Merge branch 'develop' into photon-new

This commit is contained in:
amandalund 2018-06-28 16:19:54 -05:00
commit c912cdce70
264 changed files with 18402 additions and 17147 deletions

View file

@ -17,8 +17,8 @@ class DummyOperator(TransportOperator):
y_2(1.5) ~ 3.1726475740397628
"""
def __init__(self):
pass
def __init__(self, previous_results=None):
self.prev_res = previous_results
def __call__(self, vec, power, print_out=False):
"""Evaluates F(y)

View file

@ -56,7 +56,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />

View file

@ -1 +1 @@
3b76b468b9c0e7df6508189b75748a1b7b4f2b37486396749e1a15e536526336f70b60bb207095c39ecbd46822e8c8705ea81184a3c8546e7da09bb905d74637
bd3fd10177bc0c7b8542f15228decf8608de013872d201e6ae885cf9b5b6d7516ddb32044ee2f7fd5b207e7d37d5ce3f03e347a2e850953bba4fc26b150c89d2

View file

@ -26,62 +26,42 @@ tally 2:
2.667071E+01
1.600292E+01
1.293670E+01
2.252427E+00
2.605738E-01
4.268506E+01
9.161216E+01
3.022909E+01
4.598915E+01
3.873926E+00
7.615035E-01
5.680399E+01
1.623879E+02
4.033805E+01
8.196263E+01
5.280610E+00
1.414008E+00
6.814742E+01
2.331778E+02
4.851618E+01
1.182330E+02
6.261805E+00
1.983205E+00
7.392923E+01
2.740255E+02
5.253586E+01
1.384152E+02
6.733810E+00
2.278242E+00
7.332860E+01
2.698608E+02
5.227405E+01
1.371810E+02
6.714658E+00
2.273652E+00
6.830172E+01
2.340687E+02
4.867159E+01
1.188724E+02
6.215002E+00
1.956978E+00
5.885634E+01
1.736180E+02
4.170434E+01
8.719622E+01
5.253064E+00
1.396224E+00
4.371848E+01
9.592893E+01
3.106403E+01
4.844308E+01
3.818076E+00
7.509442E-01
2.338413E+01
2.752467E+01
1.636713E+01
1.347770E+01
2.219928E+00
2.515492E-01
tally 3:
1.538752E+01
1.196478E+01
@ -364,822 +344,47 @@ tally 4:
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0.000000E+00
tally 5:
1.538652E+01
1.196332E+01
2.252427E+00
2.605738E-01
2.911344E+01
4.267319E+01
3.873926E+00
7.615035E-01
3.884516E+01
7.604619E+01
5.280610E+00
1.414008E+00
4.672391E+01
1.096625E+02
6.261805E+00
1.983205E+00
5.058447E+01
1.283588E+02
6.733810E+00
2.278242E+00
5.033589E+01
1.271898E+02
6.714658E+00
2.273652E+00
4.687563E+01
1.102719E+02
6.215002E+00
1.956978E+00
4.013134E+01
8.075062E+01
5.253064E+00
1.396224E+00
2.996497E+01
4.508840E+01
3.818076E+00
7.509442E-01
1.574994E+01
1.248291E+01
2.219928E+00
2.515492E-01
cmfd indices
1.000000E+01
1.000000E+00

View file

@ -26,62 +26,42 @@ tally 2:
2.726751E+01
1.624000E+01
1.334217E+01
2.239367E+00
2.607315E-01
4.184801E+01
8.813954E+01
2.955600E+01
4.401685E+01
3.937924E+00
7.877545E-01
5.620224E+01
1.589242E+02
3.981400E+01
7.983679E+01
5.183337E+00
1.367303E+00
6.834724E+01
2.342245E+02
4.869600E+01
1.189597E+02
6.288549E+00
1.997858E+00
7.481522E+01
2.802998E+02
5.346500E+01
1.431835E+02
6.691123E+00
2.252645E+00
7.381412E+01
2.733775E+02
5.269700E+01
1.393729E+02
6.846095E+00
2.360683E+00
6.907776E+01
2.396752E+02
4.918500E+01
1.215909E+02
6.400076E+00
2.073871E+00
5.783261E+01
1.680814E+02
4.107800E+01
8.480751E+01
5.269220E+00
1.404986E+00
4.120212E+01
8.516647E+01
2.930300E+01
4.310295E+01
3.730803E+00
7.015777E-01
2.228419E+01
2.504034E+01
1.554100E+01
1.217931E+01
2.126451E+00
2.315275E-01
tally 3:
1.561100E+01
1.233967E+01
@ -364,822 +344,47 @@ tally 4:
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0.000000E+00
tally 5:
1.560800E+01
1.233482E+01
2.239367E+00
2.607315E-01
2.847600E+01
4.087518E+01
3.937924E+00
7.877545E-01
3.833600E+01
7.405661E+01
5.183337E+00
1.367303E+00
4.686600E+01
1.101919E+02
6.288549E+00
1.997858E+00
5.154500E+01
1.331141E+02
6.691123E+00
2.252645E+00
5.067000E+01
1.288871E+02
6.846095E+00
2.360683E+00
4.737700E+01
1.128379E+02
6.400076E+00
2.073871E+00
3.952800E+01
7.854943E+01
5.269220E+00
1.404986E+00
2.818600E+01
3.989536E+01
3.730803E+00
7.015777E-01
1.497300E+01
1.131008E+01
2.126451E+00
2.315275E-01
cmfd indices
1.000000E+01
1.000000E+00

View file

@ -10,7 +10,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="mat">
<material depletable="true" id="1" name="mat">
<density units="atom/b-cm" value="0.069335" />
<nuclide ao="40.0" name="H1" />
<nuclide ao="1.0" name="U235" />

View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />

View file

@ -1,7 +1,7 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" universe="1" />
<cell id="11" material="2 3 void 2" region="-9" universe="11" />
<cell id="11" material="2 void 3 2" region="-9" universe="11" />
<cell id="12" material="1" region="9" universe="11" />
<cell fill="101" id="101" region="10 -11 12 -13" universe="0" />
<lattice id="101">
@ -26,11 +26,11 @@
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
<material id="2">
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="3">
<material depletable="true" id="3">
<density units="g/cc" value="2.0" />
<nuclide ao="1.0" name="U235" />
</material>

View file

@ -3,7 +3,7 @@ k-combined:
Cell
ID = 11
Name =
Fill = [2, 3, None, 2]
Fill = [2, None, 3, 2]
Region = -9
Rotation = None
Translation = None

View file

@ -34,7 +34,7 @@ class DistribmatTestHarness(PyAPITestHarness):
r0 = openmc.ZCylinder(R=0.3)
c11 = openmc.Cell(cell_id=11, region=-r0)
c11.fill = [dense_fuel, light_fuel, None, dense_fuel]
c11.fill = [dense_fuel, None, light_fuel, dense_fuel]
c12 = openmc.Cell(cell_id=12, region=+r0, fill=moderator)
fuel_univ = openmc.Universe(universe_id=11, cells=[c11, c12])

View file

@ -14,11 +14,11 @@ class EntropyTestHarness(TestHarness):
with StatePoint(statepoint) as sp:
# Write out k-combined.
outstr = 'k-combined:\n'
outstr += '{0:12.6E} {1:12.6E}\n'.format(*sp.k_combined)
outstr += '{:12.6E} {:12.6E}\n'.format(sp.k_combined.n, sp.k_combined.s)
# Write out entropy data.
outstr += 'entropy:\n'
results = ['{0:12.6E}'.format(x) for x in sp.entropy]
results = ['{:12.6E}'.format(x) for x in sp.entropy]
outstr += '\n'.join(results) + '\n'
return outstr

View file

@ -3,10 +3,10 @@ k-combined:
tally 1:
1.548980E-02
2.399339E-04
1.278781E-02
1.635280E-04
1.426319E-02
2.034385E-04
1.278781E-02
1.635280E-04
1.018927E-02
1.038213E-04
tally 2:

View file

@ -1 +1 @@
386147796cf64c908002a81bc47af6763a14811ba6c457ca790653ceb8ef1c6b0376b94783f9746baf7389f18321b788c72758ec56ffd05fa3146139e6e53308
a1f6ccf0bef1075ffc12e7fa058a44c83360801ba6e2c76f00e1bd7e9543fe1832777b122321dcb1cfb5fc1165ce84f711a65ca83903dd57cd09652e003daf62

View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
@ -156,7 +156,7 @@
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="2" name="Zircaloy">
<material depletable="true" id="2" name="Zircaloy">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />

View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
@ -327,18 +327,27 @@
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="4" type="meshsurface">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<filter id="5" type="meshsurface">
<bins>2</bins>
</filter>
<filter id="3" type="mesh">
<bins>3</bins>
</filter>
<filter id="6" type="meshsurface">
<bins>3</bins>
</filter>
<tally id="1" name="tally 1">
<filters>1</filters>
<scores>total</scores>
</tally>
<tally id="2" name="tally 2">
<filters>1</filters>
<filters>4</filters>
<scores>current</scores>
</tally>
<tally id="3" name="tally 3">
@ -346,7 +355,7 @@
<scores>total</scores>
</tally>
<tally id="4" name="tally 4">
<filters>2</filters>
<filters>5</filters>
<scores>current</scores>
</tally>
<tally id="5" name="tally 5">
@ -354,7 +363,7 @@
<scores>total</scores>
</tally>
<tally id="6" name="tally 6">
<filters>3</filters>
<filters>6</filters>
<scores>current</scores>
</tally>
</tallies>

View file

@ -1 +1 @@
804d161cb8eae506d3247a533d122f44a01d3cedd566b3c65c71a0b51326dd9b97f8bbf45af7304b500476f3f854d91b10ccad94122d15f23641b05b835fada6
46950c046648faaa5ff3cb7b4fdd03667ae3c6da96a7ed8121761291de452cf88481f53e967ed52407d77d90109ae24839967a22ae216531a0e1491f5051ea72

View file

@ -30,6 +30,9 @@ class FilterMeshTestHarness(HashedPyAPITestHarness):
mesh_1d_filter = openmc.MeshFilter(mesh_1d)
mesh_2d_filter = openmc.MeshFilter(mesh_2d)
mesh_3d_filter = openmc.MeshFilter(mesh_3d)
meshsurf_1d_filter = openmc.MeshSurfaceFilter(mesh_1d)
meshsurf_2d_filter = openmc.MeshSurfaceFilter(mesh_2d)
meshsurf_3d_filter = openmc.MeshSurfaceFilter(mesh_3d)
# Initialized the tallies
tally = openmc.Tally(name='tally 1')
@ -38,7 +41,7 @@ class FilterMeshTestHarness(HashedPyAPITestHarness):
self._model.tallies.append(tally)
tally = openmc.Tally(name='tally 2')
tally.filters = [mesh_1d_filter]
tally.filters = [meshsurf_1d_filter]
tally.scores = ['current']
self._model.tallies.append(tally)
@ -48,7 +51,7 @@ class FilterMeshTestHarness(HashedPyAPITestHarness):
self._model.tallies.append(tally)
tally = openmc.Tally(name='tally 4')
tally.filters = [mesh_2d_filter]
tally.filters = [meshsurf_2d_filter]
tally.scores = ['current']
self._model.tallies.append(tally)
@ -58,7 +61,7 @@ class FilterMeshTestHarness(HashedPyAPITestHarness):
self._model.tallies.append(tally)
tally = openmc.Tally(name='tally 6')
tally.filters = [mesh_3d_filter]
tally.filters = [meshsurf_3d_filter]
tally.scores = ['current']
self._model.tallies.append(tally)

View file

@ -5,7 +5,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1">
<material depletable="true" id="1">
<density units="g/cc" value="7.5" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.0001" name="U238" />

View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />

View file

@ -144,8 +144,8 @@ class MGXSTestHarness(PyAPITestHarness):
with openmc.StatePoint('statepoint.{}.h5'.format(batches)) as sp:
# Write out k-combined.
outstr += 'k-combined:\n'
form = '{0:12.6E} {1:12.6E}\n'
outstr += form.format(sp.k_combined[0], sp.k_combined[1])
form = '{:12.6E} {:12.6E}\n'
outstr += form.format(sp.k_combined.n, sp.k_combined.s)
return outstr

View file

@ -12,7 +12,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UO2 (2.4%)">
<material depletable="true" id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
@ -59,10 +59,13 @@
<filter id="7" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="14" type="material">
<filter id="11" type="legendre">
<order>3</order>
</filter>
<filter id="15" type="material">
<bins>2</bins>
</filter>
<filter id="27" type="material">
<filter id="29" type="material">
<bins>3</bins>
</filter>
<tally id="1">
@ -108,9 +111,9 @@
<estimator>analog</estimator>
</tally>
<tally id="8">
<filters>1 2 7</filters>
<filters>1 2 7 11</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="9">
@ -126,121 +129,121 @@
<estimator>analog</estimator>
</tally>
<tally id="11">
<filters>14 2</filters>
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="12">
<filters>14 2</filters>
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="13">
<filters>14 2</filters>
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="14">
<filters>14 2</filters>
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="15">
<filters>14 2</filters>
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="16">
<filters>14 2 7</filters>
<filters>15 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="17">
<filters>14 2</filters>
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="18">
<filters>14 2 7</filters>
<filters>15 2 7 11</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="19">
<filters>14 2 7</filters>
<filters>15 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="20">
<filters>14 2 7</filters>
<filters>15 2 7</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="21">
<filters>27 2</filters>
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="22">
<filters>27 2</filters>
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="23">
<filters>27 2</filters>
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="24">
<filters>27 2</filters>
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="25">
<filters>27 2</filters>
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="26">
<filters>27 2 7</filters>
<filters>29 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="27">
<filters>27 2</filters>
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="28">
<filters>27 2 7</filters>
<filters>29 2 7 11</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="29">
<filters>27 2 7</filters>
<filters>29 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="30">
<filters>27 2 7</filters>
<filters>29 2 7</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>

File diff suppressed because it is too large Load diff

View file

@ -18,32 +18,32 @@
0 1 1 total 0.388721 0.01783
material group in nuclide mean std. dev.
0 1 1 total 0.389304 0.023076
material group in group out nuclide moment mean std. dev.
0 1 1 1 total P0 0.389304 0.023146
1 1 1 1 total P1 0.046224 0.005907
2 1 1 1 total P2 0.017984 0.002883
3 1 1 1 total P3 0.006628 0.002457
material group in group out nuclide moment mean std. dev.
0 1 1 1 total P0 0.389304 0.023146
1 1 1 1 total P1 0.046224 0.005907
2 1 1 1 total P2 0.017984 0.002883
3 1 1 1 total P3 0.006628 0.002457
material group in group out legendre nuclide mean std. dev.
0 1 1 1 P0 total 0.389304 0.023146
1 1 1 1 P1 total 0.046224 0.005907
2 1 1 1 P2 total 0.017984 0.002883
3 1 1 1 P3 total 0.006628 0.002457
material group in group out legendre nuclide mean std. dev.
0 1 1 1 P0 total 0.389304 0.023146
1 1 1 1 P1 total 0.046224 0.005907
2 1 1 1 P2 total 0.017984 0.002883
3 1 1 1 P3 total 0.006628 0.002457
material group in group out nuclide mean std. dev.
0 1 1 1 total 1.0 0.066111
material group in group out nuclide mean std. dev.
0 1 1 1 total 0.085835 0.005592
material group in group out nuclide mean std. dev.
0 1 1 1 total 1.0 0.066111
material group in group out nuclide moment mean std. dev.
0 1 1 1 total P0 0.388721 0.031279
1 1 1 1 total P1 0.046155 0.006407
2 1 1 1 total P2 0.017957 0.003039
3 1 1 1 total P3 0.006618 0.002480
material group in group out nuclide moment mean std. dev.
0 1 1 1 total P0 0.388721 0.040482
1 1 1 1 total P1 0.046155 0.007097
2 1 1 1 total P2 0.017957 0.003262
3 1 1 1 total P3 0.006618 0.002518
material group in group out legendre nuclide mean std. dev.
0 1 1 1 P0 total 0.388721 0.031279
1 1 1 1 P1 total 0.046155 0.006407
2 1 1 1 P2 total 0.017957 0.003039
3 1 1 1 P3 total 0.006618 0.002480
material group in group out legendre nuclide mean std. dev.
0 1 1 1 P0 total 0.388721 0.040482
1 1 1 1 P1 total 0.046155 0.007097
2 1 1 1 P2 total 0.017957 0.003262
3 1 1 1 P3 total 0.006618 0.002518
material group out nuclide mean std. dev.
0 1 1 total 1.0 0.046071
material group out nuclide mean std. dev.
@ -109,32 +109,32 @@
0 2 1 total 0.309384 0.013551
material group in nuclide mean std. dev.
0 2 1 total 0.307987 0.029308
material group in group out nuclide moment mean std. dev.
0 2 1 1 total P0 0.307987 0.029308
1 2 1 1 total P1 0.030617 0.007464
2 2 1 1 total P2 0.018911 0.004323
3 2 1 1 total P3 0.006235 0.003338
material group in group out nuclide moment mean std. dev.
0 2 1 1 total P0 0.307987 0.029308
1 2 1 1 total P1 0.030617 0.007464
2 2 1 1 total P2 0.018911 0.004323
3 2 1 1 total P3 0.006235 0.003338
material group in group out legendre nuclide mean std. dev.
0 2 1 1 P0 total 0.307987 0.029308
1 2 1 1 P1 total 0.030617 0.007464
2 2 1 1 P2 total 0.018911 0.004323
3 2 1 1 P3 total 0.006235 0.003338
material group in group out legendre nuclide mean std. dev.
0 2 1 1 P0 total 0.307987 0.029308
1 2 1 1 P1 total 0.030617 0.007464
2 2 1 1 P2 total 0.018911 0.004323
3 2 1 1 P3 total 0.006235 0.003338
material group in group out nuclide mean std. dev.
0 2 1 1 total 1.0 0.095039
material group in group out nuclide mean std. dev.
0 2 1 1 total 0.0 0.0
material group in group out nuclide mean std. dev.
0 2 1 1 total 1.0 0.095039
material group in group out nuclide moment mean std. dev.
0 2 1 1 total P0 0.309384 0.032376
1 2 1 1 total P1 0.030756 0.007617
2 2 1 1 total P2 0.018997 0.004420
3 2 1 1 total P3 0.006263 0.003364
material group in group out nuclide moment mean std. dev.
0 2 1 1 total P0 0.309384 0.043735
1 2 1 1 total P1 0.030756 0.008159
2 2 1 1 total P2 0.018997 0.004775
3 2 1 1 total P3 0.006263 0.003417
material group in group out legendre nuclide mean std. dev.
0 2 1 1 P0 total 0.309384 0.032376
1 2 1 1 P1 total 0.030756 0.007617
2 2 1 1 P2 total 0.018997 0.004420
3 2 1 1 P3 total 0.006263 0.003364
material group in group out legendre nuclide mean std. dev.
0 2 1 1 P0 total 0.309384 0.043735
1 2 1 1 P1 total 0.030756 0.008159
2 2 1 1 P2 total 0.018997 0.004775
3 2 1 1 P3 total 0.006263 0.003417
material group out nuclide mean std. dev.
0 2 1 total 0.0 0.0
material group out nuclide mean std. dev.
@ -200,32 +200,32 @@
0 3 1 total 0.898938 0.043493
material group in nuclide mean std. dev.
0 3 1 total 0.903415 0.043959
material group in group out nuclide moment mean std. dev.
0 3 1 1 total P0 0.903415 0.043586
1 3 1 1 total P1 0.410417 0.015877
2 3 1 1 total P2 0.143301 0.007187
3 3 1 1 total P3 0.008739 0.003571
material group in group out nuclide moment mean std. dev.
0 3 1 1 total P0 0.903415 0.043586
1 3 1 1 total P1 0.410417 0.015877
2 3 1 1 total P2 0.143301 0.007187
3 3 1 1 total P3 0.008739 0.003571
material group in group out legendre nuclide mean std. dev.
0 3 1 1 P0 total 0.903415 0.043586
1 3 1 1 P1 total 0.410417 0.015877
2 3 1 1 P2 total 0.143301 0.007187
3 3 1 1 P3 total 0.008739 0.003571
material group in group out legendre nuclide mean std. dev.
0 3 1 1 P0 total 0.903415 0.043586
1 3 1 1 P1 total 0.410417 0.015877
2 3 1 1 P2 total 0.143301 0.007187
3 3 1 1 P3 total 0.008739 0.003571
material group in group out nuclide mean std. dev.
0 3 1 1 total 1.0 0.056867
material group in group out nuclide mean std. dev.
0 3 1 1 total 0.0 0.0
material group in group out nuclide mean std. dev.
0 3 1 1 total 1.0 0.056867
material group in group out nuclide moment mean std. dev.
0 3 1 1 total P0 0.898938 0.067118
1 3 1 1 total P1 0.408384 0.028127
2 3 1 1 total P2 0.142591 0.010824
3 3 1 1 total P3 0.008696 0.003588
material group in group out nuclide moment mean std. dev.
0 3 1 1 total P0 0.898938 0.084369
1 3 1 1 total P1 0.408384 0.036475
2 3 1 1 total P2 0.142591 0.013525
3 3 1 1 total P3 0.008696 0.003622
material group in group out legendre nuclide mean std. dev.
0 3 1 1 P0 total 0.898938 0.067118
1 3 1 1 P1 total 0.408384 0.028127
2 3 1 1 P2 total 0.142591 0.010824
3 3 1 1 P3 total 0.008696 0.003588
material group in group out legendre nuclide mean std. dev.
0 3 1 1 P0 total 0.898938 0.084369
1 3 1 1 P1 total 0.408384 0.036475
2 3 1 1 P2 total 0.142591 0.013525
3 3 1 1 P3 total 0.008696 0.003622
material group out nuclide mean std. dev.
0 3 1 total 0.0 0.0
material group out nuclide mean std. dev.

