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Pulsed Height Tally in mixed neutron-gamma fields (#3937)

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Co-authored-by: Bor Kos <bor.kos@bakerhughes.com>
Co-authored-by: Paul Romano <paul.k.romano@gmail.com>
This commit is contained in:
Bor Kos 2026-05-30 05:25:38 +02:00 • committed by GitHub
parent ddabe1c8c5
commit 46d8896132
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10 changed files with 505 additions and 11 deletions
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11
src/physics.cpp
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@ -1227,6 +1227,17 @@ void sample_secondary_photons(Particle& p, int i_nuclide)
// Create the secondary photon
bool created_photon = p.create_secondary(wgt, u, E, ParticleType::photon());
// Pre-add photon energy to pht_storage so pht_secondary_particles()
// subtraction results in net zero
if (created_photon && !model::active_pulse_height_tallies.empty()) {
auto it = std::find(model::pulse_height_cells.begin(),
model::pulse_height_cells.end(), p.lowest_coord().cell());
if (it != model::pulse_height_cells.end()) {
int index = std::distance(model::pulse_height_cells.begin(), it);
p.pht_storage()[index] += E;
}
}
// Tag secondary particle with parent nuclide
if (created_photon && settings::use_decay_photons) {
p.local_secondary_bank().back().parent_nuclide =

40
tests/regression_tests/pulse_height/local_neutron/inputs_true.dat Normal file
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@ -0,0 +1,40 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1">
<density value="3.7" units="g/cm3"/>
<nuclide name="Na23" ao="1.0"/>
<nuclide name="I127" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" name="inner sphere" material="1" region="-1" universe="1"/>
<cell id="2" name="outer sphere" material="void" region="1 -2" universe="1"/>
<surface id="1" type="sphere" coeffs="0.0 0.0 0.0 1"/>
<surface id="2" type="sphere" boundary="vacuum" coeffs="0.0 0.0 0.0 2"/>
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>100</particles>
<batches>5</batches>
<source type="independent" strength="1.0" particle="neutron">
<energy type="discrete">
<parameters>1000000.0 1.0</parameters>
</energy>
</source>
<photon_transport>true</photon_transport>
<shared_secondary_bank>false</shared_secondary_bank>
</settings>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<filter id="2" type="energy">
<bins>0.0 10000.0 20000.0 30000.0 40000.0 50000.0 60000.0 70000.0 80000.0 90000.0 100000.0 110000.0 120000.0 130000.0 140000.0 150000.0 160000.0 170000.0 180000.0 190000.0 200000.0 210000.0 220000.0 230000.0 240000.0 250000.0 260000.0 270000.0 280000.0 290000.0 300000.0 310000.0 320000.0 330000.0 340000.0 350000.0 360000.0 370000.0 380000.0 390000.0 400000.0 410000.0 420000.0 430000.0 440000.0 450000.0 460000.0 470000.0 480000.0 490000.0 500000.0 510000.0 520000.0 530000.0 540000.0 550000.0 560000.0 570000.0 580000.0 590000.0 600000.0 610000.0 620000.0 630000.0 640000.0 650000.0 660000.0 670000.0 680000.0 690000.0 700000.0 710000.0 720000.0 730000.0 740000.0 750000.0 760000.0 770000.0 780000.0 790000.0 800000.0 810000.0 820000.0 830000.0 840000.0 850000.0 860000.0 870000.0 880000.0 890000.0 900000.0 910000.0 920000.0 930000.0 940000.0 950000.0 960000.0 970000.0 980000.0 990000.0 1000000.0</bins>
</filter>
<tally id="1" name="pht tally">
<filters>1 2</filters>
<scores>pulse-height</scores>
</tally>
</tallies>
</model>

201
tests/regression_tests/pulse_height/local_neutron/results_true.dat Normal file
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@ -0,0 +1,201 @@
tally 1:
4.890000E+00
4.784900E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
1.000000E-02
1.000000E-04
6.000000E-02
1.800000E-03
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
1.000000E-02
1.000000E-04
0.000000E+00
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1.000000E-02
1.000000E-04
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2
tests/regression_tests/pulse_height/local/inputs_true.dat → tests/regression_tests/pulse_height/local_photon/inputs_true.dat
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@ -2,7 +2,7 @@
<model>
<materials>
<material id="1">
<density value="3.7" units="g/cc"/>
<density value="3.7" units="g/cm3"/>
<nuclide name="Na23" ao="1.0"/>
<nuclide name="I127" ao="1.0"/>
</material>

