).
.. [Josey] Colin Josey, Pablo Ducru, Benoit Forget, and Kord Smith, "Windowed
Multipole for Cross Section Doppler Broadening," *J. Comp. Phys*,
**307**, 715-727 (2016). http://dx.doi.org/10.1016/j.jcp.2015.08.013
.. _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
.. _MCNP: http://mcnp.lanl.gov
.. _Serpent: http://montecarlo.vtt.fi
.. _NJOY: http://t2.lanl.gov/codes.shtml

101
docs/source/pythonapi/examples/mgxs-part-i.ipynb
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@ -214,7 +214,6 @@
"source": [
"# Instantiate a Materials collection and export to XML\n",
"materials_file = openmc.Materials([inf_medium])\n",
"materials_file.default_xs = '71c'\n",
"materials_file.export_to_xml()"
]
},
@ -499,23 +498,37 @@
"output_type": "stream",
"text": [
"\n",
" .d88888b. 888b d888 .d8888b.\n",
" d88P\" \"Y88b 8888b d8888 d88P Y88b\n",
" 888 888 88888b.d88888 888 888\n",
" 888 888 88888b. .d88b. 88888b. 888Y88888P888 888 \n",
" 888 888 888 \"88b d8P Y8b 888 \"88b 888 Y888P 888 888 \n",
" 888 888 888 888 88888888 888 888 888 Y8P 888 888 888\n",
" Y88b. .d88P 888 d88P Y8b. 888 888 888 \" 888 Y88b d88P\n",
" \"Y88888P\" 88888P\" \"Y8888 888 888 888 888 \"Y8888P\"\n",
"__________________888______________________________________________________\n",
" 888\n",
" 888\n",
" %%%%%%%%%%%%%%%\n",
" %%%%%%%%%%%%%%%%%%%%%%%%\n",
" %%%%%%%%%%%%%%%%%%%%%%%%%%%%%%\n",
" %%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%\n",
" %%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%\n",
" %%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%\n",
" %%%%%%%%%%%%%%%%%%%%%%%%\n",
" %%%%%%%%%%%%%%%%%%%%%%%%\n",
" ############### %%%%%%%%%%%%%%%%%%%%%%%%\n",
" ################## %%%%%%%%%%%%%%%%%%%%%%%\n",
" ################### %%%%%%%%%%%%%%%%%%%%%%%\n",
" #################### %%%%%%%%%%%%%%%%%%%%%%\n",
" ##################### %%%%%%%%%%%%%%%%%%%%%\n",
" ###################### %%%%%%%%%%%%%%%%%%%%\n",
" ####################### %%%%%%%%%%%%%%%%%%\n",
" ####################### %%%%%%%%%%%%%%%%%\n",
" ###################### %%%%%%%%%%%%%%%%%\n",
" #################### %%%%%%%%%%%%%%%%%\n",
" ################# %%%%%%%%%%%%%%%%%\n",
" ############### %%%%%%%%%%%%%%%%\n",
" ############ %%%%%%%%%%%%%%%\n",
" ######## %%%%%%%%%%%%%%\n",
" %%%%%%%%%%%\n",
"\n",
" Copyright: 2011-2016 Massachusetts Institute of Technology\n",
" License: http://openmc.readthedocs.io/en/latest/license.html\n",
" Version: 0.7.1\n",
" Git SHA1: 3d68c07625e33cd64188df03ee03e9c31b3d4b74\n",
" Date/Time: 2016-07-22 21:03:18\n",
" | The OpenMC Monte Carlo Code\n",
" Copyright | 2011-2016 Massachusetts Institute of Technology\n",
" License | http://openmc.readthedocs.io/en/latest/license.html\n",
" Version | 0.8.0\n",
" Git SHA1 | fbebf7bf709fe2fe1813af95bff9b29c0d59312c\n",
" Date/Time | 2016-08-31 10:40:13\n",
" OpenMP Threads | 4\n",
"\n",
" ===========================================================================\n",
" ========================> INITIALIZATION <=========================\n",
@ -525,12 +538,12 @@
" Reading geometry XML file...\n",
" Reading cross sections XML file...\n",
" Reading materials XML file...\n",
" Reading H1.71c from /home/romano/openmc/data/nndc_hdf5/H1_71c.h5\n",
" Reading O16.71c from /home/romano/openmc/data/nndc_hdf5/O16_71c.h5\n",
" Reading U235.71c from /home/romano/openmc/data/nndc_hdf5/U235_71c.h5\n",
" Reading U238.71c from /home/romano/openmc/data/nndc_hdf5/U238_71c.h5\n",