View file

@ -0,0 +1,344 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="Fuel" region="-1" universe="0" />
<cell id="2" material="2" name="Cladding" region="1 -2" universe="0" />
<cell id="3" material="3" name="Water" region="2 3 -4 5 -6" universe="0" />
<surface coeffs="0 0 0.39218" id="1" name="Fuel OR" type="z-cylinder" />
<surface coeffs="0 0 0.4572" id="2" name="Clad OR" type="z-cylinder" />
<surface boundary="reflective" coeffs="-0.63" id="3" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="0.63" id="4" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-0.63" id="5" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="0.63" id="6" name="top" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="3" name="Hot borated water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="material">
<bins>1</bins>
</filter>
<filter id="2" type="energy">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="3" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="4" type="legendre">
<order>1</order>
</filter>
<filter id="12" type="legendre">
<order>0</order>
</filter>
<filter id="19" type="material">
<bins>2</bins>
</filter>
<filter id="37" type="material">
<bins>3</bins>
</filter>
<tally id="1">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="2">
<filters>1 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="3">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="4">
<filters>1 2 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="5">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="6">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="7">
<filters>1 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="8">
<filters>1 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="9">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="11">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="12">
<filters>1 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="13">
<filters>1 2 3</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="14">
<filters>1 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="15">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="16">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="17">
<filters>19 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="18">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="19">
<filters>19 2 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="20">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="21">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="22">
<filters>19 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="23">
<filters>19 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="24">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="25">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="26">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="27">
<filters>19 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="28">
<filters>19 2 3</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="29">
<filters>19 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="30">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="31">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="32">
<filters>37 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="33">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="34">
<filters>37 2 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="35">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="36">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="37">
<filters>37 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="38">
<filters>37 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="39">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="40">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="41">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="42">
<filters>37 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="43">
<filters>37 2 3</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="44">
<filters>37 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="45">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
</tallies>

View file

@ -0,0 +1,60 @@
material group in group out nuclide mean std. dev.
3 1 1 1 total 0.332466 0.026533
2 1 1 2 total 0.000989 0.000482
1 1 2 1 total 0.000925 0.000925
0 1 2 2 total 0.396146 0.015707
material group in group out nuclide mean std. dev.
3 1 1 1 total 0.332466 0.026533
2 1 1 2 total 0.000989 0.000482
1 1 2 1 total 0.000925 0.000925
0 1 2 2 total 0.396146 0.015707
material group in group out nuclide mean std. dev.
3 1 1 1 total 0.334690 0.037288
2 1 1 2 total 0.000995 0.000489
1 1 2 1 total 0.000887 0.000889
0 1 2 2 total 0.379453 0.030118
material group in group out nuclide mean std. dev.
3 1 1 1 total 0.334690 0.048073
2 1 1 2 total 0.000995 0.000841
1 1 2 1 total 0.000887 0.001538
0 1 2 2 total 0.379453 0.034216
material group in group out nuclide mean std. dev.
3 2 1 1 total 0.271891 0.032748
2 2 1 2 total 0.000000 0.000000
1 2 2 1 total 0.000000 0.000000
0 2 2 2 total 0.307478 0.047512
material group in group out nuclide mean std. dev.
3 2 1 1 total 0.271891 0.032748
2 2 1 2 total 0.000000 0.000000
1 2 2 1 total 0.000000 0.000000
0 2 2 2 total 0.307478 0.047512
material group in group out nuclide mean std. dev.
3 2 1 1 total 0.273933 0.038207
2 2 1 2 total 0.000000 0.000000
1 2 2 1 total 0.000000 0.000000
0 2 2 2 total 0.306635 0.052777
material group in group out nuclide mean std. dev.
3 2 1 1 total 0.273933 0.051116
2 2 1 2 total 0.000000 0.000000
1 2 2 1 total 0.000000 0.000000
0 2 2 2 total 0.306635 0.067497
material group in group out nuclide mean std. dev.
3 3 1 1 total 0.258652 0.022596
2 3 1 2 total 0.031368 0.001728
1 3 2 1 total 0.000443 0.000445
0 3 2 2 total 1.482300 0.232582
material group in group out nuclide mean std. dev.
3 3 1 1 total 0.258652 0.022596
2 3 1 2 total 0.031368 0.001728
1 3 2 1 total 0.000443 0.000445
0 3 2 2 total 1.482300 0.232582
material group in group out nuclide mean std. dev.
3 3 1 1 total 0.251610 0.041472
2 3 1 2 total 0.031023 0.002232
1 3 2 1 total 0.000440 0.000445
0 3 2 2 total 1.467612 0.356408
material group in group out nuclide mean std. dev.
3 3 1 1 total 0.251610 0.048135
2 3 1 2 total 0.031023 0.003064
1 3 2 1 total 0.000440 0.000765
0 3 2 2 total 1.467612 0.449931

View file

@ -0,0 +1,63 @@
import hashlib
import openmc
import openmc.mgxs
from openmc.examples import pwr_pin_cell
from tests.testing_harness import PyAPITestHarness
class MGXSTestHarness(PyAPITestHarness):
def __init__(self, *args, **kwargs):
# Generate inputs using parent class routine
super().__init__(*args, **kwargs)
# Initialize a two-group structure
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625, 20.e6])
# Initialize MGXS Library for a few cross section types
self.mgxs_lib = openmc.mgxs.Library(self._model.geometry)
self.mgxs_lib.by_nuclide = False
# Test all MGXS types
self.mgxs_lib.mgxs_types = ['scatter matrix', 'nu-scatter matrix',
'consistent scatter matrix',
'consistent nu-scatter matrix']
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.correction = 'P0'
self.mgxs_lib.domain_type = 'material'
self.mgxs_lib.build_library()
# Add tallies
self.mgxs_lib.add_to_tallies_file(self._model.tallies, merge=False)
def _get_results(self, hash_output=False):
"""Digest info in the statepoint and return as a string."""
# Read the statepoint file.
sp = openmc.StatePoint(self._sp_name)
# Load the MGXS library from the statepoint
self.mgxs_lib.load_from_statepoint(sp)
# Build a string from Pandas Dataframe for each MGXS
outstr = ''
for domain in self.mgxs_lib.domains:
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() + '\n'
# Hash the results if necessary
if hash_output:
sha512 = hashlib.sha512()
sha512.update(outstr.encode('utf-8'))
outstr = sha512.hexdigest()
return outstr
def test_mgxs_library_correction():
model = pwr_pin_cell()
harness = MGXSTestHarness('statepoint.10.h5', model)
harness.main()

View file

@ -39,7 +39,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="Fuel">
<material depletable="true" id="1" name="Fuel">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
@ -86,7 +86,13 @@
<filter id="5" type="energyout">
<bins>0.0 20000000.0</bins>
</filter>
<filter id="59" type="delayedgroup">
<filter id="6" type="legendre">
<order>1</order>
</filter>
<filter id="28" type="legendre">
<order>3</order>
</filter>
<filter id="65" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
@ -120,9 +126,9 @@
<estimator>analog</estimator>
</tally>
<tally id="6">
<filters>1 5</filters>
<filters>1 5 6</filters>
<nuclides>total</nuclides>
<scores>scatter-1</scores>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="7">
@ -144,9 +150,9 @@
<estimator>analog</estimator>
</tally>
<tally id="10">
<filters>1 5</filters>
<filters>1 5 6</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-1</scores>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="11">
@ -246,9 +252,9 @@
<estimator>analog</estimator>
</tally>
<tally id="27">
<filters>1 2 5</filters>
<filters>1 2 5 28</filters>
<nuclides>total</nuclides>
<scores>scatter-P3</scores>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="28">
@ -258,9 +264,9 @@
<estimator>analog</estimator>
</tally>
<tally id="29">
<filters>1 2 5</filters>
<filters>1 2 5 28</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="30">
@ -306,9 +312,9 @@
<estimator>tracklength</estimator>
</tally>
<tally id="37">
<filters>1 2 5</filters>
<filters>1 2 5 28</filters>
<nuclides>total</nuclides>
<scores>scatter-P3</scores>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="38">
@ -324,139 +330,133 @@
<estimator>tracklength</estimator>
</tally>
<tally id="40">
<filters>1 2 5</filters>
<filters>1 2 5 28</filters>
<nuclides>total</nuclides>
<scores>scatter-P3</scores>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="41">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-0</scores>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="42">
<filters>1 2 5</filters>
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>scatter-0</scores>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="43">
<filters>1 2</filters>
<filters>1 5</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="44">
<filters>1 5</filters>
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="45">
<filters>1 2</filters>
<filters>1 5</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="46">
<filters>1 5</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="47">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="48">
<tally id="47">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>inverse-velocity</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="49">
<tally id="48">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="49">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="50">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="51">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="52">
<tally id="51">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="53">
<tally id="52">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="54">
<filters>1 59 2</filters>
<tally id="53">
<filters>1 65 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="54">
<filters>1 65 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="55">
<filters>1 59 2</filters>
<filters>1 65 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="56">
<filters>1 59 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="57">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="57">
<filters>1 65 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="58">
<filters>1 59 2</filters>
<filters>1 65 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="59">
<filters>1 59 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="60">
<filters>1 59 2</filters>
<filters>1 65 2</filters>
<nuclides>total</nuclides>
<scores>decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="61">
<tally id="60">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="62">
<filters>1 59 2 5</filters>
<tally id="61">
<filters>1 65 2 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>

View file

@ -18,32 +18,32 @@
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 total 0.390797 0.008717
sum(distribcell) group in nuclide mean std. dev.
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 total 0.387332 0.014241
sum(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 0.387009 0.014230
1 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P1 0.047179 0.004923
2 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P2 0.015713 0.003654
3 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P3 0.005378 0.003137
sum(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 0.387332 0.014241
1 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P1 0.047187 0.004933
2 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P2 0.015727 0.003654
3 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P3 0.005387 0.003141
sum(distribcell) group in group out legendre nuclide mean std. dev.
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 P0 total 0.387009 0.014230
1 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 P1 total 0.047179 0.004923
2 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 P2 total 0.015713 0.003654
3 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 P3 total 0.005378 0.003137
sum(distribcell) group in group out legendre nuclide mean std. dev.
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 P0 total 0.387332 0.014241
1 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 P1 total 0.047187 0.004933
2 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 P2 total 0.015727 0.003654
3 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 P3 total 0.005387 0.003141
sum(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 1.000834 0.037242
sum(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 0.094516 0.0059
sum(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 0.037213
sum(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 0.390797 0.016955
1 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P1 0.047641 0.005091
2 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P2 0.015866 0.003708
3 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P3 0.005430 0.003170
sum(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 0.391123 0.022356
1 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P1 0.047680 0.005395
2 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P2 0.015880 0.003758
3 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P3 0.005435 0.003179
sum(distribcell) group in group out legendre nuclide mean std. dev.
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 P0 total 0.390797 0.016955
1 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 P1 total 0.047641 0.005091
2 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 P2 total 0.015866 0.003708
3 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 P3 total 0.005430 0.003170
sum(distribcell) group in group out legendre nuclide mean std. dev.
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 P0 total 0.391123 0.022356
1 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 P1 total 0.047680 0.005395
2 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 P2 total 0.015880 0.003758
3 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 P3 total 0.005435 0.003179
sum(distribcell) group out nuclide mean std. dev.
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 total 1.0 0.080455
sum(distribcell) group out nuclide mean std. dev.

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@ -0,0 +1,269 @@
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<geometry>
<cell id="1" material="1" name="Fuel" region="-1" universe="0" />
<cell id="2" material="2" name="Cladding" region="1 -2" universe="0" />
<cell id="3" material="3" name="Water" region="2 3 -4 5 -6" universe="0" />
<surface coeffs="0 0 0.39218" id="1" name="Fuel OR" type="z-cylinder" />
<surface coeffs="0 0 0.4572" id="2" name="Clad OR" type="z-cylinder" />
<surface boundary="reflective" coeffs="-0.63" id="3" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="0.63" id="4" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-0.63" id="5" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="0.63" id="6" name="top" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="3" name="Hot borated water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
</source>
</settings>
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<tallies>
<filter id="1" type="material">
<bins>1</bins>
</filter>
<filter id="2" type="energy">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="3" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="4" type="mu">
<bins>-1.0 -0.818181818182 -0.636363636364 -0.454545454545 -0.272727272727 -0.0909090909091 0.0909090909091 0.272727272727 0.454545454545 0.636363636364 0.818181818182 1.0</bins>
</filter>
<filter id="17" type="material">
<bins>2</bins>
</filter>
<filter id="33" type="material">
<bins>3</bins>
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<tally id="1">
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<nuclides>total</nuclides>
<scores>flux</scores>
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<scores>nu-scatter</scores>
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</tally>
</tallies>

