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Merge pull request #661 from nelsonag/mgxs_test

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Added further tests of MGXS data
This commit is contained in:
Will Boyd 2016-05-29 14:25:09 -05:00
commit 1ce7952c23
23 changed files with 835 additions and 643 deletions
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2
openmc/mgxs/library.py
View file

@ -34,7 +34,7 @@ class Library(object):
Parameters
----------
openmc_geometry : openmc.Geometry
An geometry which has been initialized with a root universe
A geometry which has been initialized with a root universe
by_nuclide : bool
If true, computes cross sections for each nuclide in each domain
mgxs_types : Iterable of str

2
openmc/mgxs/mgxs.py
View file

@ -3680,7 +3680,7 @@ class MultiplicityMatrixXS(MatrixMGXS):
groups=None, by_nuclide=False, name=''):
super(MultiplicityMatrixXS, self).__init__(domain, domain_type, groups,
by_nuclide, name)
self._rxn_type = 'multiplicity'
self._rxn_type = 'multiplicity matrix'
@property
def scores(self):

23
src/mgxs_header.F90
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@ -1485,8 +1485,13 @@ module mgxs_header
nuc % scatter % energy(gin) % data(gout)
mult_num(gout, gin) = mult_num(gout, gin) + atom_density * &
nuscatt
mult_denom(gout, gin) = mult_denom(gout,gin) + atom_density * &
nuscatt / nuc % scatter % mult(gin) % data(gout)
if (nuc % scatter % mult(gin) % data(gout) > ZERO) then
mult_denom(gout, gin) = mult_denom(gout,gin) + atom_density * &
nuscatt / nuc % scatter % mult(gin) % data(gout)
else
! Avoid division by zero
mult_denom(gout, gin) = mult_denom(gout,gin) + atom_density
end if
end do
end do
@ -1722,10 +1727,16 @@ module mgxs_header
nuc % scatter(iazi, ipol) % obj % energy(gin) % data(gout)
mult_num(gout, gin, iazi, ipol) = mult_num(gout, gin, iazi, ipol) + &
atom_density * nuscatt
mult_denom(gout, gin, iazi, ipol) = &
mult_denom(gout, gin, iazi, ipol) + &
atom_density * nuscatt / &
nuc % scatter(iazi, ipol) % obj % mult(gin) % data(gout)
if (nuc % scatter(iazi, ipol) % obj % mult(gin) % data(gout) > ZERO) then
mult_denom(gout, gin, iazi, ipol) = &
mult_denom(gout, gin, iazi, ipol) + &
atom_density * nuscatt / &
nuc % scatter(iazi, ipol) % obj % mult(gin) % data(gout)
else
! Avoid division by zero
mult_denom(gout, gin, iazi, ipol) = &
mult_denom(gout,gin, iazi, ipol) + atom_density
end if
end do
end do
end do

141
tests/input_set.py
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@ -15,8 +15,10 @@ class InputSet(object):
self.settings.export_to_xml()
self.materials.export_to_xml()
self.geometry.export_to_xml()
if self.tallies is not None: self.tallies.export_to_xml()
if self.plots is not None: self.plots.export_to_xml()
if self.tallies is not None:
self.tallies.export_to_xml()
if self.plots is not None:
self.plots.export_to_xml()
def build_default_materials_and_geometry(self):
# Define materials.
@ -82,7 +84,7 @@ class InputSet(object):
hot_water.add_s_alpha_beta('HH2O', '71t')
rpv_steel = openmc.Material(name='Reactor pressure vessel steel',
material_id=5)
material_id=5)
rpv_steel.set_density('g/cm3', 7.9)
rpv_steel.add_nuclide("Fe-54", 0.05437098, 'wo')
rpv_steel.add_nuclide("Fe-56", 0.88500663, 'wo')
@ -113,7 +115,7 @@ class InputSet(object):
rpv_steel.add_nuclide("Cu-65", 0.0006304, 'wo')
lower_rad_ref = openmc.Material(name='Lower radial reflector',
material_id=6)
material_id=6)
lower_rad_ref.set_density('g/cm3', 4.32)
lower_rad_ref.add_nuclide("H-1", 0.0095661, 'wo')
lower_rad_ref.add_nuclide("O-16", 0.0759107, 'wo')
@ -189,7 +191,8 @@ class InputSet(object):
bot_plate.add_nuclide("Cr-54", 0.004612692337, 'wo')
bot_plate.add_s_alpha_beta('HH2O', '71t')
bot_nozzle = openmc.Material(name='Bottom nozzle region', material_id=9)
bot_nozzle = openmc.Material(name='Bottom nozzle region',
material_id=9)
bot_nozzle.set_density('g/cm3', 2.53)
bot_nozzle.add_nuclide("H-1", 0.0245014, 'wo')
bot_nozzle.add_nuclide("O-16", 0.1944274, 'wo')
@ -252,7 +255,8 @@ class InputSet(object):
top_fa.add_nuclide("Zr-96", 0.02511169542, 'wo')
top_fa.add_s_alpha_beta('HH2O', '71t')
bot_fa = openmc.Material(name='Bottom of fuel assemblies', material_id=12)
bot_fa = openmc.Material(name='Bottom of fuel assemblies',
material_id=12)
bot_fa.set_density('g/cm3', 1.762)
bot_fa.add_nuclide("H-1", 0.0292856, 'wo')
bot_fa.add_nuclide("O-16", 0.2323919, 'wo')
@ -570,6 +574,109 @@ class InputSet(object):
self.plots.add_plot(plot)
class PinCellInputSet(object):
def __init__(self):
self.settings = openmc.Settings()
self.materials = openmc.Materials()
self.geometry = openmc.Geometry()
self.tallies = None
self.plots = None
def export(self):
self.settings.export_to_xml()
self.materials.export_to_xml()
self.geometry.export_to_xml()
if self.tallies is not None:
self.tallies.export_to_xml()
if self.plots is not None:
self.plots.export_to_xml()
def build_default_materials_and_geometry(self):
# Define materials.
fuel = openmc.Material(name='Fuel')
fuel.set_density('g/cm3', 10.29769)
fuel.add_nuclide("U-234", 4.4843e-6)
fuel.add_nuclide("U-235", 5.5815e-4)
fuel.add_nuclide("U-238", 2.2408e-2)
fuel.add_nuclide("O-16", 4.5829e-2)
clad = openmc.Material(name='Cladding')
clad.set_density('g/cm3', 6.55)
clad.add_nuclide("Zr-90", 2.1827e-2)
clad.add_nuclide("Zr-91", 4.7600e-3)
clad.add_nuclide("Zr-92", 7.2758e-3)
clad.add_nuclide("Zr-94", 7.3734e-3)
clad.add_nuclide("Zr-96", 1.1879e-3)
hot_water = openmc.Material(name='Hot borated water')
hot_water.set_density('g/cm3', 0.740582)
hot_water.add_nuclide("H-1", 4.9457e-2)
hot_water.add_nuclide("O-16", 2.4672e-2)
hot_water.add_nuclide("B-10", 8.0042e-6)
hot_water.add_nuclide("B-11", 3.2218e-5)
hot_water.add_s_alpha_beta('HH2O', '71t')
# Define the materials file.
self.materials.default_xs = '71c'
self.materials += (fuel, clad, hot_water)
# Instantiate ZCylinder surfaces
fuel_or = openmc.ZCylinder(x0=0, y0=0, R=0.39218, name='Fuel OR')
clad_or = openmc.ZCylinder(x0=0, y0=0, R=0.45720, name='Clad OR')
left = openmc.XPlane(x0=-0.63, name='left')
right = openmc.XPlane(x0=0.63, name='right')
bottom = openmc.YPlane(y0=-0.63, name='bottom')
top = openmc.YPlane(y0=0.63, name='top')
left.boundary_type = 'reflective'
right.boundary_type = 'reflective'
top.boundary_type = 'reflective'
bottom.boundary_type = 'reflective'
# Instantiate Cells
fuel_pin = openmc.Cell(name='cell 1')
cladding = openmc.Cell(name='cell 3')
water = openmc.Cell(name='cell 2')
# Use surface half-spaces to define regions
fuel_pin.region = -fuel_or
cladding.region = +fuel_or & -clad_or
water.region = +clad_or & +left & -right & +bottom & -top
# Register Materials with Cells
fuel_pin.fill = fuel
cladding.fill = clad
water.fill = hot_water
# Instantiate Universe
root = openmc.Universe(universe_id=0, name='root universe')
# Register Cells with Universe
root.add_cells([fuel_pin, cladding, water])
# Instantiate a Geometry, register the root Universe, and export to XML
self.geometry.root_universe = root
def build_default_settings(self):
self.settings.batches = 10
self.settings.inactive = 5
self.settings.particles = 100
self.settings.source = Source(space=Box([-0.63, -0.63, -1],
[0.63, 0.63, 1],
only_fissionable=True))
def build_defualt_plots(self):
plot = openmc.Plot()
plot.filename = 'mat'
plot.origin = (0.0, 0.0, 0)
plot.width = (1.26, 1.26)
plot.pixels = (300, 300)
plot.color = 'mat'
self.plots.add_plot(plot)
class MGInputSet(InputSet):
def build_default_materials_and_geometry(self):
# Define materials needed for 1D/1G slab problem
@ -595,21 +702,21 @@ class MGInputSet(InputSet):
# Define surfaces.
# Assembly/Problem Boundary
left = openmc.XPlane(x0=0.0, surface_id=200,
boundary_type='reflective')
right = openmc.XPlane(x0=10.0, surface_id=201,
boundary_type='reflective')
left = openmc.XPlane(x0=0.0, surface_id=200,
boundary_type='reflective')
right = openmc.XPlane(x0=10.0, surface_id=201,
boundary_type='reflective')
bottom = openmc.YPlane(y0=0.0, surface_id=300,
boundary_type='reflective')
top = openmc.YPlane(y0=10.0, surface_id=301,
boundary_type='reflective')
top = openmc.YPlane(y0=10.0, surface_id=301,
boundary_type='reflective')
down = openmc.ZPlane(z0=0.0, surface_id=0,
boundary_type='reflective')
down = openmc.ZPlane(z0=0.0, surface_id=0,
boundary_type='reflective')
fuel_clad_intfc = openmc.ZPlane(z0=2.0, surface_id=1)
clad_lwtr_intfc = openmc.ZPlane(z0=2.4, surface_id=2)
up = openmc.ZPlane(z0=5.0, surface_id=3,
boundary_type='reflective')
up = openmc.ZPlane(z0=5.0, surface_id=3,
boundary_type='reflective')
# Define cells
c1 = openmc.Cell(cell_id=1)
@ -625,7 +732,7 @@ class MGInputSet(InputSet):
# Define root universe.
root = openmc.Universe(universe_id=0, name='root universe')
root.add_cells((c1,c2,c3))
root.add_cells((c1, c2, c3))
# Assign root universe to geometry
self.geometry.root_universe = root