" Reading Zr90.71c from /home/romano/openmc/data/nndc_hdf5/Zr90_71c.h5\n",
" Maximum neutron transport energy: 20.0000 MeV for H1.71c\n",
" Reading H1 from /home/romano/openmc/data/nndc_hdf5/H1.h5\n",
" Reading O16 from /home/romano/openmc/data/nndc_hdf5/O16.h5\n",
" Reading U235 from /home/romano/openmc/data/nndc_hdf5/U235.h5\n",
" Reading U238 from /home/romano/openmc/data/nndc_hdf5/U238.h5\n",
" Reading Zr90 from /home/romano/openmc/data/nndc_hdf5/Zr90.h5\n",
" Maximum neutron transport energy: 20.0000 MeV for H1\n",
" Reading tallies XML file...\n",
" Building neighboring cells lists for each surface...\n",
" Initializing source particles...\n",
@ -600,20 +613,20 @@
"\n",
" =======================> TIMING STATISTICS <=======================\n",
"\n",
" Total time for initialization = 3.2300E-01 seconds\n",
" Reading cross sections = 1.6900E-01 seconds\n",
" Total time in simulation = 1.9882E+01 seconds\n",
" Time in transport only = 1.9869E+01 seconds\n",
" Time in inactive batches = 2.6590E+00 seconds\n",
" Time in active batches = 1.7223E+01 seconds\n",
" Total time for initialization = 3.9900E-01 seconds\n",
" Reading cross sections = 2.6500E-01 seconds\n",
" Total time in simulation = 1.1488E+01 seconds\n",
" Time in transport only = 1.1152E+01 seconds\n",
" Time in inactive batches = 1.2180E+00 seconds\n",
" Time in active batches = 1.0270E+01 seconds\n",
" Time synchronizing fission bank = 4.0000E-03 seconds\n",
" Sampling source sites = 4.0000E-03 seconds\n",
" SEND/RECV source sites = 0.0000E+00 seconds\n",
" Sampling source sites = 3.0000E-03 seconds\n",
" SEND/RECV source sites = 1.0000E-03 seconds\n",
" Time accumulating tallies = 0.0000E+00 seconds\n",
" Total time for finalization = 0.0000E+00 seconds\n",
" Total time elapsed = 2.0217E+01 seconds\n",
" Calculation Rate (inactive) = 9402.03 neutrons/second\n",
" Calculation Rate (active) = 5806.19 neutrons/second\n",
" Total time for finalization = 1.0000E-03 seconds\n",
" Total time elapsed = 1.1901E+01 seconds\n",
" Calculation Rate (inactive) = 20525.5 neutrons/second\n",
" Calculation Rate (active) = 9737.10 neutrons/second\n",
"\n",
" ============================> RESULTS <============================\n",
"\n",
@ -894,7 +907,7 @@
" <td>6.250000e-07</td>\n",
" <td>total</td>\n",
" <td>(((total / flux) - (absorption / flux)) - (sca...</td>\n",
" <td>-3.774758e-15</td>\n",
" <td>-2.886580e-15</td>\n",
" <td>0.011292</td>\n",
" </tr>\n",
" <tr>\n",
@ -904,7 +917,7 @@
" <td>2.000000e+01</td>\n",
" <td>total</td>\n",
" <td>(((total / flux) - (absorption / flux)) - (sca...</td>\n",
" <td>1.443290e-15</td>\n",
" <td>-5.551115e-16</td>\n",
" <td>0.002570</td>\n",
" </tr>\n",
" </tbody>\n",
@ -917,8 +930,8 @@
"1 1 6.25e-07 2.00e+01 total \n",
"\n",
" score mean std. dev. \n",
"0 (((total / flux) - (absorption / flux)) - (sca... -3.77e-15 1.13e-02 \n",
"1 (((total / flux) - (absorption / flux)) - (sca... 1.44e-15 2.57e-03 "
"0 (((total / flux) - (absorption / flux)) - (sca... -2.89e-15 1.13e-02 \n",
"1 (((total / flux) - (absorption / flux)) - (sca... -5.55e-16 2.57e-03 "
]
},
"execution_count": 22,
@ -1167,21 +1180,21 @@
],
"metadata": {
"kernelspec": {
"display_name": "Python 2",
"display_name": "Python 3",
"language": "python",
"name": "python2"
"name": "python3"
},
"language_info": {
"codemirror_mode": {
"name": "ipython",
"version": 2
"version": 3
},
"file_extension": ".py",