View file

@ -0,0 +1,540 @@
material group in group out mu bin nuclide mean std. dev.
33 1 1 1 1 total 0.025383 0.001933
34 1 1 1 2 total 0.027855 0.001701
35 1 1 1 3 total 0.031646 0.002913
36 1 1 1 4 total 0.028185 0.001430
37 1 1 1 5 total 0.030162 0.002739
38 1 1 1 6 total 0.029009 0.002713
39 1 1 1 7 total 0.030492 0.002907
40 1 1 1 8 total 0.035272 0.003860
41 1 1 1 9 total 0.043678 0.006074
42 1 1 1 10 total 0.044502 0.003030
43 1 1 1 11 total 0.058017 0.004319
22 1 1 2 1 total 0.000000 0.000000
23 1 1 2 2 total 0.000165 0.000165
24 1 1 2 3 total 0.000330 0.000202
25 1 1 2 4 total 0.000165 0.000165
26 1 1 2 5 total 0.000000 0.000000
27 1 1 2 6 total 0.000165 0.000165
28 1 1 2 7 total 0.000000 0.000000
29 1 1 2 8 total 0.000000 0.000000
30 1 1 2 9 total 0.000000 0.000000
31 1 1 2 10 total 0.000165 0.000165
32 1 1 2 11 total 0.000000 0.000000
11 1 2 1 1 total 0.000925 0.000925
12 1 2 1 2 total 0.000000 0.000000
13 1 2 1 3 total 0.000000 0.000000
14 1 2 1 4 total 0.000000 0.000000
15 1 2 1 5 total 0.000000 0.000000
16 1 2 1 6 total 0.000000 0.000000
17 1 2 1 7 total 0.000000 0.000000
18 1 2 1 8 total 0.000000 0.000000
19 1 2 1 9 total 0.000000 0.000000
20 1 2 1 10 total 0.000000 0.000000
21 1 2 1 11 total 0.000000 0.000000
0 1 2 2 1 total 0.037910 0.006498
1 1 2 2 2 total 0.031438 0.002377
2 1 2 2 3 total 0.036986 0.006429
3 1 2 2 4 total 0.029588 0.005627
4 1 2 2 5 total 0.036986 0.007359
5 1 2 2 6 total 0.035136 0.004110
6 1 2 2 7 total 0.037910 0.003188
7 1 2 2 8 total 0.041609 0.004489
8 1 2 2 9 total 0.040684 0.007710
9 1 2 2 10 total 0.043458 0.004638
10 1 2 2 11 total 0.039760 0.002920
material group in group out mu bin nuclide mean std. dev.
33 1 1 1 1 total 0.025383 0.001933
34 1 1 1 2 total 0.027855 0.001701
35 1 1 1 3 total 0.031646 0.002913
36 1 1 1 4 total 0.028185 0.001430
37 1 1 1 5 total 0.030162 0.002739
38 1 1 1 6 total 0.029009 0.002713
39 1 1 1 7 total 0.030492 0.002907
40 1 1 1 8 total 0.035272 0.003860
41 1 1 1 9 total 0.043678 0.006074
42 1 1 1 10 total 0.044502 0.003030
43 1 1 1 11 total 0.058017 0.004319
22 1 1 2 1 total 0.000000 0.000000
23 1 1 2 2 total 0.000165 0.000165
24 1 1 2 3 total 0.000330 0.000202
25 1 1 2 4 total 0.000165 0.000165
26 1 1 2 5 total 0.000000 0.000000
27 1 1 2 6 total 0.000165 0.000165
28 1 1 2 7 total 0.000000 0.000000
29 1 1 2 8 total 0.000000 0.000000
30 1 1 2 9 total 0.000000 0.000000
31 1 1 2 10 total 0.000165 0.000165
32 1 1 2 11 total 0.000000 0.000000
11 1 2 1 1 total 0.000925 0.000925
12 1 2 1 2 total 0.000000 0.000000
13 1 2 1 3 total 0.000000 0.000000
14 1 2 1 4 total 0.000000 0.000000
15 1 2 1 5 total 0.000000 0.000000
16 1 2 1 6 total 0.000000 0.000000
17 1 2 1 7 total 0.000000 0.000000
18 1 2 1 8 total 0.000000 0.000000
19 1 2 1 9 total 0.000000 0.000000
20 1 2 1 10 total 0.000000 0.000000
21 1 2 1 11 total 0.000000 0.000000
0 1 2 2 1 total 0.037910 0.006498
1 1 2 2 2 total 0.031438 0.002377
2 1 2 2 3 total 0.036986 0.006429
3 1 2 2 4 total 0.029588 0.005627
4 1 2 2 5 total 0.036986 0.007359
5 1 2 2 6 total 0.035136 0.004110
6 1 2 2 7 total 0.037910 0.003188
7 1 2 2 8 total 0.041609 0.004489
8 1 2 2 9 total 0.040684 0.007710
9 1 2 2 10 total 0.043458 0.004638
10 1 2 2 11 total 0.039760 0.002920
material group in group out mu bin nuclide mean std. dev.
33 1 1 1 1 total 0.025529 0.002197
34 1 1 1 2 total 0.028016 0.002047
35 1 1 1 3 total 0.031829 0.003196
36 1 1 1 4 total 0.028348 0.001833
37 1 1 1 5 total 0.030337 0.003012
38 1 1 1 6 total 0.029177 0.002969
39 1 1 1 7 total 0.030668 0.003172
40 1 1 1 8 total 0.035476 0.004135
41 1 1 1 9 total 0.043931 0.006358
42 1 1 1 10 total 0.044759 0.003536
43 1 1 1 11 total 0.058353 0.004934
22 1 1 2 1 total 0.000000 0.000000
23 1 1 2 2 total 0.000166 0.000166
24 1 1 2 3 total 0.000332 0.000204
25 1 1 2 4 total 0.000166 0.000166
26 1 1 2 5 total 0.000000 0.000000
27 1 1 2 6 total 0.000166 0.000166
28 1 1 2 7 total 0.000000 0.000000
29 1 1 2 8 total 0.000000 0.000000
30 1 1 2 9 total 0.000000 0.000000
31 1 1 2 10 total 0.000166 0.000166
32 1 1 2 11 total 0.000000 0.000000
11 1 2 1 1 total 0.000887 0.000890
12 1 2 1 2 total 0.000000 0.000000
13 1 2 1 3 total 0.000000 0.000000
14 1 2 1 4 total 0.000000 0.000000
15 1 2 1 5 total 0.000000 0.000000
16 1 2 1 6 total 0.000000 0.000000
17 1 2 1 7 total 0.000000 0.000000
18 1 2 1 8 total 0.000000 0.000000
19 1 2 1 9 total 0.000000 0.000000
20 1 2 1 10 total 0.000000 0.000000
21 1 2 1 11 total 0.000000 0.000000
0 1 2 2 1 total 0.036372 0.006773
1 1 2 2 2 total 0.030162 0.003165
2 1 2 2 3 total 0.035485 0.006687
3 1 2 2 4 total 0.028388 0.005781
4 1 2 2 5 total 0.035485 0.007518
5 1 2 2 6 total 0.033711 0.004644
6 1 2 2 7 total 0.036372 0.004045
7 1 2 2 8 total 0.039921 0.005195
8 1 2 2 9 total 0.039034 0.007923
9 1 2 2 10 total 0.041695 0.005386
10 1 2 2 11 total 0.038147 0.003944
material group in group out mu bin nuclide mean std. dev.
33 1 1 1 1 total 0.025529 0.002692
34 1 1 1 2 total 0.028016 0.002666
35 1 1 1 3 total 0.031829 0.003739
36 1 1 1 4 total 0.028348 0.002519
37 1 1 1 5 total 0.030337 0.003534
38 1 1 1 6 total 0.029177 0.003461
39 1 1 1 7 total 0.030668 0.003682
40 1 1 1 8 total 0.035476 0.004666
41 1 1 1 9 total 0.043931 0.006899
42 1 1 1 10 total 0.044759 0.004466
43 1 1 1 11 total 0.058353 0.006082
22 1 1 2 1 total 0.000000 0.000000
23 1 1 2 2 total 0.000166 0.000196
24 1 1 2 3 total 0.000332 0.000290
25 1 1 2 4 total 0.000166 0.000196
26 1 1 2 5 total 0.000000 0.000000
27 1 1 2 6 total 0.000166 0.000196
28 1 1 2 7 total 0.000000 0.000000
29 1 1 2 8 total 0.000000 0.000000
30 1 1 2 9 total 0.000000 0.000000
31 1 1 2 10 total 0.000166 0.000196
32 1 1 2 11 total 0.000000 0.000000
11 1 2 1 1 total 0.000887 0.001538
12 1 2 1 2 total 0.000000 0.000000
13 1 2 1 3 total 0.000000 0.000000
14 1 2 1 4 total 0.000000 0.000000
15 1 2 1 5 total 0.000000 0.000000
16 1 2 1 6 total 0.000000 0.000000
17 1 2 1 7 total 0.000000 0.000000
18 1 2 1 8 total 0.000000 0.000000
19 1 2 1 9 total 0.000000 0.000000
20 1 2 1 10 total 0.000000 0.000000
21 1 2 1 11 total 0.000000 0.000000
0 1 2 2 1 total 0.036372 0.007026
1 1 2 2 2 total 0.030162 0.003524
2 1 2 2 3 total 0.035485 0.006931
3 1 2 2 4 total 0.028388 0.005962
4 1 2 2 5 total 0.035485 0.007736
5 1 2 2 6 total 0.033711 0.004957
6 1 2 2 7 total 0.036372 0.004455
7 1 2 2 8 total 0.039921 0.005585
8 1 2 2 9 total 0.039034 0.008173
9 1 2 2 10 total 0.041695 0.005796
10 1 2 2 11 total 0.038147 0.004404
material group in group out mu bin nuclide mean std. dev.
33 2 1 1 1 total 0.026289 0.004089
34 2 1 1 2 total 0.018269 0.002939
35 2 1 1 3 total 0.025398 0.002153
36 2 1 1 4 total 0.024061 0.005097
37 2 1 1 5 total 0.022279 0.003375
38 2 1 1 6 total 0.027626 0.004817
39 2 1 1 7 total 0.025843 0.003039
40 2 1 1 8 total 0.026735 0.006742
41 2 1 1 9 total 0.027626 0.005213
42 2 1 1 10 total 0.036537 0.005920
43 2 1 1 11 total 0.049459 0.004153
22 2 1 2 1 total 0.000000 0.000000
23 2 1 2 2 total 0.000000 0.000000
24 2 1 2 3 total 0.000000 0.000000
25 2 1 2 4 total 0.000000 0.000000
26 2 1 2 5 total 0.000000 0.000000
27 2 1 2 6 total 0.000000 0.000000
28 2 1 2 7 total 0.000000 0.000000
29 2 1 2 8 total 0.000000 0.000000
30 2 1 2 9 total 0.000000 0.000000
31 2 1 2 10 total 0.000000 0.000000
32 2 1 2 11 total 0.000000 0.000000
11 2 2 1 1 total 0.000000 0.000000
12 2 2 1 2 total 0.000000 0.000000
13 2 2 1 3 total 0.000000 0.000000
14 2 2 1 4 total 0.000000 0.000000
15 2 2 1 5 total 0.000000 0.000000
16 2 2 1 6 total 0.000000 0.000000
17 2 2 1 7 total 0.000000 0.000000
18 2 2 1 8 total 0.000000 0.000000
19 2 2 1 9 total 0.000000 0.000000
20 2 2 1 10 total 0.000000 0.000000
21 2 2 1 11 total 0.000000 0.000000
0 2 2 2 1 total 0.024485 0.007210
1 2 2 2 2 total 0.036727 0.005548
2 2 2 2 3 total 0.041624 0.010918
3 2 2 2 4 total 0.019588 0.008569
4 2 2 2 5 total 0.022036 0.007526
5 2 2 2 6 total 0.019588 0.011549
6 2 2 2 7 total 0.022036 0.006454
7 2 2 2 8 total 0.036727 0.010282
8 2 2 2 9 total 0.022036 0.005164
9 2 2 2 10 total 0.031830 0.011864
10 2 2 2 11 total 0.019588 0.005336
material group in group out mu bin nuclide mean std. dev.
33 2 1 1 1 total 0.026289 0.004089
34 2 1 1 2 total 0.018269 0.002939
35 2 1 1 3 total 0.025398 0.002153
36 2 1 1 4 total 0.024061 0.005097
37 2 1 1 5 total 0.022279 0.003375
38 2 1 1 6 total 0.027626 0.004817
39 2 1 1 7 total 0.025843 0.003039
40 2 1 1 8 total 0.026735 0.006742
41 2 1 1 9 total 0.027626 0.005213
42 2 1 1 10 total 0.036537 0.005920
43 2 1 1 11 total 0.049459 0.004153
22 2 1 2 1 total 0.000000 0.000000
23 2 1 2 2 total 0.000000 0.000000
24 2 1 2 3 total 0.000000 0.000000
25 2 1 2 4 total 0.000000 0.000000
26 2 1 2 5 total 0.000000 0.000000
27 2 1 2 6 total 0.000000 0.000000
28 2 1 2 7 total 0.000000 0.000000
29 2 1 2 8 total 0.000000 0.000000
30 2 1 2 9 total 0.000000 0.000000
31 2 1 2 10 total 0.000000 0.000000
32 2 1 2 11 total 0.000000 0.000000
11 2 2 1 1 total 0.000000 0.000000
12 2 2 1 2 total 0.000000 0.000000
13 2 2 1 3 total 0.000000 0.000000
14 2 2 1 4 total 0.000000 0.000000
15 2 2 1 5 total 0.000000 0.000000
16 2 2 1 6 total 0.000000 0.000000
17 2 2 1 7 total 0.000000 0.000000
18 2 2 1 8 total 0.000000 0.000000
19 2 2 1 9 total 0.000000 0.000000
20 2 2 1 10 total 0.000000 0.000000
21 2 2 1 11 total 0.000000 0.000000
0 2 2 2 1 total 0.024485 0.007210
1 2 2 2 2 total 0.036727 0.005548
2 2 2 2 3 total 0.041624 0.010918
3 2 2 2 4 total 0.019588 0.008569
4 2 2 2 5 total 0.022036 0.007526
5 2 2 2 6 total 0.019588 0.011549
6 2 2 2 7 total 0.022036 0.006454
7 2 2 2 8 total 0.036727 0.010282
8 2 2 2 9 total 0.022036 0.005164
9 2 2 2 10 total 0.031830 0.011864
10 2 2 2 11 total 0.019588 0.005336
material group in group out mu bin nuclide mean std. dev.
33 2 1 1 1 total 0.026462 0.003961
34 2 1 1 2 total 0.018389 0.002854
35 2 1 1 3 total 0.025565 0.001877
36 2 1 1 4 total 0.024220 0.005027
37 2 1 1 5 total 0.022425 0.003262
38 2 1 1 6 total 0.027808 0.004704
39 2 1 1 7 total 0.026014 0.002854
40 2 1 1 8 total 0.026911 0.006690
41 2 1 1 9 total 0.027808 0.005114
42 2 1 1 10 total 0.036778 0.005752
43 2 1 1 11 total 0.049785 0.003610
22 2 1 2 1 total 0.000000 0.000000
23 2 1 2 2 total 0.000000 0.000000
24 2 1 2 3 total 0.000000 0.000000
25 2 1 2 4 total 0.000000 0.000000
26 2 1 2 5 total 0.000000 0.000000
27 2 1 2 6 total 0.000000 0.000000
28 2 1 2 7 total 0.000000 0.000000
29 2 1 2 8 total 0.000000 0.000000
30 2 1 2 9 total 0.000000 0.000000
31 2 1 2 10 total 0.000000 0.000000
32 2 1 2 11 total 0.000000 0.000000
11 2 2 1 1 total 0.000000 0.000000
12 2 2 1 2 total 0.000000 0.000000
13 2 2 1 3 total 0.000000 0.000000
14 2 2 1 4 total 0.000000 0.000000
15 2 2 1 5 total 0.000000 0.000000
16 2 2 1 6 total 0.000000 0.000000
17 2 2 1 7 total 0.000000 0.000000
18 2 2 1 8 total 0.000000 0.000000
19 2 2 1 9 total 0.000000 0.000000
20 2 2 1 10 total 0.000000 0.000000
21 2 2 1 11 total 0.000000 0.000000
0 2 2 2 1 total 0.024415 0.007393
1 2 2 2 2 total 0.036622 0.006106
2 2 2 2 3 total 0.041505 0.011274
3 2 2 2 4 total 0.019532 0.008656
4 2 2 2 5 total 0.021973 0.007663
5 2 2 2 6 total 0.019532 0.011599
6 2 2 2 7 total 0.021973 0.006620
7 2 2 2 8 total 0.036622 0.010574
8 2 2 2 9 total 0.021973 0.005378
9 2 2 2 10 total 0.031739 0.012040
10 2 2 2 11 total 0.019532 0.005496
material group in group out mu bin nuclide mean std. dev.
33 2 1 1 1 total 0.026462 0.004589
34 2 1 1 2 total 0.018389 0.003277
35 2 1 1 3 total 0.025565 0.002922
36 2 1 1 4 total 0.024220 0.005456
37 2 1 1 5 total 0.022425 0.003808
38 2 1 1 6 total 0.027808 0.005297
39 2 1 1 7 total 0.026014 0.003652
40 2 1 1 8 total 0.026911 0.007093
41 2 1 1 9 total 0.027808 0.005664
42 2 1 1 10 total 0.036778 0.006592
43 2 1 1 11 total 0.049785 0.005660
22 2 1 2 1 total 0.000000 0.000000
23 2 1 2 2 total 0.000000 0.000000
24 2 1 2 3 total 0.000000 0.000000
25 2 1 2 4 total 0.000000 0.000000
26 2 1 2 5 total 0.000000 0.000000
27 2 1 2 6 total 0.000000 0.000000
28 2 1 2 7 total 0.000000 0.000000
29 2 1 2 8 total 0.000000 0.000000
30 2 1 2 9 total 0.000000 0.000000
31 2 1 2 10 total 0.000000 0.000000
32 2 1 2 11 total 0.000000 0.000000
11 2 2 1 1 total 0.000000 0.000000
12 2 2 1 2 total 0.000000 0.000000
13 2 2 1 3 total 0.000000 0.000000
14 2 2 1 4 total 0.000000 0.000000
15 2 2 1 5 total 0.000000 0.000000
16 2 2 1 6 total 0.000000 0.000000
17 2 2 1 7 total 0.000000 0.000000
18 2 2 1 8 total 0.000000 0.000000
19 2 2 1 9 total 0.000000 0.000000
20 2 2 1 10 total 0.000000 0.000000
21 2 2 1 11 total 0.000000 0.000000
0 2 2 2 1 total 0.024415 0.008094
1 2 2 2 2 total 0.036622 0.007855
2 2 2 2 3 total 0.041505 0.012588
3 2 2 2 4 total 0.019532 0.009048
4 2 2 2 5 total 0.021973 0.008217
5 2 2 2 6 total 0.019532 0.011894
6 2 2 2 7 total 0.021973 0.007253
7 2 2 2 8 total 0.036622 0.011671
8 2 2 2 9 total 0.021973 0.006141
9 2 2 2 10 total 0.031739 0.012779
10 2 2 2 11 total 0.019532 0.006096
material group in group out mu bin nuclide mean std. dev.
33 3 1 1 1 total 0.007001 0.000582
34 3 1 1 2 total 0.007728 0.001008
35 3 1 1 3 total 0.006819 0.001120
36 3 1 1 4 total 0.006092 0.000787
37 3 1 1 5 total 0.007183 0.000663
38 3 1 1 6 total 0.011274 0.000704
39 3 1 1 7 total 0.042642 0.002093
40 3 1 1 8 total 0.074464 0.002664
41 3 1 1 9 total 0.119015 0.006892
42 3 1 1 10 total 0.153293 0.006049
43 3 1 1 11 total 0.204390 0.010619
22 3 1 2 1 total 0.000818 0.000302
23 3 1 2 2 total 0.000818 0.000094
24 3 1 2 3 total 0.001091 0.000234
25 3 1 2 4 total 0.001091 0.000310
26 3 1 2 5 total 0.002546 0.000607
27 3 1 2 6 total 0.002364 0.000340
28 3 1 2 7 total 0.004546 0.000835
29 3 1 2 8 total 0.004819 0.000831
30 3 1 2 9 total 0.006092 0.001113
31 3 1 2 10 total 0.004546 0.000757
32 3 1 2 11 total 0.002637 0.000371
11 3 2 1 1 total 0.000000 0.000000
12 3 2 1 2 total 0.000000 0.000000
13 3 2 1 3 total 0.000000 0.000000
14 3 2 1 4 total 0.000000 0.000000
15 3 2 1 5 total 0.000000 0.000000
16 3 2 1 6 total 0.000000 0.000000
17 3 2 1 7 total 0.000000 0.000000
18 3 2 1 8 total 0.000000 0.000000
19 3 2 1 9 total 0.000000 0.000000
20 3 2 1 10 total 0.000000 0.000000
21 3 2 1 11 total 0.000443 0.000445
0 3 2 2 1 total 0.088669 0.015373
1 3 2 2 2 total 0.098422 0.016029
2 3 2 2 3 total 0.126796 0.022922
3 3 2 2 4 total 0.118373 0.018371
4 3 2 2 5 total 0.131230 0.014538
5 3 2 2 6 total 0.167584 0.027220
6 3 2 2 7 total 0.180441 0.023605
7 3 2 2 8 total 0.213691 0.028779
8 3 2 2 9 total 0.236745 0.024777
9 3 2 2 10 total 0.333394 0.041247
10 3 2 2 11 total 0.339601 0.037814
material group in group out mu bin nuclide mean std. dev.
33 3 1 1 1 total 0.007001 0.000582
34 3 1 1 2 total 0.007728 0.001008
35 3 1 1 3 total 0.006819 0.001120
36 3 1 1 4 total 0.006092 0.000787
37 3 1 1 5 total 0.007183 0.000663
38 3 1 1 6 total 0.011274 0.000704
39 3 1 1 7 total 0.042642 0.002093
40 3 1 1 8 total 0.074464 0.002664
41 3 1 1 9 total 0.119015 0.006892
42 3 1 1 10 total 0.153293 0.006049
43 3 1 1 11 total 0.204390 0.010619
22 3 1 2 1 total 0.000818 0.000302
23 3 1 2 2 total 0.000818 0.000094
24 3 1 2 3 total 0.001091 0.000234
25 3 1 2 4 total 0.001091 0.000310
26 3 1 2 5 total 0.002546 0.000607
27 3 1 2 6 total 0.002364 0.000340
28 3 1 2 7 total 0.004546 0.000835
29 3 1 2 8 total 0.004819 0.000831
30 3 1 2 9 total 0.006092 0.001113
31 3 1 2 10 total 0.004546 0.000757
32 3 1 2 11 total 0.002637 0.000371
11 3 2 1 1 total 0.000000 0.000000
12 3 2 1 2 total 0.000000 0.000000
13 3 2 1 3 total 0.000000 0.000000
14 3 2 1 4 total 0.000000 0.000000
15 3 2 1 5 total 0.000000 0.000000
16 3 2 1 6 total 0.000000 0.000000
17 3 2 1 7 total 0.000000 0.000000
18 3 2 1 8 total 0.000000 0.000000
19 3 2 1 9 total 0.000000 0.000000
20 3 2 1 10 total 0.000000 0.000000
21 3 2 1 11 total 0.000443 0.000445
0 3 2 2 1 total 0.088669 0.015373
1 3 2 2 2 total 0.098422 0.016029
2 3 2 2 3 total 0.126796 0.022922
3 3 2 2 4 total 0.118373 0.018371
4 3 2 2 5 total 0.131230 0.014538
5 3 2 2 6 total 0.167584 0.027220
6 3 2 2 7 total 0.180441 0.023605
7 3 2 2 8 total 0.213691 0.028779
8 3 2 2 9 total 0.236745 0.024777
9 3 2 2 10 total 0.333394 0.041247
10 3 2 2 11 total 0.339601 0.037814
material group in group out mu bin nuclide mean std. dev.
33 3 1 1 1 total 0.006924 0.000646
34 3 1 1 2 total 0.007643 0.001048
35 3 1 1 3 total 0.006744 0.001144
36 3 1 1 4 total 0.006025 0.000819
37 3 1 1 5 total 0.007104 0.000721
38 3 1 1 6 total 0.011150 0.000841
39 3 1 1 7 total 0.042173 0.002735
40 3 1 1 8 total 0.073645 0.004084
41 3 1 1 9 total 0.117706 0.008446
42 3 1 1 10 total 0.151606 0.008778
43 3 1 1 11 total 0.202141 0.013551
22 3 1 2 1 total 0.000809 0.000301
23 3 1 2 2 total 0.000809 0.000099
24 3 1 2 3 total 0.001079 0.000236
25 3 1 2 4 total 0.001079 0.000310
26 3 1 2 5 total 0.002518 0.000610
27 3 1 2 6 total 0.002338 0.000351
28 3 1 2 7 total 0.004496 0.000848
29 3 1 2 8 total 0.004766 0.000847
30 3 1 2 9 total 0.006025 0.001130
31 3 1 2 10 total 0.004496 0.000773
32 3 1 2 11 total 0.002608 0.000383
11 3 2 1 1 total 0.000000 0.000000
12 3 2 1 2 total 0.000000 0.000000
13 3 2 1 3 total 0.000000 0.000000
14 3 2 1 4 total 0.000000 0.000000
15 3 2 1 5 total 0.000000 0.000000
16 3 2 1 6 total 0.000000 0.000000
17 3 2 1 7 total 0.000000 0.000000
18 3 2 1 8 total 0.000000 0.000000
19 3 2 1 9 total 0.000000 0.000000
20 3 2 1 10 total 0.000000 0.000000
21 3 2 1 11 total 0.000440 0.000443
0 3 2 2 1 total 0.088029 0.016753
1 3 2 2 2 total 0.097712 0.017664
2 3 2 2 3 total 0.125881 0.024808
3 3 2 2 4 total 0.117518 0.020437
4 3 2 2 5 total 0.130282 0.017687
5 3 2 2 6 total 0.166374 0.030012
6 3 2 2 7 total 0.179138 0.027327
7 3 2 2 8 total 0.212149 0.033068
8 3 2 2 9 total 0.235036 0.030744
9 3 2 2 10 total 0.330988 0.048491
10 3 2 2 11 total 0.337150 0.045927
material group in group out mu bin nuclide mean std. dev.
33 3 1 1 1 total 0.006924 0.000686
34 3 1 1 2 total 0.007643 0.001078
35 3 1 1 3 total 0.006744 0.001166
36 3 1 1 4 total 0.006025 0.000843
37 3 1 1 5 total 0.007104 0.000759
38 3 1 1 6 total 0.011150 0.000920
39 3 1 1 7 total 0.042173 0.003073
40 3 1 1 8 total 0.073645 0.004762
41 3 1 1 9 total 0.117706 0.009309
42 3 1 1 10 total 0.151606 0.010122
43 3 1 1 11 total 0.202141 0.015127
22 3 1 2 1 total 0.000809 0.000308
23 3 1 2 2 total 0.000809 0.000118
24 3 1 2 3 total 0.001079 0.000251
25 3 1 2 4 total 0.001079 0.000321
26 3 1 2 5 total 0.002518 0.000642
27 3 1 2 6 total 0.002338 0.000397
28 3 1 2 7 total 0.004496 0.000920
29 3 1 2 8 total 0.004766 0.000928
30 3 1 2 9 total 0.006025 0.001227
31 3 1 2 10 total 0.004496 0.000852
32 3 1 2 11 total 0.002608 0.000436
11 3 2 1 1 total 0.000000 0.000000
12 3 2 1 2 total 0.000000 0.000000
13 3 2 1 3 total 0.000000 0.000000
14 3 2 1 4 total 0.000000 0.000000
15 3 2 1 5 total 0.000000 0.000000
16 3 2 1 6 total 0.000000 0.000000
17 3 2 1 7 total 0.000000 0.000000
18 3 2 1 8 total 0.000000 0.000000
19 3 2 1 9 total 0.000000 0.000000
20 3 2 1 10 total 0.000000 0.000000
21 3 2 1 11 total 0.000440 0.000764
0 3 2 2 1 total 0.088029 0.018984
1 3 2 2 2 total 0.097712 0.020255
2 3 2 2 3 total 0.125881 0.027901
3 3 2 2 4 total 0.117518 0.023659
4 3 2 2 5 total 0.130282 0.022078
5 3 2 2 6 total 0.166374 0.034431
6 3 2 2 7 total 0.179138 0.032816
7 3 2 2 8 total 0.212149 0.039453
8 3 2 2 9 total 0.235036 0.038904
9 3 2 2 10 total 0.330988 0.058979
10 3 2 2 11 total 0.337150 0.057260