1
tests/test_mgxs_library_ce_to_mg/inputs_true.dat Normal file
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@ -0,0 +1 @@
34d5891f6f17c2d4b686b814ba61ba0045bc4289e278b1c3c47dbba59b83837fcfe15f2b8d58e7a2b07627b73d51e40348d70e9ed36dbb7cc94468d61c068c4c

2
tests/test_mgxs_library_ce_to_mg/results_true.dat Normal file
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@ -0,0 +1,2 @@
k-combined:
1.094839E+00 1.203524E-02

94
tests/test_mgxs_library_ce_to_mg/test_mgxs_library_ce_to_mg.py Normal file
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@ -0,0 +1,94 @@
#!/usr/bin/env python
import os
import sys
import glob
import hashlib
sys.path.insert(0, os.pardir)
from testing_harness import PyAPITestHarness
from input_set import PinCellInputSet
import openmc
import openmc.mgxs
class MGXSTestHarness(PyAPITestHarness):
def _build_inputs(self):
# Set the input set to use the pincell model
self._input_set = PinCellInputSet()
# Generate inputs using parent class routine
super(MGXSTestHarness, self)._build_inputs()
# Initialize a two-group structure
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6,
20.])
# Initialize MGXS Library for a few cross section types
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
self.mgxs_lib.by_nuclide = False
self.mgxs_lib.mgxs_types = ['total', 'absorption', 'nu-fission matrix',
'nu-scatter matrix', 'multiplicity matrix']
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.correction = None
self.mgxs_lib.legendre_order = 3
self.mgxs_lib.domain_type = 'material'
self.mgxs_lib.build_library()
# Initialize a tallies file
self._input_set.tallies = openmc.Tallies()
self.mgxs_lib.add_to_tallies_file(self._input_set.tallies, merge=False)
self._input_set.tallies.export_to_xml()
def _run_openmc(self):
# Initial run
if self._opts.mpi_exec is not None:
returncode = openmc.run(mpi_procs=self._opts.mpi_np,
openmc_exec=self._opts.exe,
mpi_exec=self._opts.mpi_exec)
else:
returncode = openmc.run(openmc_exec=self._opts.exe)
assert returncode == 0, 'CE OpenMC calculation did not exit' \
'successfully.'
# Build MG Inputs
# Get data needed to execute Library calculations.
statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0]
sp = openmc.StatePoint(statepoint)
self.mgxs_lib.load_from_statepoint(sp)
self._input_set.mgxs_file, self._input_set.materials, \
self._input_set.geometry = self.mgxs_lib.create_mg_mode()
# Modify settings so we can run in MG mode
self._input_set.settings.cross_sections = './mgxs.xml'
self._input_set.settings.energy_mode = 'multi-group'
# Write modified input files
self._input_set.settings.export_to_xml()
self._input_set.geometry.export_to_xml()
self._input_set.materials.export_to_xml()
self._input_set.mgxs_file.export_to_xml()
# Dont need tallies.xml, so remove the file
if os.path.exists('./tallies.xml'):
os.remove('./tallies.xml')
# Re-run MG mode.
if self._opts.mpi_exec is not None:
returncode = openmc.run(mpi_procs=self._opts.mpi_np,
openmc_exec=self._opts.exe,
mpi_exec=self._opts.mpi_exec)
else:
returncode = openmc.run(openmc_exec=self._opts.exe)
def _cleanup(self):
super(MGXSTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'mgxs.xml')
if os.path.exists(f):
os.remove(f)
if __name__ == '__main__':
harness = MGXSTestHarness('statepoint.10.*', False)
harness.main()

2
tests/test_mgxs_library_condense/inputs_true.dat
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@ -1 +1 @@
104e7fb527770ac5d3fc636da7716e8fb05d55761253d30516c899f466e6b38ffd881611a3d0cdf65c6af058c32f6f6758c68782be7a170d21024bdae751862f
317a63a9dd3bfd84e969667b00f46018e56c04c356461a75103f63569e6b70c84d0da7f5e611faaf1b2631330b05ab4346223d3d843018ce0ce8876671a450c0

191
tests/test_mgxs_library_condense/results_true.dat
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@ -1,85 +1,108 @@
material group in nuclide mean std. dev.
0 1 1 total 0.412084 0.02359 material group in nuclide mean std. dev.
0 1 1 total 0.076425 0.003691 material group in group out nuclide moment mean std. dev.
0 1 1 1 total P0 0.384780 0.022253
1 1 1 1 total P1 0.039277 0.004308
2 1 1 1 total P2 0.017574 0.002402
3 1 1 1 total P3 0.012203 0.002164 material group out nuclide mean std. dev.
0 1 1 total 1.0 0.055333 material group in nuclide mean std. dev.
0 2 1 total 0.241262 0.00841 material group in nuclide mean std. dev.
0 2 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
0 2 1 1 total P0 0.272369 0.006872
1 2 1 1 total P1 0.031107 0.005483
2 2 1 1 total P2 0.025999 0.006151
3 2 1 1 total P3 0.003219 0.003312 material group out nuclide mean std. dev.
0 2 1 total 0.0 0.0 material group in nuclide mean std. dev.
0 3 1 total 0.400028 0.034667 material group in nuclide mean std. dev.
0 3 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
0 3 1 1 total P0 0.794999 0.036548
1 3 1 1 total P1 0.401537 0.016175
2 3 1 1 total P2 0.143623 0.008719
3 3 1 1 total P3 0.001991 0.004433 material group out nuclide mean std. dev.
0 3 1 total 0.0 0.0 material group in nuclide mean std. dev.
0 4 1 total 0.377402 0.072937 material group in nuclide mean std. dev.
0 4 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
0 4 1 1 total P0 0.727311 0.080096
1 4 1 1 total P1 0.355839 0.037901
2 4 1 1 total P2 0.124483 0.015823
3 4 1 1 total P3 0.012168 0.006224 material group out nuclide mean std. dev.
0 4 1 total 0.0 0.0 material group in nuclide mean std. dev.
0 5 1 total 0.0 0.0 material group in nuclide mean std. dev.
0 5 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
0 5 1 1 total P0 0.0 0.0
1 5 1 1 total P1 0.0 0.0
2 5 1 1 total P2 0.0 0.0
3 5 1 1 total P3 0.0 0.0 material group out nuclide mean std. dev.
0 5 1 total 0.0 0.0 material group in nuclide mean std. dev.
0 6 1 total 0.0 0.0 material group in nuclide mean std. dev.
0 6 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
0 6 1 1 total P0 0.0 0.0
1 6 1 1 total P1 0.0 0.0
2 6 1 1 total P2 0.0 0.0
3 6 1 1 total P3 0.0 0.0 material group out nuclide mean std. dev.
0 6 1 total 0.0 0.0 material group in nuclide mean std. dev.
0 7 1 total 0.0 0.0 material group in nuclide mean std. dev.
0 7 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
0 7 1 1 total P0 0.0 0.0
1 7 1 1 total P1 0.0 0.0
2 7 1 1 total P2 0.0 0.0
3 7 1 1 total P3 0.0 0.0 material group out nuclide mean std. dev.
0 7 1 total 0.0 0.0 material group in nuclide mean std. dev.
0 8 1 total 0.0 0.0 material group in nuclide mean std. dev.
0 8 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
0 8 1 1 total P0 0.0 0.0
1 8 1 1 total P1 0.0 0.0
2 8 1 1 total P2 0.0 0.0
3 8 1 1 total P3 0.0 0.0 material group out nuclide mean std. dev.
0 8 1 total 0.0 0.0 material group in nuclide mean std. dev.
0 9 1 total 0.600536 0.748875 material group in nuclide mean std. dev.
0 9 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
0 9 1 1 total P0 0.720380 0.771015
1 9 1 1 total P1 0.119844 0.184691
2 9 1 1 total P2 0.038522 0.064485
3 9 1 1 total P3 0.056023 0.050595 material group out nuclide mean std. dev.
0 9 1 total 0.0 0.0 material group in nuclide mean std. dev.
0 10 1 total 0.235515 0.613974 material group in nuclide mean std. dev.
0 10 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
0 10 1 1 total P0 0.501009 0.708534
1 10 1 1 total P1 0.265494 0.375465
2 10 1 1 total P2 0.141979 0.200788
3 10 1 1 total P3 0.074258 0.105017 material group out nuclide mean std. dev.
0 10 1 total 0.0 0.0 material group in nuclide mean std. dev.
0 11 1 total 0.510145 0.741941 material group in nuclide mean std. dev.
0 11 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
0 11 1 1 total P0 0.804661 0.817658
1 11 1 1 total P1 0.312803 0.315315
2 11 1 1 total P2 0.168113 0.172935
3 11 1 1 total P3 0.003808 0.037911 material group out nuclide mean std. dev.
0 11 1 total 0.0 0.0 material group in nuclide mean std. dev.
0 12 1 total 0.73836 0.825631 material group in nuclide mean std. dev.
0 12 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
0 12 1 1 total P0 0.943429 0.856119
1 12 1 1 total P1 0.220164 0.163180
2 12 1 1 total P2 0.052884 0.042440
3 12 1 1 total P3 0.039939 0.032867 material group out nuclide mean std. dev.
0 12 1 total 0.0 0.0
0 10000 1 total 0.453624 0.021053
material group in nuclide mean std. dev.
0 10000 1 total 0.400852 0.022858
material group in nuclide mean std. dev.
0 10000 1 total 0.400852 0.022858
material group in nuclide mean std. dev.
0 10000 1 total 0.064903 0.004313
material group in nuclide mean std. dev.
0 10000 1 total 0.028048 0.00458
material group in nuclide mean std. dev.
0 10000 1 total 0.036855 0.002622
material group in nuclide mean std. dev.
0 10000 1 total 0.090649 0.00641
material group in nuclide mean std. dev.
0 10000 1 total 7.137955 0.507364
material group in nuclide mean std. dev.
0 10000 1 total 0.388721 0.01783
material group in nuclide mean std. dev.
0 10000 1 total 0.389304 0.023076
material group in group out nuclide moment mean std. dev.
0 10000 1 1 total P0 0.389304 0.023146
1 10000 1 1 total P1 0.046224 0.005907
2 10000 1 1 total P2 0.017984 0.002883
3 10000 1 1 total P3 0.006628 0.002457
material group in group out nuclide moment mean std. dev.
0 10000 1 1 total P0 0.389304 0.023146
1 10000 1 1 total P1 0.046224 0.005907
2 10000 1 1 total P2 0.017984 0.002883
3 10000 1 1 total P3 0.006628 0.002457
material group in group out nuclide mean std. dev.
0 10000 1 1 total 1.0 0.066111
material group in group out nuclide mean std. dev.
0 10000 1 1 total 0.085835 0.005592
material group out nuclide mean std. dev.
0 10000 1 total 1.0 0.046071
material group in nuclide mean std. dev.
0 10001 1 total 0.311594 0.013793
material group in nuclide mean std. dev.
0 10001 1 total 0.279255 0.02919
material group in nuclide mean std. dev.
0 10001 1 total 0.279255 0.02919
material group in nuclide mean std. dev.
0 10001 1 total 0.00221 0.000286
material group in nuclide mean std. dev.
0 10001 1 total 0.00221 0.000286
material group in nuclide mean std. dev.
0 10001 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10001 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10001 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10001 1 total 0.309384 0.013551
material group in nuclide mean std. dev.
0 10001 1 total 0.307987 0.029308
material group in group out nuclide moment mean std. dev.
0 10001 1 1 total P0 0.307987 0.029308
1 10001 1 1 total P1 0.030617 0.007464
2 10001 1 1 total P2 0.018911 0.004323
3 10001 1 1 total P3 0.006235 0.003338
material group in group out nuclide moment mean std. dev.
0 10001 1 1 total P0 0.307987 0.029308
1 10001 1 1 total P1 0.030617 0.007464
2 10001 1 1 total P2 0.018911 0.004323
3 10001 1 1 total P3 0.006235 0.003338
material group in group out nuclide mean std. dev.
0 10001 1 1 total 1.0 0.095039
material group in group out nuclide mean std. dev.
0 10001 1 1 total 0.0 0.0
material group out nuclide mean std. dev.
0 10001 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10002 1 total 0.904999 0.043964
material group in nuclide mean std. dev.
0 10002 1 total 0.499184 0.040914
material group in nuclide mean std. dev.
0 10002 1 total 0.499184 0.040914
material group in nuclide mean std. dev.
0 10002 1 total 0.00606 0.000555
material group in nuclide mean std. dev.
0 10002 1 total 0.00606 0.000555
material group in nuclide mean std. dev.
0 10002 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10002 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10002 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10002 1 total 0.898938 0.043493
material group in nuclide mean std. dev.
0 10002 1 total 0.903415 0.043959
material group in group out nuclide moment mean std. dev.
0 10002 1 1 total P0 0.903415 0.043586
1 10002 1 1 total P1 0.410417 0.015877
2 10002 1 1 total P2 0.143301 0.007187
3 10002 1 1 total P3 0.008739 0.003571
material group in group out nuclide moment mean std. dev.
0 10002 1 1 total P0 0.903415 0.043586
1 10002 1 1 total P1 0.410417 0.015877
2 10002 1 1 total P2 0.143301 0.007187
3 10002 1 1 total P3 0.008739 0.003571
material group in group out nuclide mean std. dev.
0 10002 1 1 total 1.0 0.056867
material group in group out nuclide mean std. dev.
0 10002 1 1 total 0.0 0.0
material group out nuclide mean std. dev.
0 10002 1 total 0.0 0.0

