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Enable fission heating tallies in the random ray solver (#3714)

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Kevin Sawatzky 2026-01-23 10:23:05 -06:00 • committed by GitHub
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commit 3e2f1f521a
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13 changed files with 315 additions and 6 deletions
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1
docs/source/usersguide/random_ray.rst
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@ -513,6 +513,7 @@ Supported scores:
- total
- fission
- nu-fission
- kappa-fission
- events
Supported Estimators:

1
include/openmc/random_ray/flat_source_domain.h
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@ -107,6 +107,7 @@ public:
vector<double> nu_sigma_f_;
vector<double> sigma_f_;
vector<double> chi_;
vector<double> kappa_fission_;
// 3D arrays stored in 1D representing values for all materials x energy
// groups x energy groups

6
openmc/model/model.py
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@ -1729,12 +1729,14 @@ class Model:
if correction == 'P0':
mgxs_lib.mgxs_types = [
'nu-transport', 'absorption', 'nu-fission', 'fission',
'consistent nu-scatter matrix', 'multiplicity matrix', 'chi'
'consistent nu-scatter matrix', 'multiplicity matrix', 'chi',
'kappa-fission'
]
elif correction is None:
mgxs_lib.mgxs_types = [
'total', 'absorption', 'nu-fission', 'fission',
'consistent nu-scatter matrix', 'multiplicity matrix', 'chi'
'consistent nu-scatter matrix', 'multiplicity matrix', 'chi',
'kappa-fission'
]
# Specify a "material" domain type for the cross section tally filters

14
src/random_ray/flat_source_domain.cpp
View file

@ -665,10 +665,15 @@ void FlatSourceDomain::random_ray_tally()
score = 1.0;
break;
case SCORE_KAPPA_FISSION:
score = flux * volume * kappa_fission_[material * negroups_ + g] *
density_mult;
break;
default:
fatal_error("Invalid score specified in tallies.xml. Only flux, "
"total, fission, nu-fission, and events are supported in "
"random ray mode.");
"total, fission, nu-fission, kappa-fission, and events "
"are supported in random ray mode.");
break;
}
// Apply score to the appropriate tally bin
@ -1165,6 +1170,10 @@ void FlatSourceDomain::flatten_xs()
}
chi_.push_back(chi);
double kappa_fission =
m.get_xs(MgxsType::KAPPA_FISSION, g_out, NULL, NULL, NULL, t, a);
kappa_fission_.push_back(kappa_fission);
for (int g_in = 0; g_in < negroups_; g_in++) {
double sigma_s =
m.get_xs(MgxsType::NU_SCATTER, g_in, &g_out, NULL, NULL, t, a);
@ -1180,6 +1189,7 @@ void FlatSourceDomain::flatten_xs()
nu_sigma_f_.push_back(0);
sigma_f_.push_back(0);
chi_.push_back(0);
kappa_fission_.push_back(0);
for (int g_in = 0; g_in < negroups_; g_in++) {
sigma_s_.push_back(0);
}

5
src/random_ray/random_ray_simulation.cpp
View file

@ -83,11 +83,12 @@ void validate_random_ray_inputs()
case SCORE_FISSION:
case SCORE_NU_FISSION:
case SCORE_EVENTS:
case SCORE_KAPPA_FISSION:
break;
default:
fatal_error(
"Invalid score specified. Only flux, total, fission, nu-fission, and "
"event scores are supported in random ray mode.");
"Invalid score specified. Only flux, total, fission, nu-fission, "
"kappa-fission, and event scores are supported in random ray mode.");
}
}