View file

@ -0,0 +1,64 @@
import hashlib
import openmc
import openmc.mgxs
from openmc.examples import pwr_pin_cell
from tests.testing_harness import PyAPITestHarness
class MGXSTestHarness(PyAPITestHarness):
def __init__(self, *args, **kwargs):
# Generate inputs using parent class routine
super().__init__(*args, **kwargs)
# Initialize a two-group structure
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625, 20.e6])
# Initialize MGXS Library for a few cross section types
self.mgxs_lib = openmc.mgxs.Library(self._model.geometry)
self.mgxs_lib.by_nuclide = False
# Test all MGXS types
self.mgxs_lib.mgxs_types = ['scatter matrix', 'nu-scatter matrix',
'consistent scatter matrix',
'consistent nu-scatter matrix']
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.scatter_format = 'histogram'
self.mgxs_lib.histogram_bins = 11
self.mgxs_lib.domain_type = 'material'
self.mgxs_lib.build_library()
# Add tallies
self.mgxs_lib.add_to_tallies_file(self._model.tallies, merge=False)
def _get_results(self, hash_output=False):
"""Digest info in the statepoint and return as a string."""
# Read the statepoint file.
sp = openmc.StatePoint(self._sp_name)
# Load the MGXS library from the statepoint
self.mgxs_lib.load_from_statepoint(sp)
# Build a string from Pandas Dataframe for each MGXS
outstr = ''
for domain in self.mgxs_lib.domains:
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() + '\n'
# Hash the results if necessary
if hash_output:
sha512 = hashlib.sha512()
sha512.update(outstr.encode('utf-8'))
outstr = sha512.hexdigest()
return outstr
def test_mgxs_library_histogram():
model = pwr_pin_cell()
harness = MGXSTestHarness('statepoint.10.h5', model)
harness.main()

View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
@ -323,7 +323,13 @@
<filter id="5" type="energyout">
<bins>0.0 20000000.0</bins>
</filter>
<filter id="59" type="delayedgroup">
<filter id="6" type="legendre">
<order>1</order>
</filter>
<filter id="28" type="legendre">
<order>3</order>
</filter>
<filter id="65" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
@ -357,9 +363,9 @@
<estimator>analog</estimator>
</tally>
<tally id="6">
<filters>1 5</filters>
<filters>1 5 6</filters>
<nuclides>total</nuclides>
<scores>scatter-1</scores>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="7">
@ -381,9 +387,9 @@
<estimator>analog</estimator>
</tally>
<tally id="10">
<filters>1 5</filters>
<filters>1 5 6</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-1</scores>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="11">
@ -483,9 +489,9 @@
<estimator>analog</estimator>
</tally>
<tally id="27">
<filters>1 2 5</filters>
<filters>1 2 5 28</filters>
<nuclides>total</nuclides>
<scores>scatter-P3</scores>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="28">
@ -495,9 +501,9 @@
<estimator>analog</estimator>
</tally>
<tally id="29">
<filters>1 2 5</filters>
<filters>1 2 5 28</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="30">
@ -543,9 +549,9 @@
<estimator>tracklength</estimator>
</tally>
<tally id="37">
<filters>1 2 5</filters>
<filters>1 2 5 28</filters>
<nuclides>total</nuclides>
<scores>scatter-P3</scores>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="38">
@ -561,139 +567,133 @@
<estimator>tracklength</estimator>
</tally>
<tally id="40">
<filters>1 2 5</filters>
<filters>1 2 5 28</filters>
<nuclides>total</nuclides>
<scores>scatter-P3</scores>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="41">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-0</scores>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="42">
<filters>1 2 5</filters>
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>scatter-0</scores>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="43">
<filters>1 2</filters>
<filters>1 5</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="44">
<filters>1 5</filters>
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="45">
<filters>1 2</filters>
<filters>1 5</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="46">
<filters>1 5</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="47">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="48">
<tally id="47">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>inverse-velocity</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="49">
<tally id="48">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="49">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="50">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="51">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="52">
<tally id="51">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="53">
<tally id="52">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="54">
<filters>1 59 2</filters>
<tally id="53">
<filters>1 65 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="54">
<filters>1 65 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="55">
<filters>1 59 2</filters>
<filters>1 65 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="56">
<filters>1 59 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="57">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
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View file