15
tests/test_mgxs_library_condense/test_mgxs_library_condense.py
View file

@ -6,27 +6,28 @@ import glob
import hashlib
sys.path.insert(0, os.pardir)
from testing_harness import PyAPITestHarness
from input_set import PinCellInputSet
import openmc
import openmc.mgxs
class MGXSTestHarness(PyAPITestHarness):
def _build_inputs(self):
# The openmc.mgxs module needs a summary.h5 file
self._input_set.settings.output = {'summary': True}
# Set the input set to use the pincell model
self._input_set = PinCellInputSet()
# Generate inputs using parent class routine
super(MGXSTestHarness, self)._build_inputs()
# Initialize a two-group structure
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6, 20.])
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6,
20.])
# Initialize MGXS Library for a few cross section types
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
self.mgxs_lib.by_nuclide = False
self.mgxs_lib.mgxs_types = ['transport', 'nu-fission',
'nu-scatter matrix', 'chi']
# Test all MGXS types
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.legendre_order = 3
self.mgxs_lib.domain_type = 'material'
@ -57,7 +58,7 @@ class MGXSTestHarness(PyAPITestHarness):
for mgxs_type in condense_lib.mgxs_types:
mgxs = condense_lib.get_mgxs(domain, mgxs_type)
df = mgxs.get_pandas_dataframe()
outstr += df.to_string()
outstr += df.to_string() + '\n'
# Hash the results if necessary
if hash_output:

2
tests/test_mgxs_library_distribcell/inputs_true.dat
View file

@ -1 +1 @@
018bbbc2099f7b94180b391e46e42fc9a82498c60b3f8f7f4c91480ea373427932d287fe571d53b2397f329e71485e7155d7644f0f995bbcb458ba3e872ab043
88849ac150f9c389e67de96356dfceb0bde08643f68ca25699e67d263995b95893d7340a2b08b2f0f5075fc5020f73553c5287ec6c56ace2f35ce0214961e123

36
tests/test_mgxs_library_distribcell/results_true.dat
View file

@ -1,8 +1,36 @@
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.718919 0.520644 avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0 avg(distribcell) group in group out nuclide moment mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 1.145934 0.553822
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.718919 0.520644
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.718919 0.520644
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.019762 0.010629
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.019762 0.010629
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 1.126172 0.54344
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 1.142547 0.570131
avg(distribcell) group in group out nuclide moment mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P0 1.142547 0.570131
1 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P1 0.447381 0.216322
2 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P2 0.141202 0.066504
3 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P3 0.039228 0.024621 avg(distribcell) group out nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0
3 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P3 0.039228 0.024621
avg(distribcell) group in group out nuclide moment mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P0 1.142547 0.570131
1 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P1 0.447381 0.216322
2 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P2 0.141202 0.066504
3 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P3 0.039228 0.024621
avg(distribcell) group in group out nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total 1.0 0.529717
avg(distribcell) group in group out nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total 0.0 0.0
avg(distribcell) group out nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0

10
tests/test_mgxs_library_distribcell/test_mgxs_library_distribcell.py
View file

@ -12,10 +12,6 @@ import openmc.mgxs
class MGXSTestHarness(PyAPITestHarness):
def _build_inputs(self):
# The openmc.mgxs module needs a summary.h5 file
self._input_set.settings.output = {'summary': True}
# Generate inputs using parent class routine
super(MGXSTestHarness, self)._build_inputs()
@ -26,8 +22,8 @@ class MGXSTestHarness(PyAPITestHarness):
# for one material-filled cell in the geometry
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
self.mgxs_lib.by_nuclide = False
self.mgxs_lib.mgxs_types = ['transport', 'nu-fission',
'nu-scatter matrix', 'chi']
# Test all MGXS types
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.legendre_order = 3
self.mgxs_lib.domain_type = 'distribcell'
@ -59,7 +55,7 @@ class MGXSTestHarness(PyAPITestHarness):
for mgxs_type in avg_lib.mgxs_types:
mgxs = avg_lib.get_mgxs(domain, mgxs_type)
df = mgxs.get_pandas_dataframe()
outstr += df.to_string()
outstr += df.to_string() + '\n'
# Hash the results if necessary
if hash_output:

2
tests/test_mgxs_library_hdf5/inputs_true.dat
View file

@ -1 +1 @@
104e7fb527770ac5d3fc636da7716e8fb05d55761253d30516c899f466e6b38ffd881611a3d0cdf65c6af058c32f6f6758c68782be7a170d21024bdae751862f
317a63a9dd3bfd84e969667b00f46018e56c04c356461a75103f63569e6b70c84d0da7f5e611faaf1b2631330b05ab4346223d3d843018ce0ce8876671a450c0