"mimetype": "text/x-python",
"name": "python",
"nbconvert_exporter": "python",
"pygments_lexer": "ipython2",
"version": "2.7.11"
"pygments_lexer": "ipython3",
"version": "3.5.2"
}
},
"nbformat": 4,

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docs/source/pythonapi/examples/tally-arithmetic.ipynb
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@ -105,7 +105,6 @@
"source": [
"# Instantiate a Materials collection\n",
"materials_file = openmc.Materials((fuel, water, zircaloy))\n",
"materials_file.default_xs = '71c'\n",
"\n",
"# Export to \"materials.xml\"\n",
"materials_file.export_to_xml()"
@ -339,7 +338,7 @@
"outputs": [
{
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"image/png": "iVBORw0KGgoAAAANSUhEUgAAAPoAAAD6AgMAAAD1grKuAAAABGdBTUEAALGPC/xhBQAAACBjSFJN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\nGaOiDwAAAABJRU5ErkJggg==\n",
"text/plain": [
"<IPython.core.display.Image object>"
]
@ -551,25 +550,39 @@
"name": "stdout",
"output_type": "stream",
"text": [
"rm: cannot remove 'statepoint.*': No such file or directory\n",
"\n",
" .d88888b. 888b d888 .d8888b.\n",
" d88P\" \"Y88b 8888b d8888 d88P Y88b\n",
" 888 888 88888b.d88888 888 888\n",
" 888 888 88888b. .d88b. 88888b. 888Y88888P888 888 \n",
" 888 888 888 \"88b d8P Y8b 888 \"88b 888 Y888P 888 888 \n",
" 888 888 888 888 88888888 888 888 888 Y8P 888 888 888\n",
" Y88b. .d88P 888 d88P Y8b. 888 888 888 \" 888 Y88b d88P\n",
" \"Y88888P\" 88888P\" \"Y8888 888 888 888 888 \"Y8888P\"\n",
"__________________888______________________________________________________\n",
" 888\n",
" 888\n",
" %%%%%%%%%%%%%%%\n",
" %%%%%%%%%%%%%%%%%%%%%%%%\n",
" %%%%%%%%%%%%%%%%%%%%%%%%%%%%%%\n",
" %%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%\n",
" %%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%\n",
" %%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%\n",
" %%%%%%%%%%%%%%%%%%%%%%%%\n",
" %%%%%%%%%%%%%%%%%%%%%%%%\n",
" ############### %%%%%%%%%%%%%%%%%%%%%%%%\n",
" ################## %%%%%%%%%%%%%%%%%%%%%%%\n",
" ################### %%%%%%%%%%%%%%%%%%%%%%%\n",
" #################### %%%%%%%%%%%%%%%%%%%%%%\n",
" ##################### %%%%%%%%%%%%%%%%%%%%%\n",
" ###################### %%%%%%%%%%%%%%%%%%%%\n",
" ####################### %%%%%%%%%%%%%%%%%%\n",
" ####################### %%%%%%%%%%%%%%%%%\n",
" ###################### %%%%%%%%%%%%%%%%%\n",
" #################### %%%%%%%%%%%%%%%%%\n",
" ################# %%%%%%%%%%%%%%%%%\n",
" ############### %%%%%%%%%%%%%%%%\n",
" ############ %%%%%%%%%%%%%%%\n",
" ######## %%%%%%%%%%%%%%\n",
" %%%%%%%%%%%\n",
"\n",
" Copyright: 2011-2016 Massachusetts Institute of Technology\n",
" License: http://openmc.readthedocs.io/en/latest/license.html\n",
" Version: 0.8.0\n",
" Git SHA1: 26bdadd79aac3712450d8c0612ac3edcb68e720f\n",
" Date/Time: 2016-08-29 12:20:02\n",
" MPI Processes: 1\n",
" | The OpenMC Monte Carlo Code\n",
" Copyright | 2011-2016 Massachusetts Institute of Technology\n",
" License | http://openmc.readthedocs.io/en/latest/license.html\n",
" Version | 0.8.0\n",
" Git SHA1 | 623b705a399f16c8e5063732bc6e6a357611542d\n",
" Date/Time | 2016-09-03 04:38:41\n",
" OpenMP Threads | 4\n",
"\n",
" ===========================================================================\n",
" ========================> INITIALIZATION <=========================\n",
@ -579,13 +592,13 @@
" Reading geometry XML file...\n",
" Reading cross sections XML file...\n",