@ -1,182 +1,182 @@
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.762544 0.085298
1 1 2 1 1 total 0.653375 0.153317
2 2 1 1 1 total 0.644837 0.088457
2 1 2 1 1 total 0.644837 0.088457
1 2 1 1 1 total 0.653375 0.153317
3 2 2 1 1 total 0.676480 0.094215
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.473988 0.088732
1 1 2 1 1 total 0.379821 0.167092
2 2 1 1 1 total 0.399254 0.091318
2 1 2 1 1 total 0.399254 0.091318
1 2 1 1 1 total 0.379821 0.167092
3 2 2 1 1 total 0.424265 0.099551
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.473988 0.088732
1 1 2 1 1 total 0.379821 0.167092
2 2 1 1 1 total 0.399254 0.091318
2 1 2 1 1 total 0.399254 0.091318
1 2 1 1 1 total 0.379821 0.167092
3 2 2 1 1 total 0.424265 0.099551
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.027288 0.005813
1 1 2 1 1 total 0.019449 0.004420
2 2 1 1 1 total 0.020262 0.003701
2 1 2 1 1 total 0.020262 0.003701
1 2 1 1 1 total 0.019449 0.004420
3 2 2 1 1 total 0.021266 0.002869
mesh 1 group in nuclide mean std. dev.
x y z
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1 1 2 1 1 total 0.012153 0.003804
2 2 1 1 1 total 0.013018 0.003521
2 1 2 1 1 total 0.013018 0.003521
1 2 1 1 1 total 0.012153 0.003804
3 2 2 1 1 total 0.012965 0.002454
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.011251 0.003050
1 1 2 1 1 total 0.007296 0.001795
2 2 1 1 1 total 0.007243 0.001219
2 1 2 1 1 total 0.007243 0.001219
1 2 1 1 1 total 0.007296 0.001795
3 2 2 1 1 total 0.008301 0.001066
mesh 1 group in nuclide mean std. dev.
x y z
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1 1 2 1 1 total 0.017912 0.004426
2 2 1 1 1 total 0.017954 0.003077
2 1 2 1 1 total 0.017954 0.003077
1 2 1 1 1 total 0.017912 0.004426
3 2 2 1 1 total 0.020469 0.002617
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 2.177345e+06 589804.299388
1 1 2 1 1 total 1.413154e+06 347806.623417
2 2 1 1 1 total 1.404096e+06 236476.851953
2 1 2 1 1 total 1.404096e+06 236476.851953
1 2 1 1 1 total 1.413154e+06 347806.623417
3 2 2 1 1 total 1.608259e+06 206502.707865
mesh 1 group in nuclide mean std. dev.
x y z
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1 1 2 1 1 total 0.633925 0.149098
2 2 1 1 1 total 0.624575 0.084974
2 1 2 1 1 total 0.624575 0.084974
1 2 1 1 1 total 0.633925 0.149098
3 2 2 1 1 total 0.655214 0.091422
mesh 1 group in nuclide mean std. dev.
x y z
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1 1 2 1 1 total 0.640809 0.158369
2 2 1 1 1 total 0.628158 0.064356
2 1 2 1 1 total 0.628158 0.064356
1 2 1 1 1 total 0.640809 0.158369
3 2 2 1 1 total 0.645171 0.080467
mesh 1 group in group out nuclide moment mean std. dev.
x y z
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1 1 1 1 1 1 total P1 0.288556 0.024446
2 1 1 1 1 1 total P2 0.082441 0.011443
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5 1 2 1 1 1 total P1 0.273553 0.066437
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7 1 2 1 1 1 total P3 0.012229 0.003785
8 2 1 1 1 1 total P0 0.628158 0.064356
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11 2 1 1 1 1 total P3 0.019590 0.005345
12 2 2 1 1 1 total P0 0.645171 0.080467
13 2 2 1 1 1 total P1 0.252215 0.032154
14 2 2 1 1 1 total P2 0.089251 0.009734
15 2 2 1 1 1 total P3 0.004748 0.002987
mesh 1 group in group out nuclide moment mean std. dev.
x y z
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1 1 1 1 1 1 total P1 0.288556 0.024446
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7 1 2 1 1 1 total P3 0.012229 0.003785
8 2 1 1 1 1 total P0 0.628158 0.064356
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11 2 1 1 1 1 total P3 0.019590 0.005345
12 2 2 1 1 1 total P0 0.645171 0.080467
13 2 2 1 1 1 total P1 0.252215 0.032154
14 2 2 1 1 1 total P2 0.089251 0.009734
15 2 2 1 1 1 total P3 0.004748 0.002987
mesh 1 group in group out legendre nuclide mean std. dev.
x y z
0 1 1 1 1 1 P0 total 0.763779 0.070696
1 1 1 1 1 1 P1 total 0.288556 0.024446
2 1 1 1 1 1 P2 total 0.082441 0.011443
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4 2 1 1 1 1 P0 total 0.640809 0.158369
5 2 1 1 1 1 P1 total 0.273553 0.066437
6 2 1 1 1 1 P2 total 0.108446 0.024435
7 2 1 1 1 1 P3 total 0.012229 0.003785
12 2 2 1 1 1 P0 total 0.645171 0.080467
13 2 2 1 1 1 P1 total 0.252215 0.032154
14 2 2 1 1 1 P2 total 0.089251 0.009734
15 2 2 1 1 1 P3 total 0.004748 0.002987
mesh 1 group in group out legendre nuclide mean std. dev.
x y z
0 1 1 1 1 1 P0 total 0.763779 0.070696
1 1 1 1 1 1 P1 total 0.288556 0.024446
2 1 1 1 1 1 P2 total 0.082441 0.011443
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8 1 2 1 1 1 P0 total 0.628158 0.064356
9 1 2 1 1 1 P1 total 0.245583 0.022676
10 1 2 1 1 1 P2 total 0.086370 0.007833
11 1 2 1 1 1 P3 total 0.019590 0.005345
4 2 1 1 1 1 P0 total 0.640809 0.158369
5 2 1 1 1 1 P1 total 0.273553 0.066437
6 2 1 1 1 1 P2 total 0.108446 0.024435
7 2 1 1 1 1 P3 total 0.012229 0.003785
12 2 2 1 1 1 P0 total 0.645171 0.080467
13 2 2 1 1 1 P1 total 0.252215 0.032154
14 2 2 1 1 1 P2 total 0.089251 0.009734
15 2 2 1 1 1 P3 total 0.004748 0.002987
mesh 1 group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 1.0 0.108337
1 1 2 1 1 1 total 1.0 0.238517
2 2 1 1 1 1 total 1.0 0.113128
2 1 2 1 1 1 total 1.0 0.113128
1 2 1 1 1 1 total 1.0 0.238517
3 2 2 1 1 1 total 1.0 0.132597
mesh 1 group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 0.015584 0.003404
1 1 2 1 1 1 total 0.014200 0.003676
2 2 1 1 1 1 total 0.017684 0.002499
2 1 2 1 1 1 total 0.017684 0.002499
1 2 1 1 1 1 total 0.014200 0.003676
3 2 2 1 1 1 total 0.022409 0.002481
mesh 1 group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 1.0 0.108337
1 1 2 1 1 1 total 1.0 0.238517
2 2 1 1 1 1 total 1.0 0.113128
2 1 2 1 1 1 total 1.0 0.113128
1 2 1 1 1 1 total 1.0 0.238517
3 2 2 1 1 1 total 1.0 0.132597
mesh 1 group in group out nuclide moment mean std. dev.
x y z
0 1 1 1 1 1 total P0 0.735256 0.113047
1 1 1 1 1 1 total P1 0.277780 0.041434
2 1 1 1 1 1 total P2 0.079362 0.014706
3 1 1 1 1 1 total P3 -0.005417 0.012184
4 1 2 1 1 1 total P0 0.633925 0.212349
5 1 2 1 1 1 total P1 0.270615 0.089799
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7 1 2 1 1 1 total P3 0.012098 0.004637
8 2 1 1 1 1 total P0 0.624575 0.110512
9 2 1 1 1 1 total P1 0.244182 0.041824
10 2 1 1 1 1 total P2 0.085877 0.014634
11 2 1 1 1 1 total P3 0.019478 0.006012
12 2 2 1 1 1 total P0 0.655214 0.126119
13 2 2 1 1 1 total P1 0.256141 0.049765
14 2 2 1 1 1 total P2 0.090641 0.016563
15 2 2 1 1 1 total P3 0.004822 0.003115
mesh 1 group in group out nuclide moment mean std. dev.
x y z
0 1 1 1 1 1 total P0 0.735256 0.138292
1 1 1 1 1 1 total P1 0.277780 0.051210
2 1 1 1 1 1 total P2 0.079362 0.017035
3 1 1 1 1 1 total P3 -0.005417 0.012198
4 1 2 1 1 1 total P0 0.633925 0.260681
5 1 2 1 1 1 total P1 0.270615 0.110590
6 1 2 1 1 1 total P2 0.107281 0.042750
7 1 2 1 1 1 total P3 0.012098 0.005462
8 2 1 1 1 1 total P0 0.624575 0.131169
9 2 1 1 1 1 total P1 0.244182 0.050123
10 2 1 1 1 1 total P2 0.085877 0.017565
11 2 1 1 1 1 total P3 0.019478 0.006403
12 2 2 1 1 1 total P0 0.655214 0.153147
13 2 2 1 1 1 total P1 0.256141 0.060250
14 2 2 1 1 1 total P2 0.090641 0.020464
15 2 2 1 1 1 total P3 0.004822 0.003180
mesh 1 group in group out legendre nuclide mean std. dev.
x y z
0 1 1 1 1 1 P0 total 0.735256 0.113047
1 1 1 1 1 1 P1 total 0.277780 0.041434
2 1 1 1 1 1 P2 total 0.079362 0.014706
3 1 1 1 1 1 P3 total -0.005417 0.012184
8 1 2 1 1 1 P0 total 0.624575 0.110512
9 1 2 1 1 1 P1 total 0.244182 0.041824
10 1 2 1 1 1 P2 total 0.085877 0.014634
11 1 2 1 1 1 P3 total 0.019478 0.006012
4 2 1 1 1 1 P0 total 0.633925 0.212349
5 2 1 1 1 1 P1 total 0.270615 0.089799
6 2 1 1 1 1 P2 total 0.107281 0.034246
7 2 1 1 1 1 P3 total 0.012098 0.004637
12 2 2 1 1 1 P0 total 0.655214 0.126119
13 2 2 1 1 1 P1 total 0.256141 0.049765
14 2 2 1 1 1 P2 total 0.090641 0.016563
15 2 2 1 1 1 P3 total 0.004822 0.003115
mesh 1 group in group out legendre nuclide mean std. dev.
x y z
0 1 1 1 1 1 P0 total 0.735256 0.138292
1 1 1 1 1 1 P1 total 0.277780 0.051210
2 1 1 1 1 1 P2 total 0.079362 0.017035
3 1 1 1 1 1 P3 total -0.005417 0.012198
8 1 2 1 1 1 P0 total 0.624575 0.131169
9 1 2 1 1 1 P1 total 0.244182 0.050123
10 1 2 1 1 1 P2 total 0.085877 0.017565
11 1 2 1 1 1 P3 total 0.019478 0.006403
4 2 1 1 1 1 P0 total 0.633925 0.260681
5 2 1 1 1 1 P1 total 0.270615 0.110590
6 2 1 1 1 1 P2 total 0.107281 0.042750
7 2 1 1 1 1 P3 total 0.012098 0.005462
12 2 2 1 1 1 P0 total 0.655214 0.153147
13 2 2 1 1 1 P1 total 0.256141 0.060250
14 2 2 1 1 1 P2 total 0.090641 0.020464
15 2 2 1 1 1 P3 total 0.004822 0.003180
mesh 1 group out nuclide mean std. dev.
x y z
0 1 1 1 1 total 1.0 0.300047
1 1 2 1 1 total 1.0 0.262180
2 2 1 1 1 total 1.0 0.178169
2 1 2 1 1 total 1.0 0.178169
1 2 1 1 1 total 1.0 0.262180
3 2 2 1 1 total 1.0 0.104797
mesh 1 group out nuclide mean std. dev.
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1 1 2 1 1 total 1.0 0.262180
2 2 1 1 1 total 1.0 0.178169
2 1 2 1 1 total 1.0 0.178169
1 2 1 1 1 total 1.0 0.262180
3 2 2 1 1 total 1.0 0.108931
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 7.097008e-07 1.458546e-07
1 1 2 1 1 total 3.984535e-07 1.157576e-07
2 2 1 1 1 total 4.407745e-07 7.903907e-08
2 1 2 1 1 total 4.407745e-07 7.903907e-08
1 2 1 1 1 total 3.984535e-07 1.157576e-07
3 2 2 1 1 total 4.750476e-07 6.207437e-08
mesh 1 group in nuclide mean std. dev.
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1 1 2 1 1 total 0.017783 0.004394
2 2 1 1 1 total 0.017820 0.003054
2 1 2 1 1 total 0.017820 0.003054
1 2 1 1 1 total 0.017783 0.004394
3 2 2 1 1 total 0.020320 0.002598
mesh 1 group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 0.015584 0.003404
1 1 2 1 1 1 total 0.014200 0.003676
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2 1 2 1 1 1 total 0.017684 0.002499
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3 2 2 1 1 1 total 0.022259 0.002508
mesh 1 delayedgroup group in nuclide mean std. dev.
x y z
@ -186,18 +186,18 @@
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4 1 1 1 5 1 total 0.000031 7.654909e-06
5 1 1 1 6 1 total 0.000013 3.206343e-06
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8 1 2 1 3 1 total 0.000021 5.324236e-06
9 1 2 1 4 1 total 0.000050 1.251572e-05
10 1 2 1 5 1 total 0.000022 5.762184e-06
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12 2 1 1 1 1 total 0.000004 6.723192e-07
13 2 1 1 2 1 total 0.000022 3.706235e-06
14 2 1 1 3 1 total 0.000022 3.674263e-06
15 2 1 1 4 1 total 0.000052 8.774048e-06
16 2 1 1 5 1 total 0.000024 4.168024e-06
17 2 1 1 6 1 total 0.000010 1.726268e-06
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15 1 2 1 4 1 total 0.000052 8.774048e-06
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17 1 2 1 6 1 total 0.000010 1.726268e-06
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9 2 1 1 4 1 total 0.000050 1.251572e-05
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11 2 1 1 6 1 total 0.000009 2.391676e-06
18 2 2 1 1 1 total 0.000005 5.962367e-07
19 2 2 1 2 1 total 0.000025 3.200900e-06
20 2 2 1 3 1 total 0.000025 3.127442e-06
@ -212,18 +212,18 @@
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@ -290,18 +290,18 @@
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View file