0
tests/regression_tests/random_ray_auto_convert_kappa_fission/__init__.py Normal file
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73
tests/regression_tests/random_ray_auto_convert_kappa_fission/infinite_medium/inputs_true.dat Normal file
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@ -0,0 +1,73 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<cross_sections>mgxs.h5</cross_sections>
<material id="1" name="UO2__2_4__" depletable="true">
<density value="1.0" units="macro"/>
<macroscopic name="UO2__2_4__"/>
</material>
<material id="2" name="Zircaloy">
<density value="1.0" units="macro"/>
<macroscopic name="Zircaloy"/>
</material>
<material id="3" name="Hot_borated_water">
<density value="1.0" units="macro"/>
<macroscopic name="Hot_borated_water"/>
</material>
</materials>
<geometry>
<cell id="1" name="Fuel" material="1" region="-1" universe="0"/>
<cell id="2" name="Cladding" material="2" region="1 -2" universe="0"/>
<cell id="3" name="Water" material="3" region="2 3 -4 5 -6" universe="0"/>
<surface id="1" name="Fuel OR" type="z-cylinder" coeffs="0 0 0.39218"/>
<surface id="2" name="Clad OR" type="z-cylinder" coeffs="0 0 0.4572"/>
<surface id="3" name="left" type="x-plane" boundary="reflective" coeffs="-0.63"/>
<surface id="4" name="right" type="x-plane" boundary="reflective" coeffs="0.63"/>
<surface id="5" name="bottom" type="y-plane" boundary="reflective" coeffs="-0.63"/>
<surface id="6" name="top" type="y-plane" boundary="reflective" coeffs="0.63"/>
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source type="independent" strength="1.0" particle="neutron">
<space type="box">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
<constraints>
<fissionable>true</fissionable>
</constraints>
</source>
<energy_mode>multi-group</energy_mode>
<random_ray>
<source type="independent" strength="1.0" particle="neutron">
<space type="box">
<parameters>-0.63 -0.63 -1.0 0.63 0.63 1.0</parameters>
</space>
</source>
<distance_inactive>30.0</distance_inactive>
<distance_active>150.0</distance_active>
<source_region_meshes>
<mesh id="1">
<domain id="0" type="universe"/>
</mesh>
</source_region_meshes>
<source_shape>linear</source_shape>
</random_ray>
<mesh id="1">
<dimension>2 2</dimension>
<lower_left>-0.63 -0.63</lower_left>
<upper_right>0.63 0.63</upper_right>
</mesh>
</settings>
<tallies>
<filter id="61" type="material">
<bins>1</bins>
</filter>
<tally id="193" name="KF Tally">
<filters>61</filters>
<scores>kappa-fission</scores>
</tally>
</tallies>
</model>

5
tests/regression_tests/random_ray_auto_convert_kappa_fission/infinite_medium/results_true.dat Normal file
View file

@ -0,0 +1,5 @@
k-combined:
7.479770E-01 1.624548E-02
tally 1:
2.965503E+08
1.762157E+16

73
tests/regression_tests/random_ray_auto_convert_kappa_fission/material_wise/inputs_true.dat Normal file
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@ -0,0 +1,73 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<cross_sections>mgxs.h5</cross_sections>
<material id="1" name="UO2__2_4__" depletable="true">
<density value="1.0" units="macro"/>
<macroscopic name="UO2__2_4__"/>
</material>
<material id="2" name="Zircaloy">
<density value="1.0" units="macro"/>
<macroscopic name="Zircaloy"/>
</material>
<material id="3" name="Hot_borated_water">
<density value="1.0" units="macro"/>
<macroscopic name="Hot_borated_water"/>
</material>
</materials>
<geometry>
<cell id="1" name="Fuel" material="1" region="-1" universe="0"/>
<cell id="2" name="Cladding" material="2" region="1 -2" universe="0"/>
<cell id="3" name="Water" material="3" region="2 3 -4 5 -6" universe="0"/>
<surface id="1" name="Fuel OR" type="z-cylinder" coeffs="0 0 0.39218"/>
<surface id="2" name="Clad OR" type="z-cylinder" coeffs="0 0 0.4572"/>
<surface id="3" name="left" type="x-plane" boundary="reflective" coeffs="-0.63"/>
<surface id="4" name="right" type="x-plane" boundary="reflective" coeffs="0.63"/>
<surface id="5" name="bottom" type="y-plane" boundary="reflective" coeffs="-0.63"/>
<surface id="6" name="top" type="y-plane" boundary="reflective" coeffs="0.63"/>
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source type="independent" strength="1.0" particle="neutron">
<space type="box">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
<constraints>
<fissionable>true</fissionable>
</constraints>
</source>
<energy_mode>multi-group</energy_mode>
<random_ray>
<source type="independent" strength="1.0" particle="neutron">
<space type="box">
<parameters>-0.63 -0.63 -1.0 0.63 0.63 1.0</parameters>
</space>
</source>
<distance_inactive>30.0</distance_inactive>
<distance_active>150.0</distance_active>
<source_region_meshes>
<mesh id="1">
<domain id="0" type="universe"/>
</mesh>
</source_region_meshes>
<source_shape>linear</source_shape>
</random_ray>
<mesh id="1">
<dimension>2 2</dimension>
<lower_left>-0.63 -0.63</lower_left>
<upper_right>0.63 0.63</upper_right>
</mesh>
</settings>
<tallies>
<filter id="97" type="material">
<bins>1</bins>
</filter>
<tally id="203" name="KF Tally">
<filters>97</filters>
<scores>kappa-fission</scores>
</tally>
</tallies>
</model>

5
tests/regression_tests/random_ray_auto_convert_kappa_fission/material_wise/results_true.dat Normal file
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@ -0,0 +1,5 @@
k-combined:
7.372542E-01 6.967831E-03
tally 1:
2.909255E+08
1.693395E+16