381
tests/test_mgxs_library_hdf5/results_true.dat
View file

@ -1,240 +1,195 @@
domain=1 type=transport
[ 0.37274472 0.86160691]
[ 0.02426918 0.03234902]
domain=1 type=nu-fission
[ 0.02178897 0.71407658]
[ 0.00118187 0.04055185]
domain=1 type=nu-scatter matrix
[[[ 3.81546297e-01 4.43012537e-02 2.06462886e-02 1.36952959e-02]
[ 1.55945353e-03 -5.97269486e-04 -2.38789528e-04 1.75508083e-04]]
domain=10000 type=total
[ 0.41482549 0.66016992]
[ 0.02279291 0.04751893]
domain=10000 type=transport
[ 0.35685964 0.64764766]
[ 0.0254936 0.02370374]
domain=10000 type=nu-transport
[ 0.35685964 0.64764766]
[ 0.0254936 0.02370374]
domain=10000 type=absorption
[ 0.02740784 0.26451074]
[ 0.0026925 0.02336708]
domain=10000 type=capture
[ 0.01984455 0.07171935]
[ 0.0026433 0.02520786]
domain=10000 type=fission
[ 0.00756329 0.19279139]
[ 0.00050848 0.01710592]
domain=10000 type=nu-fission
[ 0.01943174 0.46977478]
[ 0.00132298 0.041682 ]
domain=10000 type=kappa-fission
[ 1.47456982 37.28689641]
[ 0.09923532 3.30837772]
domain=10000 type=scatter
[ 0.38741765 0.39565918]
[ 0.02062573 0.02512506]
domain=10000 type=nu-scatter
[ 0.38518839 0.4123894 ]
[ 0.02694562 0.01542528]
domain=10000 type=scatter matrix
[[[ 3.84199458e-01 5.18702843e-02 2.00688453e-02 9.47771571e-03]
[ 9.88930393e-04 -2.07234596e-04 -1.03366181e-04 2.34290623e-04]]
[[ 0.00000000e+00 0.00000000e+00 0.00000000e+00 0.00000000e+00]
[ 4.03915981e-01 -1.13103276e-02 -1.48065932e-02 -6.85505346e-03]]]
[[[ 0.02403322 0.00472203 0.00253903 0.00222437]
[ 0.00051015 0.00022485 0.00022157 0.00020939]]
[[ 9.24639909e-04 -7.67704968e-04 4.93788872e-04 -1.71497229e-04]
[ 4.11464759e-01 1.64817280e-02 6.37149049e-03 -1.04991221e-02]]]
[[[ 0.02700101 0.00698255 0.0028465 0.00223352]
[ 0.00048242 0.00014901 0.00018432 0.00012817]]
[[ 0. 0. 0. 0. ]
[ 0.01896646 0.00783919 0.00862908 0.00904704]]]
domain=1 type=chi
[[ 0.00092488 0.00076791 0.00049392 0.00017154]
[ 0.01524494 0.00450173 0.01055075 0.01043819]]]
domain=10000 type=nu-scatter matrix
[[[ 3.84199458e-01 5.18702843e-02 2.00688453e-02 9.47771571e-03]
[ 9.88930393e-04 -2.07234596e-04 -1.03366181e-04 2.34290623e-04]]
[[ 9.24639909e-04 -7.67704968e-04 4.93788872e-04 -1.71497229e-04]
[ 4.11464759e-01 1.64817280e-02 6.37149049e-03 -1.04991221e-02]]]
[[[ 0.02700101 0.00698255 0.0028465 0.00223352]
[ 0.00048242 0.00014901 0.00018432 0.00012817]]
[[ 0.00092488 0.00076791 0.00049392 0.00017154]
[ 0.01524494 0.00450173 0.01055075 0.01043819]]]
domain=10000 type=multiplicity matrix
[[ 1. 1.]
[ 1. 1.]]
[[ 0.07851646 0.68718427]
[ 1.41421356 0.04113035]]
domain=10000 type=nu-fission matrix
[[ 0.02014243 0. ]
[ 0.45436647 0. ]]
[[ 0.00314909 0. ]
[ 0.02742551 0. ]]
domain=10000 type=chi
[ 1. 0.]
[ 0.05533329 0. ]
domain=2 type=transport
[ 0.23725441 0.28593027]
[ 0.00818357 0.04879593]
domain=2 type=nu-fission
[ 0.04607052 0. ]
domain=10001 type=total
[ 0.31373767 0.3008214 ]
[ 0.0155819 0.02805245]
domain=10001 type=transport
[ 0.27322787 0.31237484]
[ 0.03311537 0.04960583]
domain=10001 type=nu-transport
[ 0.27322787 0.31237484]
[ 0.03311537 0.04960583]
domain=10001 type=absorption
[ 0.00157499 0.00540038]
[ 0.00032255 0.00061814]
domain=10001 type=capture
[ 0.00157499 0.00540038]
[ 0.00032255 0.00061814]
domain=10001 type=fission
[ 0. 0.]
[ 0. 0.]
domain=2 type=nu-scatter matrix
[[[ 0.27311543 0.03586102 0.02970389 0.00224892]
domain=10001 type=nu-fission
[ 0. 0.]
[ 0. 0.]
domain=10001 type=kappa-fission
[ 0. 0.]
[ 0. 0.]
domain=10001 type=scatter
[ 0.31216268 0.29542102]
[ 0.01532192 0.02744549]
domain=10001 type=nu-scatter
[ 0.31012074 0.29626427]
[ 0.03378811 0.04379223]
domain=10001 type=scatter matrix
[[[ 0.31012074 0.03822959 0.02074494 0.0079643 ]
[ 0. 0. 0. 0. ]]
[[ 0. 0. 0. 0. ]
[ 0.26405068 -0.02187959 -0.01529469 0.01403395]]]
[[[ 0.00625287 0.00587756 0.00664018 0.00337568]
[ 0.29626427 -0.01121364 0.00883657 -0.00327007]]]
[[[ 0.03378811 0.008484 0.00469561 0.00373162]
[ 0. 0. 0. 0. ]]
[[ 0. 0. 0. 0. ]
[ 0.04539742 0.01221814 0.01027609 0.01431818]]]
domain=2 type=chi
[ 0. 0.]
[ 0. 0.]
domain=3 type=transport
[ 0.28690578 1.41815062]
[ 0.02740142 0.26530756]
domain=3 type=nu-fission
[ 0. 0.]
[ 0. 0.]
domain=3 type=nu-scatter matrix
[[[ 0.64334557 0.38340871 0.15218526 0.00303724]
[ 0.02618721 0.00736219 -0.00273849 -0.00271989]]
[[ 0. 0. 0. 0. ]
[ 1.92421362 0.4984312 0.09120485 0.01705441]]]
[[[ 0.02837604 0.01644677 0.00957372 0.00464802]
[ 0.00166461 0.00093414 0.00075617 0.00055807]]
[[ 0. 0. 0. 0. ]
[ 0.28406198 0.06342067 0.01372628 0.01391602]]]
domain=3 type=chi
[ 0. 0.]
[ 0. 0.]
domain=4 type=transport
[ 0.24244686 1.25395921]
[ 0.06103082 0.38836257]
domain=4 type=nu-fission
[ 0. 0.]
[ 0. 0.]
domain=4 type=nu-scatter matrix
[[[ 0.54394096 0.32601136 0.13113269 0.01210477]
[ 0.023662 0.00752551 -0.00272975 -0.0031405 ]]
[[ 0. 0. 0. 0. ]
[ 1.76464845 0.50069481 0.09902596 0.03297543]]]
[[[ 0.06542705 0.03860196 0.0174751 0.00607268]
[ 0.00308328 0.00130111 0.00084112 0.00057761]]
[[ 0. 0. 0. 0. ]
[ 0.41620952 0.12217802 0.03871874 0.02510259]]]
domain=4 type=chi
[ 0. 0.]
[ 0. 0.]
domain=5 type=transport
[ 0. 0.]
[ 0. 0.]
domain=5 type=nu-fission
[ 0. 0.]
[ 0. 0.]
domain=5 type=nu-scatter matrix
[[[ 0. 0. 0. 0.]
[ 0. 0. 0. 0.]]
[[ 0. 0. 0. 0.]
[ 0. 0. 0. 0.]]]
[[[ 0. 0. 0. 0.]
[ 0. 0. 0. 0.]]
[[ 0. 0. 0. 0.]
[ 0. 0. 0. 0.]]]
domain=5 type=chi
[ 0. 0.]
[ 0. 0.]
domain=6 type=transport
[ 0. 0.]
[ 0. 0.]
domain=6 type=nu-fission
[ 0. 0.]
[ 0. 0.]
domain=6 type=nu-scatter matrix
[[[ 0. 0. 0. 0.]
[ 0. 0. 0. 0.]]
[[ 0. 0. 0. 0.]
[ 0. 0. 0. 0.]]]
[[[ 0. 0. 0. 0.]
[ 0. 0. 0. 0.]]
[[ 0. 0. 0. 0.]
[ 0. 0. 0. 0.]]]
domain=6 type=chi
[ 0. 0.]
[ 0. 0.]
domain=7 type=transport
[ 0. 0.]
[ 0. 0.]
domain=7 type=nu-fission
[ 0. 0.]
[ 0. 0.]
domain=7 type=nu-scatter matrix
[[[ 0. 0. 0. 0.]
[ 0. 0. 0. 0.]]
[[ 0. 0. 0. 0.]
[ 0. 0. 0. 0.]]]
[[[ 0. 0. 0. 0.]
[ 0. 0. 0. 0.]]
[[ 0. 0. 0. 0.]
[ 0. 0. 0. 0.]]]
domain=7 type=chi
[ 0. 0.]
[ 0. 0.]
domain=8 type=transport
[ 0. 0.]
[ 0. 0.]
domain=8 type=nu-fission
[ 0. 0.]
[ 0. 0.]
domain=8 type=nu-scatter matrix
[[[ 0. 0. 0. 0.]
[ 0. 0. 0. 0.]]
[[ 0. 0. 0. 0.]
[ 0. 0. 0. 0.]]]
[[[ 0. 0. 0. 0.]
[ 0. 0. 0. 0.]]
[[ 0. 0. 0. 0.]
[ 0. 0. 0. 0.]]]
domain=8 type=chi
[ 0. 0.]
[ 0. 0.]
domain=9 type=transport
[ 0.60053598 0. ]
[ 0.74887543 0. ]
domain=9 type=nu-fission
[ 0. 0.]
[ 0. 0.]
domain=9 type=nu-scatter matrix
[[[ 0.72037987 0.11984389 0.03852204 0.05602285]
[ 0.04379223 0.01618037 0.01150396 0.00732885]]]
domain=10001 type=nu-scatter matrix
[[[ 0.31012074 0.03822959 0.02074494 0.0079643 ]
[ 0. 0. 0. 0. ]]
[[ 0. 0. 0. 0. ]
[ 0. 0. 0. 0. ]]]
[[[ 0.77101455 0.18469083 0.06448453 0.05059534]
[ 0.29626427 -0.01121364 0.00883657 -0.00327007]]]
[[[ 0.03378811 0.008484 0.00469561 0.00373162]
[ 0. 0. 0. 0. ]]
[[ 0. 0. 0. 0. ]
[ 0. 0. 0. 0. ]]]
domain=9 type=chi
[ 0.04379223 0.01618037 0.01150396 0.00732885]]]
domain=10001 type=multiplicity matrix
[[ 1. 0.]
[ 0. 1.]]
[[ 0.1087787 0. ]
[ 0. 0.14242717]]
domain=10001 type=nu-fission matrix
[[ 0. 0.]
[ 0. 0.]]
[[ 0. 0.]
[ 0. 0.]]
domain=10001 type=chi
[ 0. 0.]
[ 0. 0.]
domain=10 type=transport
[ 0.23551495 0. ]
[ 0.61397415 0. ]
domain=10 type=nu-fission
domain=10002 type=total
[ 0.66457226 2.05238401]
[ 0.03121475 0.22434291]
domain=10002 type=transport
[ 0.29056526 1.51643801]
[ 0.02385185 0.23519727]
domain=10002 type=nu-transport
[ 0.29056526 1.51643801]
[ 0.02385185 0.23519727]
domain=10002 type=absorption
[ 0.0006904 0.03168726]
[ 4.41475687e-05 3.74655858e-03]
domain=10002 type=capture
[ 0.0006904 0.03168726]
[ 4.41475687e-05 3.74655858e-03]
domain=10002 type=fission
[ 0. 0.]
[ 0. 0.]
domain=10 type=nu-scatter matrix
[[[ 0.50100891 0.26549396 0.14197875 0.07425836]
[ 0. 0. 0. 0. ]]
domain=10002 type=nu-fission
[ 0. 0.]
[ 0. 0.]
domain=10002 type=kappa-fission
[ 0. 0.]
[ 0. 0.]
domain=10002 type=scatter
[ 0.66388186 2.02069676]
[ 0.03117268 0.22060445]
domain=10002 type=nu-scatter
[ 0.6712692 2.03538833]
[ 0.02618637 0.25806033]
domain=10002 type=scatter matrix
[[[ 6.39901485e-01 3.81167449e-01 1.52391898e-01 9.14802229e-03]
[ 3.13677198e-02 8.75772321e-03 -2.56790106e-03 -3.78480288e-03]]
[[ 0. 0. 0. 0. ]
[ 0. 0. 0. 0. ]]]
[[[ 0.70853359 0.37546516 0.20078827 0.10501718]
[ 0. 0. 0. 0. ]]
[[ 4.43343134e-04 3.99960414e-04 3.19562707e-04 2.13846969e-04]
[ 2.03494499e+00 5.09940513e-01 1.11174609e-01 2.49884357e-02]]]
[[[ 2.47091228e-02 1.62432649e-02 8.15627770e-03 3.88856214e-03]
[ 1.72811290e-03 9.25670501e-04 1.01398475e-03 8.17075571e-04]]
[[ 0. 0. 0. 0. ]
[ 0. 0. 0. 0. ]]]
domain=10 type=chi
[ 0. 0.]
[ 0. 0.]
domain=11 type=transport
[ 0.18632392 0.94598628]
[ 0.63212919 1.59113341]
domain=11 type=nu-fission
[ 0. 0.]
[ 0. 0.]
domain=11 type=nu-scatter matrix
[[[ 0.47812753 0.32367878 0.14337507 0.05400336]
[ 0.03187517 0.00858456 -0.01246962 -0.01132019]]
[[ 4.44850393e-04 4.01320183e-04 3.20649143e-04 2.14573997e-04]
[ 2.57799889e-01 5.12359063e-02 1.30198170e-02 8.31235256e-03]]]
domain=10002 type=nu-scatter matrix
[[[ 6.39901485e-01 3.81167449e-01 1.52391898e-01 9.14802229e-03]
[ 3.13677198e-02 8.75772321e-03 -2.56790106e-03 -3.78480288e-03]]
[[ 0. 0. 0. 0. ]
[ 1.20124973 0.28661101 0.21819147 -0.04851424]]]
[[[ 0.67617444 0.45775092 0.20276296 0.07637229]
[ 0.0450783 0.0121404 0.01763471 0.01600917]]
[[ 4.43343134e-04 3.99960414e-04 3.19562707e-04 2.13846969e-04]
[ 2.03494499e+00 5.09940513e-01 1.11174609e-01 2.49884357e-02]]]
[[[ 2.47091228e-02 1.62432649e-02 8.15627770e-03 3.88856214e-03]
[ 1.72811290e-03 9.25670501e-04 1.01398475e-03 8.17075571e-04]]
[[ 0. 0. 0. 0. ]
[ 1.69882367 0.40532917 0.30856933 0.0686095 ]]]
domain=11 type=chi
[ 0. 0.]
[ 0. 0.]
domain=12 type=transport
[ 0.21329208 1.3909745 ]
[ 0.27144387 2.13734565]
domain=12 type=nu-fission
[ 0. 0.]
[ 0. 0.]
domain=12 type=nu-scatter matrix
[[[ 0.40859392 0.22254143 0.0909719 0.03100368]
[ 0.02723959 -0.01008785 -0.00694631 0.00969231]]
[[ 0. 0. 0. 0. ]
[ 1.57432766 0.22974802 0.01417839 0.03899727]]]
[[[ 0.27812309 0.14577636 0.06962553 0.03598053]
[ 0.02955488 0.01094529 0.00753673 0.01051613]]
[[ 0. 0. 0. 0. ]
[ 2.22643553 0.32491277 0.02005128 0.05515046]]]
domain=12 type=chi
[[ 4.44850393e-04 4.01320183e-04 3.20649143e-04 2.14573997e-04]
[ 2.57799889e-01 5.12359063e-02 1.30198170e-02 8.31235256e-03]]]
domain=10002 type=multiplicity matrix
[[ 1. 1.]
[ 1. 1.]]
[[ 0.03860919 0.06766735]
[ 1.41421356 0.13592921]]
domain=10002 type=nu-fission matrix
[[ 0. 0.]
[ 0. 0.]]
[[ 0. 0.]
[ 0. 0.]]
domain=10002 type=chi
[ 0. 0.]
[ 0. 0.]