@ -28,40 +28,40 @@
material group in nuclide mean std. dev.
1 1 1 total 0.385188 0.026946
0 1 2 total 0.412389 0.015425
material group in group out nuclide moment mean std. dev.
12 1 1 1 total P0 0.384199 0.027001
13 1 1 1 total P1 0.051870 0.006983
14 1 1 1 total P2 0.020069 0.002846
15 1 1 1 total P3 0.009478 0.002234
8 1 1 2 total P0 0.000989 0.000482
9 1 1 2 total P1 -0.000207 0.000149
10 1 1 2 total P2 -0.000103 0.000184
11 1 1 2 total P3 0.000234 0.000128
4 1 2 1 total P0 0.000925 0.000925
5 1 2 1 total P1 -0.000768 0.000768
6 1 2 1 total P2 0.000494 0.000494
7 1 2 1 total P3 -0.000171 0.000172
0 1 2 2 total P0 0.411465 0.015245
1 1 2 2 total P1 0.016482 0.004502
2 1 2 2 total P2 0.006371 0.010551
3 1 2 2 total P3 -0.010499 0.010438
material group in group out nuclide moment mean std. dev.
12 1 1 1 total P0 0.384199 0.027001
13 1 1 1 total P1 0.051870 0.006983
14 1 1 1 total P2 0.020069 0.002846
15 1 1 1 total P3 0.009478 0.002234
8 1 1 2 total P0 0.000989 0.000482
9 1 1 2 total P1 -0.000207 0.000149
10 1 1 2 total P2 -0.000103 0.000184
11 1 1 2 total P3 0.000234 0.000128
4 1 2 1 total P0 0.000925 0.000925
5 1 2 1 total P1 -0.000768 0.000768
6 1 2 1 total P2 0.000494 0.000494
7 1 2 1 total P3 -0.000171 0.000172
0 1 2 2 total P0 0.411465 0.015245
1 1 2 2 total P1 0.016482 0.004502
2 1 2 2 total P2 0.006371 0.010551
3 1 2 2 total P3 -0.010499 0.010438
material group in group out legendre nuclide mean std. dev.
12 1 1 1 P0 total 0.384199 0.027001
13 1 1 1 P1 total 0.051870 0.006983
14 1 1 1 P2 total 0.020069 0.002846
15 1 1 1 P3 total 0.009478 0.002234
8 1 1 2 P0 total 0.000989 0.000482
9 1 1 2 P1 total -0.000207 0.000149
10 1 1 2 P2 total -0.000103 0.000184
11 1 1 2 P3 total 0.000234 0.000128
4 1 2 1 P0 total 0.000925 0.000925
5 1 2 1 P1 total -0.000768 0.000768
6 1 2 1 P2 total 0.000494 0.000494
7 1 2 1 P3 total -0.000171 0.000172
0 1 2 2 P0 total 0.411465 0.015245
1 1 2 2 P1 total 0.016482 0.004502
2 1 2 2 P2 total 0.006371 0.010551
3 1 2 2 P3 total -0.010499 0.010438
material group in group out legendre nuclide mean std. dev.
12 1 1 1 P0 total 0.384199 0.027001
13 1 1 1 P1 total 0.051870 0.006983
14 1 1 1 P2 total 0.020069 0.002846
15 1 1 1 P3 total 0.009478 0.002234
8 1 1 2 P0 total 0.000989 0.000482
9 1 1 2 P1 total -0.000207 0.000149
10 1 1 2 P2 total -0.000103 0.000184
11 1 1 2 P3 total 0.000234 0.000128
4 1 2 1 P0 total 0.000925 0.000925
5 1 2 1 P1 total -0.000768 0.000768
6 1 2 1 P2 total 0.000494 0.000494
7 1 2 1 P3 total -0.000171 0.000172
0 1 2 2 P0 total 0.411465 0.015245
1 1 2 2 P1 total 0.016482 0.004502
2 1 2 2 P2 total 0.006371 0.010551
3 1 2 2 P3 total -0.010499 0.010438
material group in group out nuclide mean std. dev.
3 1 1 1 total 1.0 0.078516
2 1 1 2 total 1.0 0.687184
@ -77,40 +77,40 @@
2 1 1 2 total 0.002567 0.001256
1 1 2 1 total 0.002242 0.002243
0 1 2 2 total 0.997758 0.041053
material group in group out nuclide moment mean std. dev.
12 1 1 1 total P0 0.386423 0.036629
13 1 1 1 total P1 0.052170 0.007767
14 1 1 1 total P2 0.020185 0.003138
15 1 1 1 total P3 0.009533 0.002327
8 1 1 2 total P0 0.000995 0.000489
9 1 1 2 total P1 -0.000208 0.000150
10 1 1 2 total P2 -0.000104 0.000186
11 1 1 2 total P3 0.000236 0.000130
4 1 2 1 total P0 0.000887 0.000889
5 1 2 1 total P1 -0.000737 0.000738
6 1 2 1 total P2 0.000474 0.000475
7 1 2 1 total P3 -0.000165 0.000165
0 1 2 2 total P0 0.394772 0.029871
1 1 2 2 total P1 0.015813 0.004443
2 1 2 2 total P2 0.006113 0.010131
3 1 2 2 total P3 -0.010073 0.010037
material group in group out nuclide moment mean std. dev.
12 1 1 1 total P0 0.386423 0.047563
13 1 1 1 total P1 0.052170 0.008781
14 1 1 1 total P2 0.020185 0.003515
15 1 1 1 total P3 0.009533 0.002444
8 1 1 2 total P0 0.000995 0.000841
9 1 1 2 total P1 -0.000208 0.000208
10 1 1 2 total P2 -0.000104 0.000199
11 1 1 2 total P3 0.000236 0.000208
4 1 2 1 total P0 0.000887 0.001538
5 1 2 1 total P1 -0.000737 0.001277
6 1 2 1 total P2 0.000474 0.000821
7 1 2 1 total P3 -0.000165 0.000285
0 1 2 2 total P0 0.394772 0.033999
1 1 2 2 total P1 0.015813 0.004491
2 1 2 2 total P2 0.006113 0.010134
3 1 2 2 total P3 -0.010073 0.010045
material group in group out legendre nuclide mean std. dev.
12 1 1 1 P0 total 0.386423 0.036629
13 1 1 1 P1 total 0.052170 0.007767
14 1 1 1 P2 total 0.020185 0.003138
15 1 1 1 P3 total 0.009533 0.002327
8 1 1 2 P0 total 0.000995 0.000489
9 1 1 2 P1 total -0.000208 0.000150
10 1 1 2 P2 total -0.000104 0.000186
11 1 1 2 P3 total 0.000236 0.000130
4 1 2 1 P0 total 0.000887 0.000889
5 1 2 1 P1 total -0.000737 0.000738
6 1 2 1 P2 total 0.000474 0.000475
7 1 2 1 P3 total -0.000165 0.000165
0 1 2 2 P0 total 0.394772 0.029871
1 1 2 2 P1 total 0.015813 0.004443
2 1 2 2 P2 total 0.006113 0.010131
3 1 2 2 P3 total -0.010073 0.010037
material group in group out legendre nuclide mean std. dev.
12 1 1 1 P0 total 0.386423 0.047563
13 1 1 1 P1 total 0.052170 0.008781
14 1 1 1 P2 total 0.020185 0.003515
15 1 1 1 P3 total 0.009533 0.002444
8 1 1 2 P0 total 0.000995 0.000841
9 1 1 2 P1 total -0.000208 0.000208
10 1 1 2 P2 total -0.000104 0.000199
11 1 1 2 P3 total 0.000236 0.000208
4 1 2 1 P0 total 0.000887 0.001538
5 1 2 1 P1 total -0.000737 0.001277
6 1 2 1 P2 total 0.000474 0.000821
7 1 2 1 P3 total -0.000165 0.000285
0 1 2 2 P0 total 0.394772 0.033999
1 1 2 2 P1 total 0.015813 0.004491
2 1 2 2 P2 total 0.006113 0.010134
3 1 2 2 P3 total -0.010073 0.010045
material group out nuclide mean std. dev.
1 1 1 total 1.0 0.046071
0 1 2 total 0.0 0.000000
@ -235,40 +235,40 @@
material group in nuclide mean std. dev.
1 2 1 total 0.310121 0.033788
0 2 2 total 0.296264 0.043792
material group in group out nuclide moment mean std. dev.
12 2 1 1 total P0 0.310121 0.033788
13 2 1 1 total P1 0.038230 0.008484
14 2 1 1 total P2 0.020745 0.004696
15 2 1 1 total P3 0.007964 0.003732
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 0.296264 0.043792
1 2 2 2 total P1 -0.011214 0.016180
2 2 2 2 total P2 0.008837 0.011504
3 2 2 2 total P3 -0.003270 0.007329
material group in group out nuclide moment mean std. dev.
12 2 1 1 total P0 0.310121 0.033788
13 2 1 1 total P1 0.038230 0.008484
14 2 1 1 total P2 0.020745 0.004696
15 2 1 1 total P3 0.007964 0.003732
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 0.296264 0.043792
1 2 2 2 total P1 -0.011214 0.016180
2 2 2 2 total P2 0.008837 0.011504
3 2 2 2 total P3 -0.003270 0.007329
material group in group out legendre nuclide mean std. dev.
12 2 1 1 P0 total 0.310121 0.033788
13 2 1 1 P1 total 0.038230 0.008484
14 2 1 1 P2 total 0.020745 0.004696
15 2 1 1 P3 total 0.007964 0.003732
8 2 1 2 P0 total 0.000000 0.000000
9 2 1 2 P1 total 0.000000 0.000000
10 2 1 2 P2 total 0.000000 0.000000
11 2 1 2 P3 total 0.000000 0.000000
4 2 2 1 P0 total 0.000000 0.000000
5 2 2 1 P1 total 0.000000 0.000000
6 2 2 1 P2 total 0.000000 0.000000
7 2 2 1 P3 total 0.000000 0.000000
0 2 2 2 P0 total 0.296264 0.043792
1 2 2 2 P1 total -0.011214 0.016180
2 2 2 2 P2 total 0.008837 0.011504
3 2 2 2 P3 total -0.003270 0.007329
material group in group out legendre nuclide mean std. dev.
12 2 1 1 P0 total 0.310121 0.033788
13 2 1 1 P1 total 0.038230 0.008484
14 2 1 1 P2 total 0.020745 0.004696
15 2 1 1 P3 total 0.007964 0.003732
8 2 1 2 P0 total 0.000000 0.000000
9 2 1 2 P1 total 0.000000 0.000000
10 2 1 2 P2 total 0.000000 0.000000
11 2 1 2 P3 total 0.000000 0.000000
4 2 2 1 P0 total 0.000000 0.000000
5 2 2 1 P1 total 0.000000 0.000000
6 2 2 1 P2 total 0.000000 0.000000
7 2 2 1 P3 total 0.000000 0.000000
0 2 2 2 P0 total 0.296264 0.043792
1 2 2 2 P1 total -0.011214 0.016180
2 2 2 2 P2 total 0.008837 0.011504
3 2 2 2 P3 total -0.003270 0.007329
material group in group out nuclide mean std. dev.
3 2 1 1 total 1.0 0.108779
2 2 1 2 total 0.0 0.000000
@ -284,40 +284,40 @@
2 2 1 2 total 0.0 0.000000
1 2 2 1 total 0.0 0.000000
0 2 2 2 total 1.0 0.142427
material group in group out nuclide moment mean std. dev.
12 2 1 1 total P0 0.312163 0.037253
13 2 1 1 total P1 0.038481 0.008743
14 2 1 1 total P2 0.020882 0.004835
15 2 1 1 total P3 0.008017 0.003776
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 0.295421 0.050236
1 2 2 2 total P1 -0.011182 0.016162
2 2 2 2 total P2 0.008811 0.011495
3 2 2 2 total P3 -0.003261 0.007313
material group in group out nuclide moment mean std. dev.
12 2 1 1 total P0 0.312163 0.050407
13 2 1 1 total P1 0.038481 0.009693
14 2 1 1 total P2 0.020882 0.005342
15 2 1 1 total P3 0.008017 0.003876
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 0.295421 0.065529
1 2 2 2 total P1 -0.011182 0.016240
2 2 2 2 total P2 0.008811 0.011563
3 2 2 2 total P3 -0.003261 0.007328
material group in group out legendre nuclide mean std. dev.
12 2 1 1 P0 total 0.312163 0.037253
13 2 1 1 P1 total 0.038481 0.008743
14 2 1 1 P2 total 0.020882 0.004835
15 2 1 1 P3 total 0.008017 0.003776
8 2 1 2 P0 total 0.000000 0.000000
9 2 1 2 P1 total 0.000000 0.000000
10 2 1 2 P2 total 0.000000 0.000000
11 2 1 2 P3 total 0.000000 0.000000
4 2 2 1 P0 total 0.000000 0.000000
5 2 2 1 P1 total 0.000000 0.000000
6 2 2 1 P2 total 0.000000 0.000000
7 2 2 1 P3 total 0.000000 0.000000
0 2 2 2 P0 total 0.295421 0.050236
1 2 2 2 P1 total -0.011182 0.016162
2 2 2 2 P2 total 0.008811 0.011495
3 2 2 2 P3 total -0.003261 0.007313
material group in group out legendre nuclide mean std. dev.
12 2 1 1 P0 total 0.312163 0.050407
13 2 1 1 P1 total 0.038481 0.009693
14 2 1 1 P2 total 0.020882 0.005342
15 2 1 1 P3 total 0.008017 0.003876
8 2 1 2 P0 total 0.000000 0.000000
9 2 1 2 P1 total 0.000000 0.000000
10 2 1 2 P2 total 0.000000 0.000000
11 2 1 2 P3 total 0.000000 0.000000
4 2 2 1 P0 total 0.000000 0.000000
5 2 2 1 P1 total 0.000000 0.000000
6 2 2 1 P2 total 0.000000 0.000000
7 2 2 1 P3 total 0.000000 0.000000
0 2 2 2 P0 total 0.295421 0.065529
1 2 2 2 P1 total -0.011182 0.016240
2 2 2 2 P2 total 0.008811 0.011563
3 2 2 2 P3 total -0.003261 0.007328
material group out nuclide mean std. dev.
1 2 1 total 0.0 0.0
0 2 2 total 0.0 0.0
@ -442,40 +442,40 @@
material group in nuclide mean std. dev.
1 3 1 total 0.671269 0.026186
0 3 2 total 2.035388 0.258060
material group in group out nuclide moment mean std. dev.
12 3 1 1 total P0 0.639901 0.024709
13 3 1 1 total P1 0.381167 0.016243
14 3 1 1 total P2 0.152392 0.008156
15 3 1 1 total P3 0.009148 0.003889
8 3 1 2 total P0 0.031368 0.001728
9 3 1 2 total P1 0.008758 0.000926
10 3 1 2 total P2 -0.002568 0.001014
11 3 1 2 total P3 -0.003785 0.000817
4 3 2 1 total P0 0.000443 0.000445
5 3 2 1 total P1 0.000400 0.000401
6 3 2 1 total P2 0.000320 0.000321
7 3 2 1 total P3 0.000214 0.000215
0 3 2 2 total P0 2.034945 0.257800
1 3 2 2 total P1 0.509940 0.051236
2 3 2 2 total P2 0.111175 0.013020
3 3 2 2 total P3 0.024988 0.008312
material group in group out nuclide moment mean std. dev.
12 3 1 1 total P0 0.639901 0.024709
13 3 1 1 total P1 0.381167 0.016243
14 3 1 1 total P2 0.152392 0.008156
15 3 1 1 total P3 0.009148 0.003889
8 3 1 2 total P0 0.031368 0.001728
9 3 1 2 total P1 0.008758 0.000926
10 3 1 2 total P2 -0.002568 0.001014
11 3 1 2 total P3 -0.003785 0.000817
4 3 2 1 total P0 0.000443 0.000445
5 3 2 1 total P1 0.000400 0.000401
6 3 2 1 total P2 0.000320 0.000321
7 3 2 1 total P3 0.000214 0.000215
0 3 2 2 total P0 2.034945 0.257800
1 3 2 2 total P1 0.509940 0.051236
2 3 2 2 total P2 0.111175 0.013020
3 3 2 2 total P3 0.024988 0.008312
material group in group out legendre nuclide mean std. dev.
12 3 1 1 P0 total 0.639901 0.024709
13 3 1 1 P1 total 0.381167 0.016243
14 3 1 1 P2 total 0.152392 0.008156
15 3 1 1 P3 total 0.009148 0.003889
8 3 1 2 P0 total 0.031368 0.001728
9 3 1 2 P1 total 0.008758 0.000926
10 3 1 2 P2 total -0.002568 0.001014
11 3 1 2 P3 total -0.003785 0.000817
4 3 2 1 P0 total 0.000443 0.000445
5 3 2 1 P1 total 0.000400 0.000401
6 3 2 1 P2 total 0.000320 0.000321
7 3 2 1 P3 total 0.000214 0.000215
0 3 2 2 P0 total 2.034945 0.257800
1 3 2 2 P1 total 0.509940 0.051236
2 3 2 2 P2 total 0.111175 0.013020
3 3 2 2 P3 total 0.024988 0.008312
material group in group out legendre nuclide mean std. dev.
12 3 1 1 P0 total 0.639901 0.024709
13 3 1 1 P1 total 0.381167 0.016243
14 3 1 1 P2 total 0.152392 0.008156
15 3 1 1 P3 total 0.009148 0.003889
8 3 1 2 P0 total 0.031368 0.001728
9 3 1 2 P1 total 0.008758 0.000926
10 3 1 2 P2 total -0.002568 0.001014
11 3 1 2 P3 total -0.003785 0.000817
4 3 2 1 P0 total 0.000443 0.000445
5 3 2 1 P1 total 0.000400 0.000401
6 3 2 1 P2 total 0.000320 0.000321
7 3 2 1 P3 total 0.000214 0.000215
0 3 2 2 P0 total 2.034945 0.257800
1 3 2 2 P1 total 0.509940 0.051236
2 3 2 2 P2 total 0.111175 0.013020
3 3 2 2 P3 total 0.024988 0.008312
material group in group out nuclide mean std. dev.
3 3 1 1 total 1.0 0.038609
2 3 1 2 total 1.0 0.067667
@ -491,40 +491,40 @@
2 3 1 2 total 0.046729 0.002547
1 3 2 1 total 0.000218 0.000219
0 3 2 2 total 0.999782 0.135885
material group in group out nuclide moment mean std. dev.
12 3 1 1 total P0 0.632859 0.038142
13 3 1 1 total P1 0.376973 0.023715
14 3 1 1 total P2 0.150715 0.010664
15 3 1 1 total P3 0.009047 0.003868
8 3 1 2 total P0 0.031023 0.002232
9 3 1 2 total P1 0.008661 0.000999
10 3 1 2 total P2 -0.002540 0.001010
11 3 1 2 total P3 -0.003743 0.000826
4 3 2 1 total P0 0.000440 0.000445
5 3 2 1 total P1 0.000397 0.000401
6 3 2 1 total P2 0.000317 0.000321
7 3 2 1 total P3 0.000212 0.000215
0 3 2 2 total P0 2.020256 0.352194
1 3 2 2 total P1 0.506260 0.079140
2 3 2 2 total P2 0.110372 0.018488
3 3 2 2 total P3 0.024808 0.008771
material group in group out nuclide moment mean std. dev.
12 3 1 1 total P0 0.632859 0.045297
13 3 1 1 total P1 0.376973 0.027825
14 3 1 1 total P2 0.150715 0.012148
15 3 1 1 total P3 0.009047 0.003884
8 3 1 2 total P0 0.031023 0.003064
9 3 1 2 total P1 0.008661 0.001159
10 3 1 2 total P2 -0.002540 0.001024
11 3 1 2 total P3 -0.003743 0.000864
4 3 2 1 total P0 0.000440 0.000765
5 3 2 1 total P1 0.000397 0.000690
6 3 2 1 total P2 0.000317 0.000551
7 3 2 1 total P3 0.000212 0.000369
0 3 2 2 total P0 2.020256 0.446601
1 3 2 2 total P1 0.506260 0.104875
2 3 2 2 total P2 0.110372 0.023809
3 3 2 2 total P3 0.024808 0.009397
material group in group out legendre nuclide mean std. dev.
12 3 1 1 P0 total 0.632859 0.038142
13 3 1 1 P1 total 0.376973 0.023715
14 3 1 1 P2 total 0.150715 0.010664
15 3 1 1 P3 total 0.009047 0.003868
8 3 1 2 P0 total 0.031023 0.002232
9 3 1 2 P1 total 0.008661 0.000999
10 3 1 2 P2 total -0.002540 0.001010
11 3 1 2 P3 total -0.003743 0.000826
4 3 2 1 P0 total 0.000440 0.000445
5 3 2 1 P1 total 0.000397 0.000401
6 3 2 1 P2 total 0.000317 0.000321
7 3 2 1 P3 total 0.000212 0.000215
0 3 2 2 P0 total 2.020256 0.352194
1 3 2 2 P1 total 0.506260 0.079140
2 3 2 2 P2 total 0.110372 0.018488
3 3 2 2 P3 total 0.024808 0.008771
material group in group out legendre nuclide mean std. dev.
12 3 1 1 P0 total 0.632859 0.045297
13 3 1 1 P1 total 0.376973 0.027825
14 3 1 1 P2 total 0.150715 0.012148
15 3 1 1 P3 total 0.009047 0.003884
8 3 1 2 P0 total 0.031023 0.003064
9 3 1 2 P1 total 0.008661 0.001159
10 3 1 2 P2 total -0.002540 0.001024
11 3 1 2 P3 total -0.003743 0.000864
4 3 2 1 P0 total 0.000440 0.000765
5 3 2 1 P1 total 0.000397 0.000690
6 3 2 1 P2 total 0.000317 0.000551
7 3 2 1 P3 total 0.000212 0.000369
0 3 2 2 P0 total 2.020256 0.446601
1 3 2 2 P1 total 0.506260 0.104875
2 3 2 2 P2 total 0.110372 0.023809
3 3 2 2 P3 total 0.024808 0.009397
material group out nuclide mean std. dev.
1 3 1 total 0.0 0.0
0 3 2 total 0.0 0.0

File diff suppressed because it is too large Load diff

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@ -1 +1 @@
174d1593a15de41e2aba88cc4c48fc3a400314b400571a0328dfdf7482df111b3ac9701dbd196d06668b49d3acaa67d766702db0942c03140e9e004942f7bdfd
0edd3036c0b5b1eebad90dc8fba25006f14745ceb51dd109e70d0c610d66071f32128facdbc6d4e5077534fe96fff9a8e0ddeefb4a18d6c578f8e805bab7aa22

View file

@ -1,7 +1,7 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" universe="1" />
<cell id="11" material="2" region="-1" temperature="500 0 700 800" universe="11" />
<cell id="11" material="2" region="-1" temperature="500 700 0 800" universe="11" />
<cell id="12" material="1" region="1" universe="11" />
<cell fill="101" id="101" region="2 -3 4 -5" universe="0" />
<lattice id="101">
@ -27,7 +27,7 @@
<nuclide ao="1.0" name="O16" />
<sab name="c_H_in_H2O" />
</material>
<material id="2">
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>

View file

@ -37,5 +37,5 @@ Cell
Fill = Material 2
Region = -1
Rotation = None
Temperature = [ 500. 0. 700. 800.]
Temperature = [ 500. 700. 0. 800.]
Translation = None

View file

@ -29,7 +29,7 @@ def make_model():
r0 = openmc.ZCylinder(R=0.3)
c11 = openmc.Cell(cell_id=11, fill=dense_fuel, region=-r0)
c11.temperature = [500, 0, 700, 800]
c11.temperature = [500, 700, 0, 800]
c12 = openmc.Cell(cell_id=12, fill=moderator, region=+r0)
fuel_univ = openmc.Universe(universe_id=11, cells=(c11, c12))

View file

@ -18,7 +18,7 @@
<nuclide ao="1.0" name="O16" />
<sab name="c_H_in_H2O" />
</material>
<material id="2">
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>

View file

@ -5,7 +5,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1">
<material depletable="true" id="1">
<density units="g/cc" value="1.0" />
<nuclide ao="1.0" name="U238" />
<nuclide ao="0.02" name="U235" />

View file

@ -12,19 +12,19 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1">
<material depletable="true" id="1">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
<nuclide ao="1.0" name="H1" />
<sab fraction="0.5" name="c_H_in_H2O" />
</material>
<material id="2">
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
<nuclide ao="1.0" name="C0" />
<sab name="c_Graphite" />
</material>
<material id="3">
<material depletable="true" id="3">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
<nuclide ao="1.0" name="Be9" />
@ -32,7 +32,7 @@
<sab name="c_Be_in_BeO" />
<sab name="c_O_in_BeO" />
</material>
<material id="4">
<material depletable="true" id="4">
<density units="g/cm3" value="5.90168" />
<nuclide ao="0.3" name="H1" />
<nuclide ao="0.15" name="Zr90" />

View file

@ -1 +1 @@
4675d5101f4f829369c39cb33d654430836b934ab07c165777ba6e214bdf3a698b8082f4f9bb9e78f1f0e495b30ea02cf9b3d14622c59915d818d678a1e5b7b1
138b312cdaa822c9b62f757b3259522004b679c4ed289a92798b29a6442c26d12c53256635be273f13e3703816ff50a1b9f52d79770eade01e482384ac0d389f

View file

@ -9,7 +9,7 @@
</mesh>
<filter id="1">
<type>mesh</type>
<type>meshsurface</type>
<bins>1</bins>
</filter>