0
tests/regression_tests/pulse_height/local/results_true.dat → tests/regression_tests/pulse_height/local_photon/results_true.dat
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40
tests/regression_tests/pulse_height/shared_neutron/inputs_true.dat Normal file
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@ -0,0 +1,40 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1">
<density value="3.7" units="g/cm3"/>
<nuclide name="Na23" ao="1.0"/>
<nuclide name="I127" ao="1.0"/>
</material>
</materials>
<geometry>
<cell id="1" name="inner sphere" material="1" region="-1" universe="1"/>
<cell id="2" name="outer sphere" material="void" region="1 -2" universe="1"/>
<surface id="1" type="sphere" coeffs="0.0 0.0 0.0 1"/>
<surface id="2" type="sphere" boundary="vacuum" coeffs="0.0 0.0 0.0 2"/>
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>100</particles>
<batches>5</batches>
<source type="independent" strength="1.0" particle="neutron">
<energy type="discrete">
<parameters>1000000.0 1.0</parameters>
</energy>
</source>
<photon_transport>true</photon_transport>
<shared_secondary_bank>true</shared_secondary_bank>
</settings>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<filter id="2" type="energy">
<bins>0.0 10000.0 20000.0 30000.0 40000.0 50000.0 60000.0 70000.0 80000.0 90000.0 100000.0 110000.0 120000.0 130000.0 140000.0 150000.0 160000.0 170000.0 180000.0 190000.0 200000.0 210000.0 220000.0 230000.0 240000.0 250000.0 260000.0 270000.0 280000.0 290000.0 300000.0 310000.0 320000.0 330000.0 340000.0 350000.0 360000.0 370000.0 380000.0 390000.0 400000.0 410000.0 420000.0 430000.0 440000.0 450000.0 460000.0 470000.0 480000.0 490000.0 500000.0 510000.0 520000.0 530000.0 540000.0 550000.0 560000.0 570000.0 580000.0 590000.0 600000.0 610000.0 620000.0 630000.0 640000.0 650000.0 660000.0 670000.0 680000.0 690000.0 700000.0 710000.0 720000.0 730000.0 740000.0 750000.0 760000.0 770000.0 780000.0 790000.0 800000.0 810000.0 820000.0 830000.0 840000.0 850000.0 860000.0 870000.0 880000.0 890000.0 900000.0 910000.0 920000.0 930000.0 940000.0 950000.0 960000.0 970000.0 980000.0 990000.0 1000000.0</bins>
</filter>
<tally id="1" name="pht tally">
<filters>1 2</filters>
<scores>pulse-height</scores>
</tally>
</tallies>
</model>

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tests/regression_tests/pulse_height/shared_neutron/results_true.dat Normal file
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@ -0,0 +1,201 @@
tally 1:
4.890000E+00
4.784900E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
1.000000E-02
1.000000E-04
6.000000E-02
1.800000E-03
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
1.000000E-02
1.000000E-04
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
1.000000E-02
1.000000E-04
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
0.000000E+00
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2
tests/regression_tests/pulse_height/shared/inputs_true.dat → tests/regression_tests/pulse_height/shared_photon/inputs_true.dat
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@ -2,7 +2,7 @@
<model>
<materials>
<material id="1">
<density value="3.7" units="g/cc"/>
<density value="3.7" units="g/cm3"/>
<nuclide name="Na23" ao="1.0"/>
<nuclide name="I127" ao="1.0"/>
</material>

0
tests/regression_tests/pulse_height/shared/results_true.dat → tests/regression_tests/pulse_height/shared_photon/results_true.dat
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19
tests/regression_tests/pulse_height/test.py
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@ -6,23 +6,24 @@ from openmc.utility_funcs import change_directory
from tests.testing_harness import PyAPITestHarness
@pytest.mark.parametrize("shared_secondary,subdir", [
(False, "local"),
(True, "shared"),
@pytest.mark.parametrize("shared_secondary,particle", [
(False, "photon"),
(False, "neutron"),
(True, "photon"),
(True, "neutron")
])
def test_pulse_height(shared_secondary, subdir):
def test_pulse_height(shared_secondary, particle):
subdir = f"shared_{particle}" if shared_secondary else f"local_{particle}"
with change_directory(subdir):
openmc.reset_auto_ids()
model = openmc.Model()
# Define materials
NaI = openmc.Material()
NaI.set_density('g/cc', 3.7)
NaI.set_density('g/cm3', 3.7)
NaI.add_element('Na', 1.0)
NaI.add_element('I', 1.0)
model.materials = openmc.Materials([NaI])
# Define geometry: two spheres in each other
s1 = openmc.Sphere(r=1)
s2 = openmc.Sphere(r=2, boundary_type='vacuum')
@ -38,14 +39,14 @@ def test_pulse_height(shared_secondary, subdir):
model.settings.shared_secondary_bank = shared_secondary
model.settings.source = openmc.IndependentSource(
energy=openmc.stats.delta_function(1e6),
particle='photon'
particle=particle
)
# Define tallies
tally = openmc.Tally(name="pht tally")
tally.scores = ['pulse-height']
cell_filter = openmc.CellFilter(inner_sphere)
energy_filter = openmc.EnergyFilter(np.linspace(0, 1_000_000, 101))
energy_filter = openmc.EnergyFilter(np.linspace(0, 1e6, 101))
tally.filters = [cell_filter, energy_filter]
model.tallies = [tally]