14
tests/test_mgxs_library_hdf5/test_mgxs_library_hdf5.py
View file

@ -7,27 +7,28 @@ import hashlib
import h5py
sys.path.insert(0, os.pardir)
from testing_harness import PyAPITestHarness
from input_set import PinCellInputSet
import openmc
import openmc.mgxs
class MGXSTestHarness(PyAPITestHarness):
def _build_inputs(self):
# The openmc.mgxs module needs a summary.h5 file
self._input_set.settings.output = {'summary': True}
# Set the input set to use the pincell model
self._input_set = PinCellInputSet()
# Generate inputs using parent class routine
super(MGXSTestHarness, self)._build_inputs()
# Initialize a two-group structure
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6, 20.])
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6,
20.])
# Initialize MGXS Library for a few cross section types
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
self.mgxs_lib.by_nuclide = False
self.mgxs_lib.mgxs_types = ['transport', 'nu-fission',
'nu-scatter matrix', 'chi']
# Test all MGXS types
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.legendre_order = 3
self.mgxs_lib.domain_type = 'material'
@ -75,7 +76,6 @@ class MGXSTestHarness(PyAPITestHarness):
return outstr
def _cleanup(self):
super(MGXSTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')

2
tests/test_mgxs_library_no_nuclides/inputs_true.dat
View file

@ -1 +1 @@
104e7fb527770ac5d3fc636da7716e8fb05d55761253d30516c899f466e6b38ffd881611a3d0cdf65c6af058c32f6f6758c68782be7a170d21024bdae751862f
317a63a9dd3bfd84e969667b00f46018e56c04c356461a75103f63569e6b70c84d0da7f5e611faaf1b2631330b05ab4346223d3d843018ce0ce8876671a450c0