View file

@ -5,7 +5,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1">
<material depletable="true" id="1">
<temperature>294</temperature>
<density units="g/cm3" value="4.5" />
<nuclide ao="1.0" name="U235" />

File diff suppressed because it is too large Load diff

View file

@ -30,7 +30,7 @@
<tally id="10">
<filters>1 2 3</filters>
<scores>scatter-P3 nu-fission</scores>
<scores>scatter nu-fission</scores>
</tally>
<tally id="5">

File diff suppressed because it is too large Load diff

View file

@ -30,7 +30,7 @@
<tally id="10">
<filters>1 2 3</filters>
<scores>scatter-P3 nu-fission</scores>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
<tally id="5">

View file

@ -11,7 +11,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="13" name="UO2 fuel at 2.4% wt enrichment">
<material depletable="true" id="13" name="UO2 fuel at 2.4% wt enrichment">
<density units="g/cc" value="10.0" />
<nuclide ao="1.0" name="U238" />
<nuclide ao="0.02" name="U235" />

View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
@ -341,13 +341,19 @@
<filter id="9" type="polar">
<bins>0.0 0.6283 1.2566 1.885 2.5132 3.14159</bins>
</filter>
<filter id="10" type="universe">
<filter id="10" type="legendre">
<order>4</order>
</filter>
<filter cosine="particle" id="11" type="sphericalharmonics">
<order>4</order>
</filter>
<filter id="12" type="universe">
<bins>1 2 3 4 6 8</bins>
</filter>
<filter id="11" type="cell">
<filter id="13" type="cell">
<bins>10 21 22 23 60</bins>
</filter>
<filter id="12" type="cell">
<filter id="14" type="cell">
<bins>21 22 23 27 28 29 60</bins>
</filter>
<tally id="1">
@ -414,80 +420,80 @@
</tally>
<tally id="15">
<filters>10</filters>
<scores>total</scores>
<scores>scatter nu-scatter</scores>
</tally>
<tally id="16">
<filters>11</filters>
<scores>absorption delayed-nu-fission events fission inverse-velocity kappa-fission (n,2n) (n,n1) (n,gamma) nu-fission scatter elastic total prompt-nu-fission fission-q-prompt fission-q-recoverable</scores>
<estimator>tracklength</estimator>
<scores>scatter nu-scatter flux total</scores>
</tally>
<tally id="17">
<filters>11</filters>
<scores>absorption delayed-nu-fission events fission inverse-velocity kappa-fission (n,2n) (n,n1) (n,gamma) nu-fission scatter elastic total prompt-nu-fission fission-q-prompt fission-q-recoverable</scores>
<estimator>analog</estimator>
<scores>flux total</scores>
</tally>
<tally id="18">
<filters>11</filters>
<scores>absorption delayed-nu-fission events fission inverse-velocity kappa-fission (n,2n) (n,n1) (n,gamma) nu-fission scatter elastic total prompt-nu-fission fission-q-prompt fission-q-recoverable</scores>
<estimator>collision</estimator>
<scores>flux total</scores>
</tally>
<tally id="19">
<filters>12</filters>
<scores>flux</scores>
<scores>total</scores>
</tally>
<tally id="20">
<filters>12</filters>
<scores>flux-y5</scores>
<filters>13</filters>
<scores>absorption delayed-nu-fission events fission inverse-velocity kappa-fission (n,2n) (n,n1) (n,gamma) nu-fission scatter elastic total prompt-nu-fission fission-q-prompt fission-q-recoverable</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="21">
<filters>12</filters>
<scores>flux-y5</scores>
<filters>13</filters>
<scores>absorption delayed-nu-fission events fission inverse-velocity kappa-fission (n,2n) (n,n1) (n,gamma) nu-fission scatter elastic total prompt-nu-fission fission-q-prompt fission-q-recoverable</scores>
<estimator>analog</estimator>
</tally>
<tally id="22">
<filters>12</filters>
<scores>flux-y5</scores>
<filters>13</filters>
<scores>absorption delayed-nu-fission events fission inverse-velocity kappa-fission (n,2n) (n,n1) (n,gamma) nu-fission scatter elastic total prompt-nu-fission fission-q-prompt fission-q-recoverable</scores>
<estimator>collision</estimator>
</tally>
<tally id="23">
<filters>11</filters>
<scores>scatter scatter-1 scatter-2 scatter-3 scatter-4 nu-scatter nu-scatter-1 nu-scatter-2 nu-scatter-3 nu-scatter-4</scores>
<filters>14</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="24">
<filters>11</filters>
<scores>scatter-p4 scatter-y4 nu-scatter-p4 nu-scatter-y3</scores>
<filters>14</filters>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="25">
<filters>11</filters>
<scores>total</scores>
<filters>14</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="26">
<filters>11</filters>
<filters>13</filters>
<nuclides>U235 total</nuclides>
<scores>total-y4</scores>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="27">
<filters>11</filters>
<filters>13</filters>
<nuclides>U235 total</nuclides>
<scores>total-y4</scores>
<scores>total</scores>
<estimator>analog</estimator>
</tally>
<tally id="28">
<filters>11</filters>
<filters>13</filters>
<nuclides>U235 total</nuclides>
<scores>total-y4</scores>
<scores>total</scores>
<estimator>collision</estimator>
</tally>
<tally id="29">
<filters>11</filters>
<filters>13</filters>
<nuclides>all</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="30">
<filters>11</filters>
<filters>13</filters>
<nuclides>all</nuclides>
<scores>total</scores>
<estimator>collision</estimator>

View file

@ -1 +1 @@
13014f42dea87bf6c1fc0d41361cdba8a7e32a8f809d348567dfce638c849f58a0c0f17065c199946db81a264ef72db850aea93b0e11adf4f70ec969e30529cd
8cf1936c565c6a09bffe2f7a0623ded1405bae37c1de8159551e64b86ca4f6bce82890a630b9428bcf8353f6de8e5cfc1f1a4263fd51a1c6b5cddb0a9c2ff368

View file

@ -1,5 +1,6 @@
from openmc.filter import *
from openmc import Mesh, Tally, Tallies
from openmc.filter_expansion import *
from openmc import Mesh, Tally
from tests.testing_harness import HashedPyAPITestHarness
@ -28,8 +29,8 @@ def test_tallies():
azimuthal_tally2.estimator = 'analog'
mesh_2x2 = Mesh(mesh_id=1)
mesh_2x2.lower_left = [-182.07, -182.07]
mesh_2x2.upper_right = [182.07, 182.07]
mesh_2x2.lower_left = [-182.07, -182.07]
mesh_2x2.upper_right = [182.07, 182.07]
mesh_2x2.dimension = [2, 2]
mesh_filter = MeshFilter(mesh_2x2)
azimuthal_tally3 = Tally()
@ -97,6 +98,28 @@ def test_tallies():
polar_tally3.scores = ['flux']
polar_tally3.estimator = 'tracklength'
legendre_filter = LegendreFilter(order=4)
legendre_tally = Tally()
legendre_tally.filters = [legendre_filter]
legendre_tally.scores = ['scatter', 'nu-scatter']
legendre_tally.estimatir = 'analog'
harmonics_filter = SphericalHarmonicsFilter(order=4)
harmonics_tally = Tally()
harmonics_tally.filters = [harmonics_filter]
harmonics_tally.scores = ['scatter', 'nu-scatter', 'flux', 'total']
harmonics_tally.estimatir = 'analog'
harmonics_tally2 = Tally()
harmonics_tally2.filters = [harmonics_filter]
harmonics_tally2.scores = ['flux', 'total']
harmonics_tally2.estimatir = 'collision'
harmonics_tally3 = Tally()
harmonics_tally3.filters = [harmonics_filter]
harmonics_tally3.scores = ['flux', 'total']
harmonics_tally3.estimatir = 'tracklength'
universe_tally = Tally()
universe_tally.filters = [
UniverseFilter((model.geometry.get_all_universes()[1],
@ -120,37 +143,22 @@ def test_tallies():
score_tallies[2].estimator = 'collision'
cell_filter2 = CellFilter((21, 22, 23, 27, 28, 29, 60))
flux_tallies = [Tally() for i in range(4)]
flux_tallies = [Tally() for i in range(3)]
for t in flux_tallies:
t.filters = [cell_filter2]
flux_tallies[0].scores = ['flux']
for t in flux_tallies[1:]:
t.scores = ['flux-y5']
flux_tallies[1].estimator = 'tracklength'
flux_tallies[2].estimator = 'analog'
flux_tallies[3].estimator = 'collision'
t.scores = ['flux']
flux_tallies[0].estimator = 'tracklength'
flux_tallies[1].estimator = 'analog'
flux_tallies[2].estimator = 'collision'
scatter_tally1 = Tally()
scatter_tally1.filters = [cell_filter]
scatter_tally1.scores = ['scatter', 'scatter-1', 'scatter-2', 'scatter-3',
'scatter-4', 'nu-scatter', 'nu-scatter-1',
'nu-scatter-2', 'nu-scatter-3', 'nu-scatter-4']
scatter_tally2 = Tally()
scatter_tally2.filters = [cell_filter]
scatter_tally2.scores = ['scatter-p4', 'scatter-y4', 'nu-scatter-p4',
'nu-scatter-y3']
total_tallies = [Tally() for i in range(4)]
total_tallies = [Tally() for i in range(3)]
for t in total_tallies:
t.filters = [cell_filter]
total_tallies[0].scores = ['total']
for t in total_tallies[1:]:
t.scores = ['total-y4']
t.scores = ['total']
t.nuclides = ['U235', 'total']
total_tallies[1].estimator = 'tracklength'
total_tallies[2].estimator = 'analog'
total_tallies[3].estimator = 'collision'
total_tallies[0].estimator = 'tracklength'
total_tallies[1].estimator = 'analog'
total_tallies[2].estimator = 'collision'
all_nuclide_tallies = [Tally() for i in range(4)]
for t in all_nuclide_tallies:
@ -167,10 +175,10 @@ def test_tallies():
azimuthal_tally1, azimuthal_tally2, azimuthal_tally3,
cellborn_tally, dg_tally, energy_tally, energyout_tally,
transfer_tally, material_tally, mu_tally1, mu_tally2,
polar_tally1, polar_tally2, polar_tally3, universe_tally]
polar_tally1, polar_tally2, polar_tally3, legendre_tally,
harmonics_tally, harmonics_tally2, harmonics_tally3, universe_tally]
model.tallies += score_tallies
model.tallies += flux_tallies
model.tallies += (scatter_tally1, scatter_tally2)
model.tallies += total_tallies
model.tallies += all_nuclide_tallies

View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />

View file

@ -1 +1 @@
eb2002dd2f3016154e7014501629227eb2e5b2a9655b5c0cb3b9d4d681f918fae4197bf4756fe9865c8d34f392b981b287a15e9b2fab5a46b2a5b8a33a8ae770
8294c7481b3433a4beb25541ae72c1ea915def0c0d0f393f7585371877187f4a2a25e70bb602232e2bc1e877e78db0e9384591e5c71575659f95abb10fae0af3

View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />

View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />

View file

@ -48,20 +48,20 @@
13 (500, 5000, 50000) 6.25e-01 2.00e+07 U235 nu-fission 0.00e+00 0.00e+00
14 (500, 5000, 50000) 6.25e-01 2.00e+07 U238 fission 0.00e+00 0.00e+00
15 (500, 5000, 50000) 6.25e-01 2.00e+07 U238 nu-fission 0.00e+00 0.00e+00
sum(mesh) energy low [eV] energy high [eV] nuclide score mean std. dev.
0 ((1, 1, 1), (1, 2, 1)) 0.00e+00 6.25e-01 U235 fission 1.48e-02 3.65e-03
1 ((1, 1, 1), (1, 2, 1)) 0.00e+00 6.25e-01 U235 nu-fission 3.60e-02 8.90e-03
2 ((1, 1, 1), (1, 2, 1)) 0.00e+00 6.25e-01 U238 fission 2.06e-08 4.98e-09
3 ((1, 1, 1), (1, 2, 1)) 0.00e+00 6.25e-01 U238 nu-fission 5.14e-08 1.24e-08
4 ((1, 1, 1), (1, 2, 1)) 6.25e-01 2.00e+07 U235 fission 2.23e-03 3.92e-04
5 ((1, 1, 1), (1, 2, 1)) 6.25e-01 2.00e+07 U235 nu-fission 5.45e-03 9.56e-04
6 ((1, 1, 1), (1, 2, 1)) 6.25e-01 2.00e+07 U238 fission 5.58e-04 2.08e-04
7 ((1, 1, 1), (1, 2, 1)) 6.25e-01 2.00e+07 U238 nu-fission 1.50e-03 5.43e-04
8 ((2, 1, 1), (2, 2, 1)) 0.00e+00 6.25e-01 U235 fission 2.56e-02 5.50e-03
9 ((2, 1, 1), (2, 2, 1)) 0.00e+00 6.25e-01 U235 nu-fission 6.24e-02 1.34e-02
10 ((2, 1, 1), (2, 2, 1)) 0.00e+00 6.25e-01 U238 fission 3.55e-08 7.70e-09
11 ((2, 1, 1), (2, 2, 1)) 0.00e+00 6.25e-01 U238 nu-fission 8.85e-08 1.92e-08
12 ((2, 1, 1), (2, 2, 1)) 6.25e-01 2.00e+07 U235 fission 5.01e-03 1.38e-03
13 ((2, 1, 1), (2, 2, 1)) 6.25e-01 2.00e+07 U235 nu-fission 1.22e-02 3.37e-03
14 ((2, 1, 1), (2, 2, 1)) 6.25e-01 2.00e+07 U238 fission 2.40e-03 2.69e-04
15 ((2, 1, 1), (2, 2, 1)) 6.25e-01 2.00e+07 U238 nu-fission 6.60e-03 7.63e-04
sum(mesh) energy low [eV] energy high [eV] nuclide score mean std. dev.
0 ((1, 1), (1, 2)) 0.00e+00 6.25e-01 U235 fission 0.00e+00 0.00e+00
1 ((1, 1), (1, 2)) 0.00e+00 6.25e-01 U235 nu-fission 0.00e+00 0.00e+00
2 ((1, 1), (1, 2)) 0.00e+00 6.25e-01 U238 fission 0.00e+00 0.00e+00
3 ((1, 1), (1, 2)) 0.00e+00 6.25e-01 U238 nu-fission 0.00e+00 0.00e+00
4 ((1, 1), (1, 2)) 6.25e-01 2.00e+07 U235 fission 1.60e-04 1.60e-04
5 ((1, 1), (1, 2)) 6.25e-01 2.00e+07 U235 nu-fission 3.91e-04 3.91e-04
6 ((1, 1), (1, 2)) 6.25e-01 2.00e+07 U238 fission 5.12e-05 5.12e-05
7 ((1, 1), (1, 2)) 6.25e-01 2.00e+07 U238 nu-fission 1.36e-04 1.36e-04
8 ((2, 1), (2, 2)) 0.00e+00 6.25e-01 U235 fission 4.04e-02 6.60e-03
9 ((2, 1), (2, 2)) 0.00e+00 6.25e-01 U235 nu-fission 9.85e-02 1.61e-02
10 ((2, 1), (2, 2)) 0.00e+00 6.25e-01 U238 fission 5.61e-08 9.18e-09
11 ((2, 1), (2, 2)) 0.00e+00 6.25e-01 U238 nu-fission 1.40e-07 2.29e-08
12 ((2, 1), (2, 2)) 6.25e-01 2.00e+07 U235 fission 7.08e-03 1.43e-03
13 ((2, 1), (2, 2)) 6.25e-01 2.00e+07 U235 nu-fission 1.73e-02 3.48e-03
14 ((2, 1), (2, 2)) 6.25e-01 2.00e+07 U238 fission 2.91e-03 3.36e-04
15 ((2, 1), (2, 2)) 6.25e-01 2.00e+07 U238 nu-fission 7.96e-03 9.27e-04

View file

@ -87,12 +87,14 @@ class TallySliceMergeTestHarness(PyAPITestHarness):
# Slice the tallies by cell filter bins
cell_filter_prod = itertools.product(tallies, self.cell_filters)
tallies = map(lambda tf: tf[0].get_slice(filters=[type(tf[1])],
filter_bins=[tf[1].get_bin(0)]), cell_filter_prod)
filter_bins=[(tf[1].bins[0],)]),
cell_filter_prod)
# Slice the tallies by energy filter bins
energy_filter_prod = itertools.product(tallies, self.energy_filters)
tallies = map(lambda tf: tf[0].get_slice(filters=[type(tf[1])],
filter_bins=[(tf[1].get_bin(0),)]), energy_filter_prod)
filter_bins=[(tf[1].bins[0],)]),
energy_filter_prod)
# Slice the tallies by nuclide
nuclide_prod = itertools.product(tallies, self.nuclides)
@ -126,10 +128,10 @@ class TallySliceMergeTestHarness(PyAPITestHarness):
# Sum up a few subdomains from the distribcell tally
sum1 = distribcell_tally.summation(filter_type=openmc.DistribcellFilter,
filter_bins=[0,100,2000,30000])
filter_bins=[0, 100, 2000, 30000])
# Sum up a few subdomains from the distribcell tally
sum2 = distribcell_tally.summation(filter_type=openmc.DistribcellFilter,
filter_bins=[500,5000,50000])
filter_bins=[500, 5000, 50000])
# Merge the distribcell tally slices
merge_tally = sum1.merge(sum2)
@ -143,10 +145,10 @@ class TallySliceMergeTestHarness(PyAPITestHarness):
# Sum up a few subdomains from the mesh tally
sum1 = mesh_tally.summation(filter_type=openmc.MeshFilter,
filter_bins=[(1,1,1), (1,2,1)])
filter_bins=[(1, 1), (1, 2)])
# Sum up a few subdomains from the mesh tally
sum2 = mesh_tally.summation(filter_type=openmc.MeshFilter,
filter_bins=[(2,1,1), (2,2,1)])
filter_bins=[(2, 1), (2, 2)])
# Merge the mesh tally slices
merge_tally = sum1.merge(sum2)

View file

@ -22,6 +22,7 @@ def test_full(run_in_tmpdir):
This test runs a complete OpenMC simulation and tests the outputs.
It will take a while.
"""
n_rings = 2

View file

@ -19,7 +19,7 @@ class TrackTestHarness(TestHarness):
def _get_results(self):
"""Digest info in the statepoint and return as a string."""
# Run the track-to-vtk conversion script.
call(['../../scripts/openmc-track-to-vtk', '-o', 'poly'] +
call(['../../../scripts/openmc-track-to-vtk', '-o', 'poly'] +
glob.glob('track_1_1_*.h5'))
# Make sure the vtk file was created then return it's contents.