" Reading materials XML file...\n",
" Reading U235.71c from /Users/sam/git/openmc-sam/data/nndc_hdf5/U235_71c.h5\n",
" Reading U238.71c from /Users/sam/git/openmc-sam/data/nndc_hdf5/U238_71c.h5\n",
" Reading O16.71c from /Users/sam/git/openmc-sam/data/nndc_hdf5/O16_71c.h5\n",
" Reading H1.71c from /Users/sam/git/openmc-sam/data/nndc_hdf5/H1_71c.h5\n",
" Reading B10.71c from /Users/sam/git/openmc-sam/data/nndc_hdf5/B10_71c.h5\n",
" Reading Zr90.71c from /Users/sam/git/openmc-sam/data/nndc_hdf5/Zr90_71c.h5\n",
" Maximum neutron transport energy: 20.0000 MeV for U235.71c\n",
" Reading U235 from /opt/xsdata/nndc_new/U235.h5\n",
" Reading U238 from /opt/xsdata/nndc_new/U238.h5\n",
" Reading O16 from /opt/xsdata/nndc_new/O16.h5\n",
" Reading H1 from /opt/xsdata/nndc_new/H1.h5\n",
" Reading B10 from /opt/xsdata/nndc_new/B10.h5\n",
" Reading Zr90 from /opt/xsdata/nndc_new/Zr90.h5\n",
" Maximum neutron transport energy: 20.0000 MeV for U235\n",
" Reading tallies XML file...\n",
" Building neighboring cells lists for each surface...\n",
" Initializing source particles...\n",
@ -625,20 +638,20 @@
"\n",
" =======================> TIMING STATISTICS <=======================\n",
"\n",
" Total time for initialization = 4.6800E-01 seconds\n",
" Reading cross sections = 2.8200E-01 seconds\n",
" Total time in simulation = 1.8453E+01 seconds\n",
" Time in transport only = 1.8432E+01 seconds\n",
" Time in inactive batches = 2.5060E+00 seconds\n",
" Time in active batches = 1.5947E+01 seconds\n",
" Time synchronizing fission bank = 2.0000E-03 seconds\n",
" Sampling source sites = 0.0000E+00 seconds\n",
" SEND/RECV source sites = 1.0000E-03 seconds\n",
" Time accumulating tallies = 1.0000E-03 seconds\n",
" Total time for finalization = 3.0000E-03 seconds\n",
" Total time elapsed = 1.8947E+01 seconds\n",
" Calculation Rate (inactive) = 4988.03 neutrons/second\n",
" Calculation Rate (active) = 2351.54 neutrons/second\n",
" Total time for initialization = 3.8900E-01 seconds\n",
" Reading cross sections = 2.7000E-01 seconds\n",
" Total time in simulation = 4.6960E+00 seconds\n",
" Time in transport only = 4.6760E+00 seconds\n",
" Time in inactive batches = 6.6400E-01 seconds\n",
" Time in active batches = 4.0320E+00 seconds\n",
" Time synchronizing fission bank = 1.0000E-03 seconds\n",
" Sampling source sites = 1.0000E-03 seconds\n",
" SEND/RECV source sites = 0.0000E+00 seconds\n",
" Time accumulating tallies = 0.0000E+00 seconds\n",
" Total time for finalization = 1.0000E-03 seconds\n",
" Total time elapsed = 5.0960E+00 seconds\n",
" Calculation Rate (inactive) = 18825.3 neutrons/second\n",
" Calculation Rate (active) = 9300.60 neutrons/second\n",
"\n",
" ============================> RESULTS <============================\n",
"\n",
@ -1728,21 +1741,21 @@
],
"metadata": {
"kernelspec": {
"display_name": "Python 2",
"display_name": "Python 3",
"language": "python",
"name": "python2"
"name": "python3"
},
"language_info": {
"codemirror_mode": {
"name": "ipython",
"version": 2
"version": 3
},
"file_extension": ".py",
"mimetype": "text/x-python",
"name": "python",
"nbconvert_exporter": "python",
"pygments_lexer": "ipython2",
"version": "2.7.12"
"pygments_lexer": "ipython3",
"version": "3.5.2"
}
},
"nbformat": 4,

120
docs/source/usersguide/input.rst
View file

@ -281,6 +281,8 @@ based on the recommended value in LA-UR-14-24530_.
.. note:: This element is not used in the multi-group :ref:`energy_mode`.