494
tests/test_mgxs_library_no_nuclides/results_true.dat
View file

@ -1,265 +1,231 @@
material group in nuclide mean std. dev.
1 1 1 total 0.372745 0.024269
0 1 2 total 0.861607 0.032349 material group in nuclide mean std. dev.
1 1 1 total 0.021789 0.001182
0 1 2 total 0.714077 0.040552 material group in group out nuclide moment mean std. dev.
12 1 1 1 total P0 0.381546 0.024033
13 1 1 1 total P1 0.044301 0.004722
14 1 1 1 total P2 0.020646 0.002539
15 1 1 1 total P3 0.013695 0.002224
8 1 1 2 total P0 0.001559 0.000510
9 1 1 2 total P1 -0.000597 0.000225
10 1 1 2 total P2 -0.000239 0.000222
11 1 1 2 total P3 0.000176 0.000209
4 1 2 1 total P0 0.000000 0.000000
5 1 2 1 total P1 0.000000 0.000000
6 1 2 1 total P2 0.000000 0.000000
7 1 2 1 total P3 0.000000 0.000000
0 1 2 2 total P0 0.403916 0.018966
1 1 2 2 total P1 -0.011310 0.007839
2 1 2 2 total P2 -0.014807 0.008629
3 1 2 2 total P3 -0.006855 0.009047 material group out nuclide mean std. dev.
1 1 1 total 1.0 0.055333
0 1 2 total 0.0 0.000000 material group in nuclide mean std. dev.
1 2 1 total 0.237254 0.008184
0 2 2 total 0.285930 0.048796 material group in nuclide mean std. dev.
1 2 1 total 0.0 0.0
0 2 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
12 2 1 1 total P0 0.273115 0.006253
13 2 1 1 total P1 0.035861 0.005878
14 2 1 1 total P2 0.029704 0.006640
15 2 1 1 total P3 0.002249 0.003376
8 2 1 2 total P0 0.000000 0.000000
9 2 1 2 total P1 0.000000 0.000000
10 2 1 2 total P2 0.000000 0.000000
11 2 1 2 total P3 0.000000 0.000000
4 2 2 1 total P0 0.000000 0.000000
5 2 2 1 total P1 0.000000 0.000000
6 2 2 1 total P2 0.000000 0.000000
7 2 2 1 total P3 0.000000 0.000000
0 2 2 2 total P0 0.264051 0.045397
1 2 2 2 total P1 -0.021880 0.012218
2 2 2 2 total P2 -0.015295 0.010276
3 2 2 2 total P3 0.014034 0.014318 material group out nuclide mean std. dev.
1 2 1 total 0.0 0.0
0 2 2 total 0.0 0.0 material group in nuclide mean std. dev.
1 3 1 total 0.286906 0.027401
0 3 2 total 1.418151 0.265308 material group in nuclide mean std. dev.
1 3 1 total 0.0 0.0
0 3 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
12 3 1 1 total P0 0.643346 0.028376
13 3 1 1 total P1 0.383409 0.016447
14 3 1 1 total P2 0.152185 0.009574
15 3 1 1 total P3 0.003037 0.004648
8 3 1 2 total P0 0.026187 0.001665
9 3 1 2 total P1 0.007362 0.000934
10 3 1 2 total P2 -0.002738 0.000756
11 3 1 2 total P3 -0.002720 0.000558
4 3 2 1 total P0 0.000000 0.000000
5 3 2 1 total P1 0.000000 0.000000
6 3 2 1 total P2 0.000000 0.000000
7 3 2 1 total P3 0.000000 0.000000
0 3 2 2 total P0 1.924214 0.284062
1 3 2 2 total P1 0.498431 0.063421
2 3 2 2 total P2 0.091205 0.013726
3 3 2 2 total P3 0.017054 0.013916 material group out nuclide mean std. dev.
1 3 1 total 0.0 0.0
0 3 2 total 0.0 0.0 material group in nuclide mean std. dev.
1 4 1 total 0.242447 0.061031
0 4 2 total 1.253959 0.388363 material group in nuclide mean std. dev.
1 4 1 total 0.0 0.0
0 4 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
12 4 1 1 total P0 0.543941 0.065427
13 4 1 1 total P1 0.326011 0.038602
14 4 1 1 total P2 0.131133 0.017475
15 4 1 1 total P3 0.012105 0.006073
8 4 1 2 total P0 0.023662 0.003083
9 4 1 2 total P1 0.007526 0.001301
10 4 1 2 total P2 -0.002730 0.000841
11 4 1 2 total P3 -0.003140 0.000578
4 4 2 1 total P0 0.000000 0.000000
5 4 2 1 total P1 0.000000 0.000000
6 4 2 1 total P2 0.000000 0.000000
7 4 2 1 total P3 0.000000 0.000000
0 4 2 2 total P0 1.764648 0.416210
1 4 2 2 total P1 0.500695 0.122178
2 4 2 2 total P2 0.099026 0.038719
3 4 2 2 total P3 0.032975 0.025103 material group out nuclide mean std. dev.
1 4 1 total 0.0 0.0
0 4 2 total 0.0 0.0 material group in nuclide mean std. dev.
1 5 1 total 0.0 0.0
0 5 2 total 0.0 0.0 material group in nuclide mean std. dev.
1 5 1 total 0.0 0.0
0 5 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
12 5 1 1 total P0 0.0 0.0
13 5 1 1 total P1 0.0 0.0
14 5 1 1 total P2 0.0 0.0
15 5 1 1 total P3 0.0 0.0
8 5 1 2 total P0 0.0 0.0
9 5 1 2 total P1 0.0 0.0
10 5 1 2 total P2 0.0 0.0
11 5 1 2 total P3 0.0 0.0
4 5 2 1 total P0 0.0 0.0
5 5 2 1 total P1 0.0 0.0
6 5 2 1 total P2 0.0 0.0
7 5 2 1 total P3 0.0 0.0
0 5 2 2 total P0 0.0 0.0
1 5 2 2 total P1 0.0 0.0
2 5 2 2 total P2 0.0 0.0
3 5 2 2 total P3 0.0 0.0 material group out nuclide mean std. dev.
1 5 1 total 0.0 0.0
0 5 2 total 0.0 0.0 material group in nuclide mean std. dev.
1 6 1 total 0.0 0.0
0 6 2 total 0.0 0.0 material group in nuclide mean std. dev.
1 6 1 total 0.0 0.0
0 6 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
12 6 1 1 total P0 0.0 0.0
13 6 1 1 total P1 0.0 0.0
14 6 1 1 total P2 0.0 0.0
15 6 1 1 total P3 0.0 0.0
8 6 1 2 total P0 0.0 0.0
9 6 1 2 total P1 0.0 0.0
10 6 1 2 total P2 0.0 0.0
11 6 1 2 total P3 0.0 0.0
4 6 2 1 total P0 0.0 0.0
5 6 2 1 total P1 0.0 0.0
6 6 2 1 total P2 0.0 0.0
7 6 2 1 total P3 0.0 0.0
0 6 2 2 total P0 0.0 0.0
1 6 2 2 total P1 0.0 0.0
2 6 2 2 total P2 0.0 0.0
3 6 2 2 total P3 0.0 0.0 material group out nuclide mean std. dev.
1 6 1 total 0.0 0.0
0 6 2 total 0.0 0.0 material group in nuclide mean std. dev.
1 7 1 total 0.0 0.0
0 7 2 total 0.0 0.0 material group in nuclide mean std. dev.
1 7 1 total 0.0 0.0
0 7 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
12 7 1 1 total P0 0.0 0.0
13 7 1 1 total P1 0.0 0.0
14 7 1 1 total P2 0.0 0.0
15 7 1 1 total P3 0.0 0.0
8 7 1 2 total P0 0.0 0.0
9 7 1 2 total P1 0.0 0.0
10 7 1 2 total P2 0.0 0.0
11 7 1 2 total P3 0.0 0.0
4 7 2 1 total P0 0.0 0.0
5 7 2 1 total P1 0.0 0.0
6 7 2 1 total P2 0.0 0.0
7 7 2 1 total P3 0.0 0.0
0 7 2 2 total P0 0.0 0.0
1 7 2 2 total P1 0.0 0.0
2 7 2 2 total P2 0.0 0.0
3 7 2 2 total P3 0.0 0.0 material group out nuclide mean std. dev.
1 7 1 total 0.0 0.0
0 7 2 total 0.0 0.0 material group in nuclide mean std. dev.
1 8 1 total 0.0 0.0
0 8 2 total 0.0 0.0 material group in nuclide mean std. dev.
1 8 1 total 0.0 0.0
0 8 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
12 8 1 1 total P0 0.0 0.0
13 8 1 1 total P1 0.0 0.0
14 8 1 1 total P2 0.0 0.0
15 8 1 1 total P3 0.0 0.0
8 8 1 2 total P0 0.0 0.0
9 8 1 2 total P1 0.0 0.0
10 8 1 2 total P2 0.0 0.0
11 8 1 2 total P3 0.0 0.0
4 8 2 1 total P0 0.0 0.0
5 8 2 1 total P1 0.0 0.0
6 8 2 1 total P2 0.0 0.0
7 8 2 1 total P3 0.0 0.0
0 8 2 2 total P0 0.0 0.0
1 8 2 2 total P1 0.0 0.0
2 8 2 2 total P2 0.0 0.0
3 8 2 2 total P3 0.0 0.0 material group out nuclide mean std. dev.
1 8 1 total 0.0 0.0
0 8 2 total 0.0 0.0 material group in nuclide mean std. dev.
1 9 1 total 0.600536 0.748875
0 9 2 total 0.000000 0.000000 material group in nuclide mean std. dev.
1 9 1 total 0.0 0.0
0 9 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
12 9 1 1 total P0 0.720380 0.771015
13 9 1 1 total P1 0.119844 0.184691
14 9 1 1 total P2 0.038522 0.064485
15 9 1 1 total P3 0.056023 0.050595
8 9 1 2 total P0 0.000000 0.000000
9 9 1 2 total P1 0.000000 0.000000
10 9 1 2 total P2 0.000000 0.000000
11 9 1 2 total P3 0.000000 0.000000
4 9 2 1 total P0 0.000000 0.000000
5 9 2 1 total P1 0.000000 0.000000
6 9 2 1 total P2 0.000000 0.000000
7 9 2 1 total P3 0.000000 0.000000
0 9 2 2 total P0 0.000000 0.000000
1 9 2 2 total P1 0.000000 0.000000
2 9 2 2 total P2 0.000000 0.000000
3 9 2 2 total P3 0.000000 0.000000 material group out nuclide mean std. dev.
1 9 1 total 0.0 0.0
0 9 2 total 0.0 0.0 material group in nuclide mean std. dev.
1 10 1 total 0.235515 0.613974
0 10 2 total 0.000000 0.000000 material group in nuclide mean std. dev.
1 10 1 total 0.0 0.0
0 10 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
12 10 1 1 total P0 0.501009 0.708534
13 10 1 1 total P1 0.265494 0.375465
14 10 1 1 total P2 0.141979 0.200788
15 10 1 1 total P3 0.074258 0.105017
8 10 1 2 total P0 0.000000 0.000000
9 10 1 2 total P1 0.000000 0.000000
10 10 1 2 total P2 0.000000 0.000000
11 10 1 2 total P3 0.000000 0.000000
4 10 2 1 total P0 0.000000 0.000000
5 10 2 1 total P1 0.000000 0.000000
6 10 2 1 total P2 0.000000 0.000000
7 10 2 1 total P3 0.000000 0.000000
0 10 2 2 total P0 0.000000 0.000000
1 10 2 2 total P1 0.000000 0.000000
2 10 2 2 total P2 0.000000 0.000000
3 10 2 2 total P3 0.000000 0.000000 material group out nuclide mean std. dev.
1 10 1 total 0.0 0.0
0 10 2 total 0.0 0.0 material group in nuclide mean std. dev.
1 11 1 total 0.186324 0.632129
0 11 2 total 0.945986 1.591133 material group in nuclide mean std. dev.
1 11 1 total 0.0 0.0
0 11 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
12 11 1 1 total P0 0.478128 0.676174
13 11 1 1 total P1 0.323679 0.457751
14 11 1 1 total P2 0.143375 0.202763
15 11 1 1 total P3 0.054003 0.076372
8 11 1 2 total P0 0.031875 0.045078
9 11 1 2 total P1 0.008585 0.012140
10 11 1 2 total P2 -0.012470 0.017635
11 11 1 2 total P3 -0.011320 0.016009
4 11 2 1 total P0 0.000000 0.000000
5 11 2 1 total P1 0.000000 0.000000
6 11 2 1 total P2 0.000000 0.000000
7 11 2 1 total P3 0.000000 0.000000
0 11 2 2 total P0 1.201250 1.698824
1 11 2 2 total P1 0.286611 0.405329
2 11 2 2 total P2 0.218191 0.308569
3 11 2 2 total P3 -0.048514 0.068609 material group out nuclide mean std. dev.
1 11 1 total 0.0 0.0
0 11 2 total 0.0 0.0 material group in nuclide mean std. dev.
1 12 1 total 0.213292 0.271444
0 12 2 total 1.390975 2.137346 material group in nuclide mean std. dev.
1 12 1 total 0.0 0.0
0 12 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev.
