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added multi-temperature MG test.
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@jtramm
jtramm committed Jul 17, 2023
1 parent 8756b0f commit e2541fc
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Empty file added tests/regression_tests/mg_temperature_multi/__init__.py
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53 changes: 53 additions & 0 deletions tests/regression_tests/mg_temperature_multi/inputs_true.dat
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<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<cross_sections>mgxs.h5</cross_sections>
<material id="1" name="UO2 fuel">
<density units="macro" value="1.0"/>
<macroscopic name="UO2"/>
</material>
<material id="2" name="Water">
<density units="macro" value="1.0"/>
<macroscopic name="LWTR"/>
</material>
</materials>
<geometry>
<cell id="1" material="1" name="fuel inner" region="-1" temperature="600.0" universe="1"/>
<cell id="2" material="1" name="fuel outer" region="1 -2" temperature="294.0" universe="1"/>
<cell id="3" material="2" name="moderator" region="2 3 -4 5 -6" universe="1"/>
<surface coeffs="0.0 0.0 0.25" id="1" name="Fuel IR" type="z-cylinder"/>
<surface coeffs="0.0 0.0 0.54" id="2" name="Fuel OR" type="z-cylinder"/>
<surface boundary="reflective" coeffs="-0.63" id="3" name="minimum x" type="x-plane"/>
<surface boundary="reflective" coeffs="0.63" id="4" name="maximum x" type="x-plane"/>
<surface boundary="reflective" coeffs="-0.63" id="5" name="minimum y" type="y-plane"/>
<surface boundary="reflective" coeffs="0.63" id="6" name="maximum y" type="y-plane"/>
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source particle="neutron" strength="1.0" type="independent">
<space type="fission">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
</source>
<energy_mode>multi-group</energy_mode>
</settings>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<filter id="2" type="cell">
<bins>2</bins>
</filter>
<tally id="1" name="inner tally">
<filters>1</filters>
<scores>flux</scores>
</tally>
<tally id="2" name="outer tally">
<filters>2</filters>
<scores>flux</scores>
</tally>
</tallies>
</model>
8 changes: 8 additions & 0 deletions tests/regression_tests/mg_temperature_multi/results_true.dat
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k-combined:
1.337115E+00 7.221249E-03
tally 1:
2.549066E+01
1.299987E+02
tally 2:
9.276778E+01
1.721791E+03
163 changes: 163 additions & 0 deletions tests/regression_tests/mg_temperature_multi/test.py
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import os

import numpy as np

import openmc
import openmc.mgxs

from tests.testing_harness import PyAPITestHarness

def create_library():
# Instantiate the energy group data
egroups=[1e-5, 0.0635, 10.0, 1.0e2, 1.0e3, 0.5e6, 1.0e6, 20.0e6]
groups = openmc.mgxs.EnergyGroups(egroups)

# Instantiate the 7-group (C5G7) cross section data
uo2_xsdata = openmc.XSdata('UO2', groups, temperatures=[294.0, 600.0])
uo2_xsdata.order = 0
scatter_matrix = np.array(
[[[0.1275370, 0.0423780, 0.0000094, 0.0000000, 0.0000000, 0.0000000, 0.0000000],
[0.0000000, 0.3244560, 0.0016314, 0.0000000, 0.0000000, 0.0000000, 0.0000000],
[0.0000000, 0.0000000, 0.4509400, 0.0026792, 0.0000000, 0.0000000, 0.0000000],
[0.0000000, 0.0000000, 0.0000000, 0.4525650, 0.0055664, 0.0000000, 0.0000000],
[0.0000000, 0.0000000, 0.0000000, 0.0001253, 0.2714010, 0.0102550, 0.0000000],
[0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.0012968, 0.2658020, 0.0168090],
[0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.0085458, 0.2730800]]])
scatter_matrix = np.rollaxis(scatter_matrix, 0, 3)

# Original C5G7 data
uo2_xsdata.set_total([0.1779492, 0.3298048, 0.4803882, 0.5543674, 0.3118013, 0.3951678, 0.5644058], temperature=294.0)
uo2_xsdata.set_absorption([8.0248E-03, 3.7174E-03, 2.6769E-02, 9.6236E-02, 3.0020E-02, 1.1126E-01, 2.8278E-01], temperature=294.0)
uo2_xsdata.set_scatter_matrix(scatter_matrix, temperature=294.0)
uo2_xsdata.set_fission([7.21206E-03, 8.19301E-04, 6.45320E-03, 1.85648E-02, 1.78084E-02, 8.30348E-02, 2.16004E-01], temperature=294.0)
uo2_xsdata.set_nu_fission([2.005998E-02, 2.027303E-03, 1.570599E-02, 4.518301E-02, 4.334208E-02, 2.020901E-01, 5.257105E-01], temperature=294.0)
uo2_xsdata.set_chi([5.8791E-01, 4.1176E-01, 3.3906E-04, 1.1761E-07, 0.0000E+00, 0.0000E+00, 0.0000E+00], temperature=294.0)