73
tests/regression_tests/random_ray_auto_convert_kappa_fission/stochastic_slab/inputs_true.dat Normal file
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@ -0,0 +1,73 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<cross_sections>mgxs.h5</cross_sections>
<material id="1" name="UO2__2_4__" depletable="true">
<density value="1.0" units="macro"/>
<macroscopic name="UO2__2_4__"/>
</material>
<material id="2" name="Zircaloy">
<density value="1.0" units="macro"/>
<macroscopic name="Zircaloy"/>
</material>
<material id="3" name="Hot_borated_water">
<density value="1.0" units="macro"/>
<macroscopic name="Hot_borated_water"/>
</material>
</materials>
<geometry>
<cell id="1" name="Fuel" material="1" region="-1" universe="0"/>
<cell id="2" name="Cladding" material="2" region="1 -2" universe="0"/>
<cell id="3" name="Water" material="3" region="2 3 -4 5 -6" universe="0"/>
<surface id="1" name="Fuel OR" type="z-cylinder" coeffs="0 0 0.39218"/>
<surface id="2" name="Clad OR" type="z-cylinder" coeffs="0 0 0.4572"/>
<surface id="3" name="left" type="x-plane" boundary="reflective" coeffs="-0.63"/>
<surface id="4" name="right" type="x-plane" boundary="reflective" coeffs="0.63"/>
<surface id="5" name="bottom" type="y-plane" boundary="reflective" coeffs="-0.63"/>
<surface id="6" name="top" type="y-plane" boundary="reflective" coeffs="0.63"/>
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source type="independent" strength="1.0" particle="neutron">
<space type="box">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
<constraints>
<fissionable>true</fissionable>
</constraints>
</source>
<energy_mode>multi-group</energy_mode>
<random_ray>
<source type="independent" strength="1.0" particle="neutron">
<space type="box">
<parameters>-0.63 -0.63 -1.0 0.63 0.63 1.0</parameters>
</space>
</source>
<distance_inactive>30.0</distance_inactive>
<distance_active>150.0</distance_active>
<source_region_meshes>
<mesh id="1">
<domain id="0" type="universe"/>
</mesh>
</source_region_meshes>
<source_shape>linear</source_shape>
</random_ray>
<mesh id="1">
<dimension>2 2</dimension>
<lower_left>-0.63 -0.63</lower_left>
<upper_right>0.63 0.63</upper_right>
</mesh>
</settings>
<tallies>
<filter id="97" type="material">
<bins>1</bins>
</filter>
<tally id="203" name="KF Tally">
<filters>97</filters>
<scores>kappa-fission</scores>
</tally>
</tallies>
</model>

5
tests/regression_tests/random_ray_auto_convert_kappa_fission/stochastic_slab/results_true.dat Normal file
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@ -0,0 +1,5 @@
k-combined:
6.413334E-01 2.083132E-02
tally 1:
2.541463E+08
1.297259E+16

60
tests/regression_tests/random_ray_auto_convert_kappa_fission/test.py Normal file
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@ -0,0 +1,60 @@
import os
import openmc
from openmc.examples import pwr_pin_cell
from openmc import RegularMesh
from openmc.utility_funcs import change_directory
import pytest
from tests.testing_harness import TolerantPyAPITestHarness
class MGXSTestHarness(TolerantPyAPITestHarness):
def _cleanup(self):
super()._cleanup()
f = 'mgxs.h5'
if os.path.exists(f):
os.remove(f)
@pytest.mark.parametrize("method", ["material_wise", "stochastic_slab", "infinite_medium"])
def test_random_ray_auto_convert(method):
with change_directory(method):
openmc.reset_auto_ids()
# Start with a normal continuous energy model
model = pwr_pin_cell()
# Convert to a multi-group model
model.convert_to_multigroup(
method=method, groups='CASMO-2', nparticles=100,
overwrite_mgxs_library=False, mgxs_path="mgxs.h5"
)
# Convert to a random ray model
model.convert_to_random_ray()
# Set the number of particles
model.settings.particles = 100
# Overlay a basic 2x2 mesh
n = 2
mesh = RegularMesh()
mesh.dimension = (n, n)
bbox = model.geometry.bounding_box
mesh.lower_left = (bbox.lower_left[0], bbox.lower_left[1])
mesh.upper_right = (bbox.upper_right[0], bbox.upper_right[1])
model.settings.random_ray['source_region_meshes'] = [
(mesh, [model.geometry.root_universe])]
# Set the source shape to linear
model.settings.random_ray['source_shape'] = 'linear'
# Set a material tally
t = openmc.Tally(name = 'KF Tally')
t.filters = [openmc.MaterialFilter(bins=1)]
t.scores = ['kappa-fission']
model.tallies.append(t)
harness = MGXSTestHarness('statepoint.10.h5', model)
harness.main()