12 12 1 1 total P0 0.408594 0.278123
13 12 1 1 total P1 0.222541 0.145776
14 12 1 1 total P2 0.090972 0.069626
15 12 1 1 total P3 0.031004 0.035981
8 12 1 2 total P0 0.027240 0.029555
9 12 1 2 total P1 -0.010088 0.010945
10 12 1 2 total P2 -0.006946 0.007537
11 12 1 2 total P3 0.009692 0.010516
4 12 2 1 total P0 0.000000 0.000000
5 12 2 1 total P1 0.000000 0.000000
6 12 2 1 total P2 0.000000 0.000000
7 12 2 1 total P3 0.000000 0.000000
0 12 2 2 total P0 1.574328 2.226436
1 12 2 2 total P1 0.229748 0.324913
2 12 2 2 total P2 0.014178 0.020051
3 12 2 2 total P3 0.038997 0.055150 material group out nuclide mean std. dev.
1 12 1 total 0.0 0.0
0 12 2 total 0.0 0.0
1 10000 1 total 0.414825 0.022793
0 10000 2 total 0.660170 0.047519
material group in nuclide mean std. dev.
1 10000 1 total 0.356860 0.025494
0 10000 2 total 0.647648 0.023704
material group in nuclide mean std. dev.
1 10000 1 total 0.356860 0.025494
0 10000 2 total 0.647648 0.023704
material group in nuclide mean std. dev.
1 10000 1 total 0.027408 0.002692
0 10000 2 total 0.264511 0.023367
material group in nuclide mean std. dev.
1 10000 1 total 0.019845 0.002643
0 10000 2 total 0.071719 0.025208
material group in nuclide mean std. dev.
1 10000 1 total 0.007563 0.000508
0 10000 2 total 0.192791 0.017106
material group in nuclide mean std. dev.
1 10000 1 total 0.019432 0.001323
0 10000 2 total 0.469775 0.041682
material group in nuclide mean std. dev.
1 10000 1 total 1.474570 0.099235
0 10000 2 total 37.286896 3.308378
material group in nuclide mean std. dev.
1 10000 1 total 0.387418 0.020626
0 10000 2 total 0.395659 0.025125
material group in nuclide mean std. dev.
1 10000 1 total 0.385188 0.026946
0 10000 2 total 0.412389 0.015425
material group in group out nuclide moment mean std. dev.
12 10000 1 1 total P0 0.384199 0.027001
13 10000 1 1 total P1 0.051870 0.006983
14 10000 1 1 total P2 0.020069 0.002846
15 10000 1 1 total P3 0.009478 0.002234
8 10000 1 2 total P0 0.000989 0.000482
9 10000 1 2 total P1 -0.000207 0.000149
10 10000 1 2 total P2 -0.000103 0.000184
11 10000 1 2 total P3 0.000234 0.000128
4 10000 2 1 total P0 0.000925 0.000925
5 10000 2 1 total P1 -0.000768 0.000768
6 10000 2 1 total P2 0.000494 0.000494
7 10000 2 1 total P3 -0.000171 0.000172
0 10000 2 2 total P0 0.411465 0.015245
1 10000 2 2 total P1 0.016482 0.004502
2 10000 2 2 total P2 0.006371 0.010551
3 10000 2 2 total P3 -0.010499 0.010438
material group in group out nuclide moment mean std. dev.
12 10000 1 1 total P0 0.384199 0.027001
13 10000 1 1 total P1 0.051870 0.006983
14 10000 1 1 total P2 0.020069 0.002846
15 10000 1 1 total P3 0.009478 0.002234
8 10000 1 2 total P0 0.000989 0.000482
9 10000 1 2 total P1 -0.000207 0.000149
10 10000 1 2 total P2 -0.000103 0.000184
11 10000 1 2 total P3 0.000234 0.000128
4 10000 2 1 total P0 0.000925 0.000925
5 10000 2 1 total P1 -0.000768 0.000768
6 10000 2 1 total P2 0.000494 0.000494
7 10000 2 1 total P3 -0.000171 0.000172
0 10000 2 2 total P0 0.411465 0.015245
1 10000 2 2 total P1 0.016482 0.004502
2 10000 2 2 total P2 0.006371 0.010551
3 10000 2 2 total P3 -0.010499 0.010438
material group in group out nuclide mean std. dev.
3 10000 1 1 total 1.0 0.078516
2 10000 1 2 total 1.0 0.687184
1 10000 2 1 total 1.0 1.414214
0 10000 2 2 total 1.0 0.041130
material group in group out nuclide mean std. dev.
3 10000 1 1 total 0.020142 0.003149
2 10000 1 2 total 0.000000 0.000000
1 10000 2 1 total 0.454366 0.027426
0 10000 2 2 total 0.000000 0.000000
material group out nuclide mean std. dev.
1 10000 1 total 1.0 0.046071
0 10000 2 total 0.0 0.000000
material group in nuclide mean std. dev.
1 10001 1 total 0.313738 0.015582
0 10001 2 total 0.300821 0.028052
material group in nuclide mean std. dev.
1 10001 1 total 0.273228 0.033115
0 10001 2 total 0.312375 0.049606
material group in nuclide mean std. dev.
1 10001 1 total 0.273228 0.033115
0 10001 2 total 0.312375 0.049606
material group in nuclide mean std. dev.
1 10001 1 total 0.001575 0.000323
0 10001 2 total 0.005400 0.000618
material group in nuclide mean std. dev.
1 10001 1 total 0.001575 0.000323
0 10001 2 total 0.005400 0.000618
material group in nuclide mean std. dev.
1 10001 1 total 0.0 0.0
0 10001 2 total 0.0 0.0
material group in nuclide mean std. dev.
1 10001 1 total 0.0 0.0
0 10001 2 total 0.0 0.0
material group in nuclide mean std. dev.
1 10001 1 total 0.0 0.0
0 10001 2 total 0.0 0.0
material group in nuclide mean std. dev.
1 10001 1 total 0.312163 0.015322
0 10001 2 total 0.295421 0.027445
material group in nuclide mean std. dev.
1 10001 1 total 0.310121 0.033788
0 10001 2 total 0.296264 0.043792
material group in group out nuclide moment mean std. dev.
12 10001 1 1 total P0 0.310121 0.033788
13 10001 1 1 total P1 0.038230 0.008484
14 10001 1 1 total P2 0.020745 0.004696
15 10001 1 1 total P3 0.007964 0.003732
8 10001 1 2 total P0 0.000000 0.000000
9 10001 1 2 total P1 0.000000 0.000000
10 10001 1 2 total P2 0.000000 0.000000
11 10001 1 2 total P3 0.000000 0.000000
4 10001 2 1 total P0 0.000000 0.000000
5 10001 2 1 total P1 0.000000 0.000000
6 10001 2 1 total P2 0.000000 0.000000
7 10001 2 1 total P3 0.000000 0.000000
0 10001 2 2 total P0 0.296264 0.043792
1 10001 2 2 total P1 -0.011214 0.016180
2 10001 2 2 total P2 0.008837 0.011504
3 10001 2 2 total P3 -0.003270 0.007329
material group in group out nuclide moment mean std. dev.
12 10001 1 1 total P0 0.310121 0.033788
13 10001 1 1 total P1 0.038230 0.008484
14 10001 1 1 total P2 0.020745 0.004696
15 10001 1 1 total P3 0.007964 0.003732
8 10001 1 2 total P0 0.000000 0.000000
9 10001 1 2 total P1 0.000000 0.000000
10 10001 1 2 total P2 0.000000 0.000000
11 10001 1 2 total P3 0.000000 0.000000
4 10001 2 1 total P0 0.000000 0.000000
5 10001 2 1 total P1 0.000000 0.000000
6 10001 2 1 total P2 0.000000 0.000000
7 10001 2 1 total P3 0.000000 0.000000
0 10001 2 2 total P0 0.296264 0.043792
1 10001 2 2 total P1 -0.011214 0.016180
2 10001 2 2 total P2 0.008837 0.011504
3 10001 2 2 total P3 -0.003270 0.007329
material group in group out nuclide mean std. dev.
3 10001 1 1 total 1.0 0.108779
2 10001 1 2 total 0.0 0.000000
1 10001 2 1 total 0.0 0.000000
0 10001 2 2 total 1.0 0.142427
material group in group out nuclide mean std. dev.
3 10001 1 1 total 0.0 0.0
2 10001 1 2 total 0.0 0.0
1 10001 2 1 total 0.0 0.0
0 10001 2 2 total 0.0 0.0
material group out nuclide mean std. dev.
1 10001 1 total 0.0 0.0
0 10001 2 total 0.0 0.0
material group in nuclide mean std. dev.
1 10002 1 total 0.664572 0.031215
0 10002 2 total 2.052384 0.224343
material group in nuclide mean std. dev.
1 10002 1 total 0.290565 0.023852
0 10002 2 total 1.516438 0.235197
material group in nuclide mean std. dev.
1 10002 1 total 0.290565 0.023852
0 10002 2 total 1.516438 0.235197
material group in nuclide mean std. dev.
1 10002 1 total 0.000690 0.000044
0 10002 2 total 0.031687 0.003747
material group in nuclide mean std. dev.
1 10002 1 total 0.000690 0.000044
0 10002 2 total 0.031687 0.003747
material group in nuclide mean std. dev.
1 10002 1 total 0.0 0.0
0 10002 2 total 0.0 0.0
material group in nuclide mean std. dev.
1 10002 1 total 0.0 0.0
0 10002 2 total 0.0 0.0
material group in nuclide mean std. dev.
1 10002 1 total 0.0 0.0
0 10002 2 total 0.0 0.0
material group in nuclide mean std. dev.
1 10002 1 total 0.663882 0.031173
0 10002 2 total 2.020697 0.220604
material group in nuclide mean std. dev.
1 10002 1 total 0.671269 0.026186
0 10002 2 total 2.035388 0.258060
material group in group out nuclide moment mean std. dev.
12 10002 1 1 total P0 0.639901 0.024709
13 10002 1 1 total P1 0.381167 0.016243
14 10002 1 1 total P2 0.152392 0.008156
15 10002 1 1 total P3 0.009148 0.003889
8 10002 1 2 total P0 0.031368 0.001728
9 10002 1 2 total P1 0.008758 0.000926
10 10002 1 2 total P2 -0.002568 0.001014
11 10002 1 2 total P3 -0.003785 0.000817
4 10002 2 1 total P0 0.000443 0.000445
5 10002 2 1 total P1 0.000400 0.000401
6 10002 2 1 total P2 0.000320 0.000321
7 10002 2 1 total P3 0.000214 0.000215
0 10002 2 2 total P0 2.034945 0.257800
1 10002 2 2 total P1 0.509941 0.051236
2 10002 2 2 total P2 0.111175 0.013020
3 10002 2 2 total P3 0.024988 0.008312
material group in group out nuclide moment mean std. dev.
12 10002 1 1 total P0 0.639901 0.024709
13 10002 1 1 total P1 0.381167 0.016243
14 10002 1 1 total P2 0.152392 0.008156
15 10002 1 1 total P3 0.009148 0.003889
8 10002 1 2 total P0 0.031368 0.001728
9 10002 1 2 total P1 0.008758 0.000926
10 10002 1 2 total P2 -0.002568 0.001014
11 10002 1 2 total P3 -0.003785 0.000817
4 10002 2 1 total P0 0.000443 0.000445
5 10002 2 1 total P1 0.000400 0.000401
6 10002 2 1 total P2 0.000320 0.000321
7 10002 2 1 total P3 0.000214 0.000215
0 10002 2 2 total P0 2.034945 0.257800
1 10002 2 2 total P1 0.509941 0.051236
2 10002 2 2 total P2 0.111175 0.013020
3 10002 2 2 total P3 0.024988 0.008312
material group in group out nuclide mean std. dev.
3 10002 1 1 total 1.0 0.038609
2 10002 1 2 total 1.0 0.067667
1 10002 2 1 total 1.0 1.414214
0 10002 2 2 total 1.0 0.135929
material group in group out nuclide mean std. dev.
3 10002 1 1 total 0.0 0.0
2 10002 1 2 total 0.0 0.0
1 10002 2 1 total 0.0 0.0
0 10002 2 2 total 0.0 0.0
material group out nuclide mean std. dev.
1 10002 1 total 0.0 0.0
0 10002 2 total 0.0 0.0