# Altered C5G7 data (permuted Chi)
uo2_xsdata.set_total([0.1779492, 0.3298048, 0.4803882, 0.5543674, 0.3118013, 0.3951678, 0.5644058], temperature=600.0)
uo2_xsdata.set_absorption([8.0248E-03, 3.7174E-03, 2.6769E-02, 9.6236E-02, 3.0020E-02, 1.1126E-01, 2.8278E-01], temperature=600.0)
uo2_xsdata.set_scatter_matrix(scatter_matrix, temperature=600.0)
uo2_xsdata.set_fission([7.21206E-03, 8.19301E-04, 6.45320E-03, 1.85648E-02, 1.78084E-02, 8.30348E-02, 2.16004E-01], temperature=600.0)
uo2_xsdata.set_nu_fission([2.005998E-02, 2.027303E-03, 1.570599E-02, 4.518301E-02, 4.334208E-02, 2.020901E-01, 5.257105E-01], temperature=600.0)
uo2_xsdata.set_chi([4.1176E-01, 5.8791E-01, 3.3906E-04, 1.1761E-07, 0.0000E+00, 0.0000E+00, 0.0000E+00], temperature=600.0)


h2o_xsdata = openmc.XSdata('LWTR', groups)
h2o_xsdata.order = 0
h2o_xsdata.set_total([0.15920605, 0.412969593, 0.59030986, 0.58435,
0.718, 1.2544497, 2.650379])
h2o_xsdata.set_absorption([6.0105E-04, 1.5793E-05, 3.3716E-04,
1.9406E-03, 5.7416E-03, 1.5001E-02,
3.7239E-02])
scatter_matrix = np.array(
[[[0.0444777, 0.1134000, 0.0007235, 0.0000037, 0.0000001, 0.0000000, 0.0000000],
[0.0000000, 0.2823340, 0.1299400, 0.0006234, 0.0000480, 0.0000074, 0.0000010],
[0.0000000, 0.0000000, 0.3452560, 0.2245700, 0.0169990, 0.0026443, 0.0005034],
[0.0000000, 0.0000000, 0.0000000, 0.0910284, 0.4155100, 0.0637320, 0.0121390],
[0.0000000, 0.0000000, 0.0000000, 0.0000714, 0.1391380, 0.5118200, 0.0612290],
[0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.0022157, 0.6999130, 0.5373200],
[0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.1324400, 2.4807000]]])
scatter_matrix = np.rollaxis(scatter_matrix, 0, 3)
h2o_xsdata.set_scatter_matrix(scatter_matrix)

mg_cross_sections_file = openmc.MGXSLibrary(groups)
mg_cross_sections_file.add_xsdatas([uo2_xsdata, h2o_xsdata])
mg_cross_sections_file.export_to_hdf5()

class MGXSTestHarness(PyAPITestHarness):
def _cleanup(self):
super()._cleanup()
f = 'mgxs.h5'
if os.path.exists(f):
os.remove(f)

def test_mg_temperature_multi():
###############################################################################
# Create multigroup data
create_library()

###############################################################################
# Create materials for the problem

# Instantiate some Macroscopic Data
uo2_data = openmc.Macroscopic('UO2')
h2o_data = openmc.Macroscopic('LWTR')

# Instantiate some Materials and register the appropriate Macroscopic objects
uo2 = openmc.Material(name='UO2 fuel')
uo2.set_density('macro', 1.0)
uo2.add_macroscopic(uo2_data)

water = openmc.Material(name='Water')
water.set_density('macro', 1.0)
water.add_macroscopic(h2o_data)

# Instantiate a Materials collection and export to XML
materials = openmc.Materials([uo2, water])
materials.cross_sections = "mgxs.h5"

###############################################################################
# Define problem geometry

# Create a surface for the fuel outer radius
fuel_ir = openmc.ZCylinder(r=0.25, name='Fuel IR')
fuel_or = openmc.ZCylinder(r=0.54, name='Fuel OR')

# Create a region represented as the inside of a rectangular prism
pitch = 1.26
box = openmc.rectangular_prism(pitch, pitch, boundary_type='reflective')

# Instantiate Cells
fuel_inner = openmc.Cell(fill=uo2, region=-fuel_ir, name='fuel inner')
fuel_inner.temperature = 600.0
fuel_outer = openmc.Cell(fill=uo2, region=+fuel_ir & -fuel_or, name='fuel outer')
fuel_outer.temperature = 294.0
moderator = openmc.Cell(fill=water, region=+fuel_or & box, name='moderator')

# Create a geometry with the two cells and export to XML
geometry = openmc.Geometry([fuel_inner, fuel_outer, moderator])

###############################################################################
# Define problem settings

# Instantiate a Settings object, set all runtime parameters, and export to XML
settings = openmc.Settings()
settings.energy_mode = "multi-group"
settings.batches = 10
settings.inactive = 5
settings.particles = 1000

# Create an initial uniform spatial source distribution over fissionable zones
lower_left = (-pitch/2, -pitch/2, -1)
upper_right = (pitch/2, pitch/2, 1)
uniform_dist = openmc.stats.Box(lower_left, upper_right, only_fissionable=True)
settings.source = openmc.IndependentSource(space=uniform_dist)

###############################################################################
# Define tallies

# Instantiate the energy group data
egroups=[1e-5, 0.0635, 10.0, 1.0e2, 1.0e3, 0.5e6, 1.0e6, 20.0e6]

inner_filter = openmc.CellFilter(fuel_inner)
outer_filter = openmc.CellFilter(fuel_outer)
energy_filter = openmc.EnergyFilter(egroups)

inner_tally = openmc.Tally(name="inner tally")
inner_tally.filters = [energy_filter]
inner_tally.filters = [inner_filter]
inner_tally.scores = ['flux']

outer_tally = openmc.Tally(name="outer tally")
outer_tally.filters = [energy_filter]
outer_tally.filters = [outer_filter]
outer_tally.scores = ['flux']

# Instantiate a Tallies collection and export to XML
tallies = openmc.Tallies([inner_tally, outer_tally])

# Generate model and run test
model = openmc.model.Model(geometry=geometry, materials=materials, settings=settings,tallies=tallies)

harness = MGXSTestHarness('statepoint.10.h5', model=model)
harness.main()

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