.. _multipole_library:
``<multipole_library>`` Element
-------------------------------
@ -290,8 +292,8 @@ OpenMC can use it for on-the-fly Doppler-broadening of resolved resonance range
cross sections. If this element is absent from the settings.xml file, the
:envvar:`OPENMC_MULTIPOLE_LIBRARY` environment variable will be used.
.. note:: The <use_windowed_multipole> element must also be set to "true"
for windowed multipole functionality.
.. note:: The :ref:`temperature_method` must also be set to "multipole" for
windowed multipole functionality.
``<max_order>`` Element
---------------------------
@ -395,19 +397,16 @@ attributes or sub-elements:
:scatterer:
An element with attributes/sub-elements called ``nuclide``, ``method``,
``xs_label``, ``xs_label_0K``, ``E_min``, and ``E_max``. The ``nuclide``
attribute is the name, as given by the ``name`` attribute within the
``nuclide`` sub-element of the ``material`` element in ``materials.xml``,
of the nuclide to which a resonance scattering treatment is to be applied.
``E_min``, and ``E_max``. The ``nuclide`` attribute is the name, as given
by the ``name`` attribute within the ``nuclide`` sub-element of the
``material`` element in ``materials.xml``, of the nuclide to which a
resonance scattering treatment is to be applied.
The ``method`` attribute gives the type of resonance scattering treatment
that is to be applied to the ``nuclide``. Acceptable inputs - none of
which are case-sensitive - for the ``method`` attribute are ``ARES``,
``CXS``, ``WCM``, and ``DBRC``. Descriptions of each of these methods
are documented here_. The ``xs_label`` attribute gives the label for the
cross section data of the ``nuclide`` at a given temperature. The
``xs_label_0K`` gives the label for the 0 K cross section data for the
``nuclide``. The ``E_min`` attribute gives the minimum energy above
which the ``method`` is applied. The ``E_max`` attribute gives the
are documented here_. The ``E_min`` attribute gives the minimum energy
above which the ``method`` is applied. The ``E_max`` attribute gives the
maximum energy below which the ``method`` is applied. One example would
be as follows:
@ -419,16 +418,12 @@ attributes or sub-elements:
<scatterer>
<nuclide>U-238</nuclide>
<method>ARES</method>
<xs_label>92238.72c</xs_label>
<xs_label_0K>92238.00c</xs_label_0K>
<E_min>5.0e-6</E_min>
<E_max>40.0e-6</E_max>
</scatterer>
<scatterer>
<nuclide>Pu-239</nuclide>
<method>dbrc</method>
<xs_label>94239.72c</xs_label>
<xs_label_0K>94239.00c</xs_label_0K>
<E_min>0.01e-6</E_min>
<E_max>210.0e-6</E_max>
</scatterer>
@ -714,6 +709,45 @@ survival biasing, otherwise known as implicit capture or absorption.
*Default*: false
.. _temperature_default:
``<temperature_default>`` Element
---------------------------------
The ``<temperature_default>`` element specifies a default temperature in Kelvin
that is to be applied to cells in the absence of an explicit cell temperature or
a material default temperature.
*Default*: 293.6 K
.. _temperature_method:
``<temperature_method>`` Element
--------------------------------
The ``<temperature_method>`` element has an accepted value of "nearest" or
"interpolation". A value of "nearest" indicates that for each cell, the nearest
temperature at which cross sections are given is to be applied, within a given
tolerance (see :ref:`temperature_tolerance`). A value of "multipole" indicates
that the windowed multipole method should be used to evaluate
temperature-dependent cross sections in the resolved resonance range (a
:ref:`windowed multipole library <multipole_library>` must also be available).
*Default*: "nearest"
.. _temperature_tolerance:
``<temperature_tolerance>`` Element
-----------------------------------
The ``<temperature_tolerance>`` element specifies a tolerance in Kelvin that is
to be applied when the "nearest" temperature method is used. For example, if a
cell temperature is 340 K and the tolerance is 15 K, then the closest
temperature in the range of 325 K to 355 K will be used to evaluate cross
sections.
*Default*: 10 K
``<threads>`` Element
---------------------
@ -1090,7 +1124,9 @@ Each ``<cell>`` element can have the following attributes or sub-elements:
specified for the "distributed temperature" feature. This will give each
unique instance of the cell its own temperature.
*Default*: The temperature of the coldest nuclide in the cell's material(s)
*Default*: If a material default temperature is supplied, it is used. In the
absence of a material default temperature, the :ref:`global default
temperature <temperature_default>` is used.