15
tests/test_mgxs_library_no_nuclides/test_mgxs_library_no_nuclides.py
View file

@ -6,27 +6,28 @@ import glob
import hashlib
sys.path.insert(0, os.pardir)
from testing_harness import PyAPITestHarness
from input_set import PinCellInputSet
import openmc
import openmc.mgxs
class MGXSTestHarness(PyAPITestHarness):
def _build_inputs(self):
# The openmc.mgxs module needs a summary.h5 file
self._input_set.settings.output = {'summary': True}
# Set the input set to use the pincell model
self._input_set = PinCellInputSet()
# Generate inputs using parent class routine
super(MGXSTestHarness, self)._build_inputs()
# Initialize a two-group structure
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6, 20.])
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6,
20.])
# Initialize MGXS Library for a few cross section types
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
self.mgxs_lib.by_nuclide = False
self.mgxs_lib.mgxs_types = ['transport', 'nu-fission',
'nu-scatter matrix', 'chi']
# Test all MGXS types
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.legendre_order = 3
self.mgxs_lib.domain_type = 'material'
@ -53,7 +54,7 @@ class MGXSTestHarness(PyAPITestHarness):
for mgxs_type in self.mgxs_lib.mgxs_types:
mgxs = self.mgxs_lib.get_mgxs(domain, mgxs_type)
df = mgxs.get_pandas_dataframe()
outstr += df.to_string()
outstr += df.to_string() + '\n'
# Hash the results if necessary
if hash_output:

2
tests/test_mgxs_library_nuclides/inputs_true.dat
View file

@ -1 +1 @@
791a2bd647b8bae03aafc39e29ff1ce1ffc44063b0d757ccba4e1eda6eb73b8a275020f4f5774b17dede49fbf15549787279c8b2fc45caba0097155b32e56fa8
eebb1469278f470b5859ed83e9b6526e7c4e3fed503bd22e414c6dc13b19b8e4cb6a44e3c14269e6e173f43056eda78268f455662ae119280bc18ea6a071dac7

2
tests/test_mgxs_library_nuclides/results_true.dat
View file

@ -1 +1 @@
1ee58383dc8ac46c5e0d72321cbc34b0dba531435d5e0e632cbbf9572eb7d669c8c8ad9f370345325afa0bdeb2f818b0f5204b7c4a7c4aaf58ded7acbd715ef8
a631b8a347f344d822e6300ed2576caa7c05a74daedeb4aaaabfb89570942cff1bbd47ad7f81306e668e12266404f7abdcf680fdfeb5a4835579892e32bf57e8

15
tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py
View file

@ -6,27 +6,28 @@ import glob
import hashlib
sys.path.insert(0, os.pardir)
from testing_harness import PyAPITestHarness
from input_set import PinCellInputSet
import openmc
import openmc.mgxs
class MGXSTestHarness(PyAPITestHarness):
def _build_inputs(self):
# The openmc.mgxs module needs a summary.h5 file
self._input_set.settings.output = {'summary': True}
# Set the input set to use the pincell model
self._input_set = PinCellInputSet()
# Generate inputs using parent class routine
super(MGXSTestHarness, self)._build_inputs()
# Initialize a two-group structure
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6, 20.])
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6,
20.])
# Initialize MGXS Library for a few cross section types
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
self.mgxs_lib.by_nuclide = True
self.mgxs_lib.mgxs_types = ['transport', 'nu-fission',
'nu-scatter matrix', 'chi']
# Test all MGXS types
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.legendre_order = 3
self.mgxs_lib.domain_type = 'material'
@ -53,7 +54,7 @@ class MGXSTestHarness(PyAPITestHarness):
for mgxs_type in self.mgxs_lib.mgxs_types:
mgxs = self.mgxs_lib.get_mgxs(domain, mgxs_type)
df = mgxs.get_pandas_dataframe()
outstr += df.to_string()
outstr += df.to_string() + '\n'
# Hash the results if necessary
if hash_output:

30
tests/testing_harness.py
View file

@ -6,7 +6,6 @@ import hashlib
from optparse import OptionParser
import os
import shutil
from subprocess import Popen, STDOUT, PIPE, call
import sys
import numpy as np
@ -18,6 +17,7 @@ import openmc
class TestHarness(object):
"""General class for running OpenMC regression tests."""
def __init__(self, statepoint_name, tallies_present=False):
self._sp_name = statepoint_name
self._tallies = tallies_present
@ -74,13 +74,13 @@ class TestHarness(object):
def _test_output_created(self):
"""Make sure statepoint.* and tallies.out have been created."""
statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))
assert len(statepoint) == 1, 'Either multiple or no statepoint files ' \
'exist.'
assert len(statepoint) == 1, 'Either multiple or no statepoint files' \
' exist.'
assert statepoint[0].endswith('h5'), \
'Statepoint file is not a HDF5 file.'
'Statepoint file is not a HDF5 file.'
if self._tallies:
assert os.path.exists(os.path.join(os.getcwd(), 'tallies.out')), \
'Tally output file does not exist.'
'Tally output file does not exist.'
def _get_results(self, hash_output=False):
"""Digest info in the statepoint and return as a string."""
@ -98,7 +98,7 @@ class TestHarness(object):
tally_num = 1
for tally_ind in sp.tallies:
tally = sp.tallies[tally_ind]
results = np.zeros((tally.sum.size*2, ))
results = np.zeros((tally.sum.size * 2, ))
results[0::2] = tally.sum.ravel()
results[1::2] = tally.sum_sq.ravel()
results = ['{0:12.6E}'.format(x) for x in results]
@ -144,6 +144,7 @@ class TestHarness(object):
class HashedTestHarness(TestHarness):
"""Specialized TestHarness that hashes the results."""
def _get_results(self):
"""Digest info in the statepoint and return as a string."""
return super(HashedTestHarness, self)._get_results(True)
@ -151,6 +152,7 @@ class HashedTestHarness(TestHarness):
class CMFDTestHarness(TestHarness):
"""Specialized TestHarness for running OpenMC CMFD tests."""
def _get_results(self):
"""Digest info in the statepoint and return as a string."""
# Read the statepoint file.
@ -184,6 +186,7 @@ class CMFDTestHarness(TestHarness):
class ParticleRestartTestHarness(TestHarness):
"""Specialized TestHarness for running OpenMC particle restart tests."""
def _run_openmc(self):
# Set arguments
args = {'openmc_exec': self._opts.exe}
@ -204,9 +207,9 @@ class ParticleRestartTestHarness(TestHarness):
"""Make sure the restart file has been created."""
particle = glob.glob(os.path.join(os.getcwd(), self._sp_name))
assert len(particle) == 1, 'Either multiple or no particle restart ' \
'files exist.'
'files exist.'
assert particle[0].endswith('h5'), \
'Particle restart file is not a HDF5 file.'
'Particle restart file is not a HDF5 file.'
def _get_results(self):
"""Digest info in the statepoint and return as a string."""
@ -229,10 +232,10 @@ class ParticleRestartTestHarness(TestHarness):
outstr += 'particle energy:\n'
outstr += "{0:12.6E}\n".format(p.energy)
outstr += 'particle xyz:\n'
outstr += "{0:12.6E} {1:12.6E} {2:12.6E}\n".format(p.xyz[0],p.xyz[1],
outstr += "{0:12.6E} {1:12.6E} {2:12.6E}\n".format(p.xyz[0], p.xyz[1],
p.xyz[2])
outstr += 'particle uvw:\n'
outstr += "{0:12.6E} {1:12.6E} {2:12.6E}\n".format(p.uvw[0],p.uvw[1],
outstr += "{0:12.6E} {1:12.6E} {2:12.6E}\n".format(p.uvw[0], p.uvw[1],
p.uvw[2])
return outstr
@ -240,13 +243,15 @@ class ParticleRestartTestHarness(TestHarness):
class PyAPITestHarness(TestHarness):
def __init__(self, statepoint_name, tallies_present=False, mg=False):
super(PyAPITestHarness, self).__init__(statepoint_name, tallies_present)
super(PyAPITestHarness, self).__init__(statepoint_name,
tallies_present)
self.parser.add_option('--build-inputs', dest='build_only',
action='store_true', default=False)
if mg:
self._input_set = MGInputSet()
else:
self._input_set = InputSet()
def main(self):
"""Accept commandline arguments and either run or update tests."""
(self._opts, self._args) = self.parser.parse_args()
@ -321,7 +326,8 @@ class PyAPITestHarness(TestHarness):
compare = filecmp.cmp('inputs_test.dat', 'inputs_true.dat')
if not compare:
f = open('inputs_test.dat')
for line in f.readlines(): print(line)
for line in f.readlines():
print(line)
f.close()
os.rename('inputs_test.dat', 'inputs_error.dat')
assert compare, 'Input files are broken.'