:rotation:
If the cell is filled with a universe, this element specifies the angles in
@ -1295,6 +1331,14 @@ Each ``material`` element can have the following attributes or sub-elements:
*Default*: ""
:temperature:
An element with no attributes which is used to set the default temperature
of the material in Kelvin.
*Default*: If a material default temperature is not given and a cell
temperature is not specified, the :ref:`global default temperature
<temperature_default>` is used.
:density:
An element with attributes/sub-elements called ``value`` and ``units``. The
``value`` attribute is the numeric value of the density while the ``units``
@ -1315,17 +1359,16 @@ Each ``material`` element can have the following attributes or sub-elements:
``nuclide``, ``element``, or ``sab`` quantity.
:nuclide:
An element with attributes/sub-elements called ``name``, ``xs``, and ``ao``
An element with attributes/sub-elements called ``name``, and ``ao``
or ``wo``. The ``name`` attribute is the name of the cross-section for a
desired nuclide while the ``xs`` attribute is the cross-section
identifier. Finally, the ``ao`` and ``wo`` attributes specify the atom or
desired nuclide. Finally, the ``ao`` and ``wo`` attributes specify the atom or
weight percent of that nuclide within the material, respectively. One
example would be as follows:
.. code-block:: xml
<nuclide name="H-1" xs="70c" ao="2.0" />
<nuclide name="O-16" xs="70c" ao="1.0" />
<nuclide name="H1" ao="2.0" />
<nuclide name="O16" ao="1.0" />
.. note:: If one nuclide is specified in atom percent, all others must also
be given in atom percent. The same applies for weight percentages.
@ -1349,11 +1392,10 @@ Each ``material`` element can have the following attributes or sub-elements:
Specifies that a natural element is present in the material. The natural
element is split up into individual isotopes based on `IUPAC Isotopic
Compositions of the Elements 2009`_. This element has
attributes/sub-elements called ``name``, ``xs``, and ``ao``. The ``name``
attribute is the atomic symbol of the element while the ``xs`` attribute is
the cross-section identifier. Finally, the ``ao`` attribute specifies the
atom percent of the element within the material, respectively. One example
would be as follows:
attributes/sub-elements called ``name``, and ``ao``. The ``name``
attribute is the atomic symbol of the element. Finally, the ``ao``
attribute specifies the atom percent of the element within the material,
respectively. One example would be as follows:
.. code-block:: xml
@ -1383,10 +1425,9 @@ Each ``material`` element can have the following attributes or sub-elements:
multi-group :ref:`energy_mode`.
:sab:
Associates an S(a,b) table with the material. This element has
attributes/sub-elements called ``name`` and ``xs``. The ``name`` attribute
is the name of the S(a,b) table that should be associated with the material,
and ``xs`` is the cross-section identifier for the table.
Associates an S(a,b) table with the material. This element has one
attribute/sub-element called ``name``. The ``name`` attribute
is the name of the S(a,b) table that should be associated with the material.
*Default*: None
@ -1397,14 +1438,13 @@ Each ``material`` element can have the following attributes or sub-elements:
recognizes that some multi-group libraries may be providing material
specific macroscopic cross sections instead of always providing nuclide
specific data like in the continuous-energy case. To that end, the
macroscopic element has attributes/sub-elements called ``name``, and ``xs``.
macroscopic element has one attribute/sub-element called ``name``.
The ``name`` attribute is the name of the cross-section for a
desired nuclide while the ``xs`` attribute is the cross-section
identifier. One example would be as follows:
desired nuclide. One example would be as follows:
.. code-block:: xml
<macroscopic name="UO2" xs="71c" />
<macroscopic name="UO2" />
.. note:: This element is only used in the multi-group :ref:`energy_mode`.
@ -1413,18 +1453,6 @@ Each ``material`` element can have the following attributes or sub-elements:
.. _IUPAC Isotopic Compositions of the Elements 2009:
http://pac.iupac.org/publications/pac/pdf/2011/pdf/8302x0397.pdf
``<default_xs>`` Element
------------------------
In some circumstances, the cross-section identifier may be the same for many or
all nuclides in a given problem. In this case, rather than specifying the
``xs=...`` attribute on every nuclide, a ``<default_xs>`` element can be used to
set the default cross-section identifier for any nuclide without an identifier
explicitly listed. This element has no attributes and accepts a 3-letter string
that indicates the default cross-section identifier, e.g. "70c".
*Default*: None
------------------------------------
Tallies Specification -- tallies.xml
------------------------------------