View file

@ -393,7 +393,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="13">
<material depletable="true" id="13">
<density units="g/cm3" value="10.5" />
<nuclide ao="0.14154" name="U235" />
<nuclide ao="0.85846" name="U238" />

View file

@ -18,7 +18,7 @@
<nuclide ao="0.0001" name="B10" />
<sab name="c_H_in_H2O" />
</material>
<material id="2">
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
<nuclide ao="0.1" name="Mo99" />

View file

@ -1,30 +1,30 @@
Volume calculation 0
Domain 1: 31.4693 +/- 0.0721 cm^3
Domain 2: 2.0933 +/- 0.0310 cm^3
Domain 3: 2.0486 +/- 0.0307 cm^3
Cell Nuclide Atoms Uncertainty
0 1 U235 3.481769e+23 7.979991e+20
1 1 Mo99 3.481769e+22 7.979991e+19
2 2 H1 1.399770e+23 2.072914e+21
3 2 O16 6.998852e+22 1.036457e+21
4 2 B10 6.998852e+18 1.036457e+17
5 3 H1 1.369920e+23 2.051689e+21
6 3 O16 6.849599e+22 1.025844e+21
7 3 B10 6.849599e+18 1.025844e+17
Domain 1: 31.47+/-0.07 cm^3
Domain 2: 2.093+/-0.031 cm^3
Domain 3: 2.049+/-0.031 cm^3
Cell Nuclide Atoms
0 1 U235 (3.482+/-0.008)e+23
1 1 Mo99 (3.482+/-0.008)e+22
2 2 H1 (1.400+/-0.021)e+23
3 2 O16 (7.00+/-0.10)e+22
4 2 B10 (7.00+/-0.10)e+18
5 3 H1 (1.370+/-0.021)e+23
6 3 O16 (6.85+/-0.10)e+22
7 3 B10 (6.85+/-0.10)e+18
Volume calculation 1
Domain 1: 4.1419 +/- 0.0426 cm^3
Domain 2: 31.4693 +/- 0.0721 cm^3
Material Nuclide Atoms Uncertainty
0 1 H1 2.769690e+23 2.850067e+21
1 1 O16 1.384845e+23 1.425034e+21
2 1 B10 1.384845e+19 1.425034e+17
3 2 U235 3.481769e+23 7.979991e+20
4 2 Mo99 3.481769e+22 7.979991e+19
Domain 1: 4.14+/-0.04 cm^3
Domain 2: 31.47+/-0.07 cm^3
Material Nuclide Atoms
0 1 H1 (2.770+/-0.029)e+23
1 1 O16 (1.385+/-0.014)e+23
2 1 B10 (1.385+/-0.014)e+19
3 2 U235 (3.482+/-0.008)e+23
4 2 Mo99 (3.482+/-0.008)e+22
Volume calculation 2
Domain 0: 35.6112 +/- 0.0664 cm^3
Universe Nuclide Atoms Uncertainty
0 0 H1 2.769690e+23 2.850067e+21
1 0 O16 1.384845e+23 1.425034e+21
2 0 B10 1.384845e+19 1.425034e+17
3 0 U235 3.481769e+23 7.979991e+20
4 0 Mo99 3.481769e+22 7.979991e+19
Domain 0: 35.61+/-0.07 cm^3
Universe Nuclide Atoms
0 0 H1 (2.770+/-0.029)e+23
1 0 O16 (1.385+/-0.014)e+23
2 0 B10 (1.385+/-0.014)e+19
3 0 U235 (3.482+/-0.008)e+23
4 0 Mo99 (3.482+/-0.008)e+22

View file

@ -64,8 +64,7 @@ class VolumeTest(PyAPITestHarness):
# Write cell volumes and total # of atoms for each nuclide
for uid, volume in sorted(volume_calc.volumes.items()):
outstr += 'Domain {0}: {1[0]:.4f} +/- {1[1]:.4f} cm^3\n'.format(
uid, volume)
outstr += 'Domain {}: {} cm^3\n'.format(uid, volume)
outstr += str(volume_calc.atoms_dataframe) + '\n'
return outstr

View file

@ -75,7 +75,7 @@ class TestHarness(object):
# Write out k-combined.
outstr = 'k-combined:\n'
form = '{0:12.6E} {1:12.6E}\n'
outstr += form.format(sp.k_combined[0], sp.k_combined[1])
outstr += form.format(sp.k_combined.n, sp.k_combined.s)
# Write out tally data.
for i, tally_ind in enumerate(sp.tallies):

View file

@ -4,6 +4,7 @@ import os
import numpy as np
import pytest
import openmc
import openmc.exceptions as exc
import openmc.capi
from tests import cdtemp
@ -25,6 +26,15 @@ def pincell_model():
mat_tally.scores = ['total', 'elastic', '(n,gamma)']
pincell.tallies.append(mat_tally)
# Add an expansion tally
zernike_tally = openmc.Tally()
filter3 = openmc.ZernikeFilter(5, r=.63)
cells = pincell.geometry.root_universe.cells
filter4 = openmc.CellFilter(list(cells.values()))
zernike_tally.filters = [filter3, filter4]
zernike_tally.scores = ['fission']
pincell.tallies.append(zernike_tally)
# Write XML files in tmpdir
with cdtemp():
pincell.export_to_xml()
@ -60,7 +70,7 @@ def test_cell(capi_init):
def test_new_cell(capi_init):
with pytest.raises(openmc.capi.AllocationError):
with pytest.raises(exc.AllocationError):
openmc.capi.Cell(1)
new_cell = openmc.capi.Cell()
new_cell_with_id = openmc.capi.Cell(10)
@ -91,7 +101,7 @@ def test_material(capi_init):
def test_new_material(capi_init):
with pytest.raises(openmc.capi.AllocationError):
with pytest.raises(exc.AllocationError):
openmc.capi.Material(1)
new_mat = openmc.capi.Material()
new_mat_with_id = openmc.capi.Material(10)
@ -109,7 +119,7 @@ def test_nuclide_mapping(capi_init):
def test_load_nuclide(capi_init):
openmc.capi.load_nuclide('Pu239')
with pytest.raises(openmc.capi.DataError):
with pytest.raises(exc.DataError):
openmc.capi.load_nuclide('Pu3')
@ -131,7 +141,7 @@ def test_settings(capi_init):
def test_tally_mapping(capi_init):
tallies = openmc.capi.tallies
assert isinstance(tallies, Mapping)
assert len(tallies) == 1
assert len(tallies) == 2
for tally_id, tally in tallies.items():
assert isinstance(tally, openmc.capi.Tally)
assert tally_id == tally.id
@ -145,7 +155,7 @@ def test_tally(capi_init):
assert isinstance(t.filters[1], openmc.capi.EnergyFilter)
# Create new filter and replace existing
with pytest.raises(openmc.capi.AllocationError):
with pytest.raises(exc.AllocationError):
openmc.capi.MaterialFilter(uid=1)
mats = openmc.capi.materials
f = openmc.capi.MaterialFilter([mats[2], mats[1]])
@ -153,7 +163,7 @@ def test_tally(capi_init):
assert t.filters == [f]
assert t.nuclides == ['U235', 'U238']
with pytest.raises(openmc.capi.DataError):
with pytest.raises(exc.DataError):
t.nuclides = ['Zr2']
t.nuclides = ['U234', 'Zr90']
assert t.nuclides == ['U234', 'Zr90']
@ -163,25 +173,41 @@ def test_tally(capi_init):
t.scores = new_scores
assert t.scores == new_scores
assert not t.active
t.active = True
assert t.active
t2 = openmc.capi.tallies[2]
t2.id = 2
assert len(t2.filters) == 2
assert isinstance(t2.filters[0], openmc.capi.ZernikeFilter)
assert isinstance(t2.filters[1], openmc.capi.CellFilter)
assert len(t2.filters[1].bins) == 3
assert t2.filters[0].order == 5
def test_new_tally(capi_init):
with pytest.raises(openmc.capi.AllocationError):
with pytest.raises(exc.AllocationError):
openmc.capi.Material(1)
new_tally = openmc.capi.Tally()
new_tally.scores = ['flux']
new_tally_with_id = openmc.capi.Tally(10)
new_tally_with_id.scores = ['flux']
assert len(openmc.capi.tallies) == 3
assert len(openmc.capi.tallies) == 4
def test_tally_results(capi_run):
t = openmc.capi.tallies[1]
assert t.num_realizations == 5
assert t.num_realizations == 10 # t was made active in test_tally
assert np.all(t.mean >= 0)
nonzero = (t.mean > 0.0)
assert np.all(t.std_dev[nonzero] >= 0)
assert np.all(t.ci_width()[nonzero] >= 1.95*t.std_dev[nonzero])
t2 = openmc.capi.tallies[2]
n = 5
assert t2.mean.size == (n + 1) * (n + 2) // 2 * 3 # Number of Zernike coeffs * 3 cells
def test_global_tallies(capi_run):
assert openmc.capi.num_realizations() == 5
@ -206,7 +232,7 @@ def test_by_batch(capi_run):
# Running next batch before simulation is initialized should raise an
# exception
with pytest.raises(openmc.capi.AllocationError):
with pytest.raises(exc.AllocationError):
openmc.capi.next_batch()
openmc.capi.simulation_init()
@ -241,7 +267,7 @@ def test_find_cell(capi_init):
assert cell is openmc.capi.cells[1]
cell, instance = openmc.capi.find_cell((0.4, 0., 0.))
assert cell is openmc.capi.cells[2]
with pytest.raises(openmc.capi.GeometryError):
with pytest.raises(exc.GeometryError):
openmc.capi.find_cell((100., 100., 100.))
@ -250,3 +276,38 @@ def test_find_material(capi_init):
assert mat is openmc.capi.materials[1]
mat = openmc.capi.find_material((0.4, 0., 0.))
assert mat is openmc.capi.materials[2]
def test_mesh(capi_init):
mesh = openmc.capi.Mesh()
mesh.dimension = (2, 3, 4)
assert mesh.dimension == (2, 3, 4)
with pytest.raises(exc.AllocationError):
mesh2 = openmc.capi.Mesh(mesh.id)
# Make sure each combination of parameters works
ll = (0., 0., 0.)
ur = (10., 10., 10.)
width = (1., 1., 1.)
mesh.set_parameters(lower_left=ll, upper_right=ur)
assert mesh.lower_left == pytest.approx(ll)
assert mesh.upper_right == pytest.approx(ur)
mesh.set_parameters(lower_left=ll, width=width)
assert mesh.lower_left == pytest.approx(ll)
assert mesh.width == pytest.approx(width)
mesh.set_parameters(upper_right=ur, width=width)
assert mesh.upper_right == pytest.approx(ur)
assert mesh.width == pytest.approx(width)
meshes = openmc.capi.meshes
assert isinstance(meshes, Mapping)
assert len(meshes) == 1
for mesh_id, mesh in meshes.items():
assert isinstance(mesh, openmc.capi.Mesh)
assert mesh_id == mesh.id
mf = openmc.capi.MeshFilter(mesh)
assert mf.mesh == mesh
msf = openmc.capi.MeshSurfaceFilter(mesh)
assert msf.mesh == mesh

View file

@ -50,6 +50,19 @@ def test_thin():
assert f(1.0) == pytest.approx(np.sin(1.0), 0.001)
def test_atomic_mass():
assert openmc.data.atomic_mass('H1') == 1.00782503223
assert openmc.data.atomic_mass('U235') == 235.043930131
with pytest.raises(KeyError):
openmc.data.atomic_mass('U100')
def test_atomic_weight():
assert openmc.data.atomic_weight('C') == 12.011115164862904
with pytest.raises(ValueError):
openmc.data.atomic_weight('Qt')
def test_water_density():
dens = openmc.data.water_density
# These test values are from IAPWS R7-97(2012). They are actually specific

View file

@ -17,6 +17,13 @@ def u235():
return openmc.data.WindowedMultipole.from_hdf5(filename)
@pytest.fixture(scope='module')
def u234():
directory = os.environ['OPENMC_MULTIPOLE_LIBRARY']
filename = os.path.join(directory, '092234.h5')
return openmc.data.WindowedMultipole.from_hdf5(filename)
@pytest.fixture(scope='module')
def fe56():
directory = os.environ['OPENMC_MULTIPOLE_LIBRARY']
@ -24,8 +31,8 @@ def fe56():
return openmc.data.WindowedMultipole.from_hdf5(filename)
def test_evaluate(u235):
"""Make sure multipole object can be called."""
def test_evaluate_rm(u235):
"""Make sure a Reich-Moore multipole object can be called."""
energies = [1e-3, 1.0, 10.0, 50.]
total, absorption, fission = u235(energies, 0.0)
assert total[1] == pytest.approx(90.64895383)
@ -33,6 +40,15 @@ def test_evaluate(u235):
assert total[1] == pytest.approx(91.12534964)
def test_evaluate_mlbw(u234):
"""Make sure a Multi-Level Breit-Wigner multipole object can be called."""
energies = [1e-3, 1.0, 10.0, 50.]
total, absorption, fission = u234(energies, 0.0)
assert total[3] == pytest.approx(15.02827953)
total, absorption, fission = u234(energies, 300.0)
assert total[3] == pytest.approx(15.08269143)
def test_high_l(fe56):
"""Test a nuclide (Fe56) with a high l-value (4)."""
energies = [1e-3, 1.0, 10.0, 1e3, 1e5]
@ -40,3 +56,9 @@ def test_high_l(fe56):
assert total[0] == pytest.approx(25.072619556789267)
total, absorption, fission = fe56(energies, 300.0)
assert total[0] == pytest.approx(27.85535792368082)
def test_export_to_hdf5(tmpdir, u235):
filename = str(tmpdir.join('092235.h5'))
u235.export_to_hdf5(filename)
assert os.path.exists(filename)

View file

@ -345,10 +345,10 @@ def test_nbody(tmpdir, h2):
assert nbody1.q_value == nbody2.q_value
def test_ace_convert(tmpdir):
def test_ace_convert(run_in_tmpdir):
filename = os.path.join(_ENDF_DATA, 'neutrons', 'n-001_H_001.endf')
ace_ascii = str(tmpdir.join('ace_ascii'))
ace_binary = str(tmpdir.join('ace_binary'))
ace_ascii = 'ace_ascii'
ace_binary = 'ace_binary'
openmc.data.njoy.make_ace(filename, ace=ace_ascii)
# Convert to binary

View file

@ -25,6 +25,9 @@ def test_results_save(run_in_tmpdir):
# Mock geometry
op = MagicMock()
# Avoid DummyOperator thinking it's doing a restart calculation
op.prev_res = None
vol_dict = {}
full_burn_list = []
@ -72,8 +75,8 @@ def test_results_save(run_in_tmpdir):
op_result1 = [OperatorResult(k, rates) for k, rates in zip(eigvl1, rate1)]
op_result2 = [OperatorResult(k, rates) for k, rates in zip(eigvl2, rate2)]
Results.save(op, x1, op_result1, t1, 0)
Results.save(op, x2, op_result2, t2, 1)
Results.save(op, x1, op_result1, t1, 0, 0)
Results.save(op, x2, op_result2, t2, 0, 1)
# Load the files
res = ResultsList("depletion_results.h5")

View file

@ -10,7 +10,7 @@ from tests import dummy_operator
def test_predictor(run_in_tmpdir):
"""Integral regression test of integrator algorithm using predictor/corrector"""
"""Integral regression test of integrator algorithm using predictor"""
op = dummy_operator.DummyOperator()
op.output_dir = "test_integrator_regression"

View file

@ -0,0 +1,168 @@
"""Regression tests for openmc.deplete restart capability.
These tests run in two steps, a first run then a restart run, a simple test
problem described in dummy_geometry.py.
"""
from pytest import approx
import openmc.deplete
from tests import dummy_operator
def test_restart_predictor(run_in_tmpdir):
"""Integral regression test of integrator algorithm using predictor."""
op = dummy_operator.DummyOperator()
output_dir = "test_restart_predictor"
op.output_dir = output_dir
# Perform simulation using the predictor algorithm
dt = [0.75]
power = 1.0
openmc.deplete.predictor(op, dt, power, print_out=False)
# Load the files
prev_res = openmc.deplete.ResultsList(op.output_dir / "depletion_results.h5")
# Re-create depletion operator and load previous results
op = dummy_operator.DummyOperator(prev_res)
op.output_dir = output_dir
# Perform restarts simulation using the predictor algorithm
openmc.deplete.predictor(op, dt, power, print_out=False)
# Load the files
res = openmc.deplete.ResultsList(op.output_dir / "depletion_results.h5")
_, y1 = res.get_atoms("1", "1")
_, y2 = res.get_atoms("1", "2")
# Mathematica solution
s1 = [2.46847546272295, 0.986431226850467]
s2 = [4.11525874568034, -0.0581692232513460]
assert y1[1] == approx(s1[0])
assert y2[1] == approx(s1[1])
assert y1[2] == approx(s2[0])
assert y2[2] == approx(s2[1])
def test_restart_cecm(run_in_tmpdir):
"""Integral regression test of integrator algorithm using CE/CM."""
op = dummy_operator.DummyOperator()
output_dir = "test_restart_cecm"
op.output_dir = output_dir
# Perform simulation using the MCNPX/MCNP6 algorithm
dt = [0.75]
power = 1.0
openmc.deplete.cecm(op, dt, power, print_out=False)
# Load the files
prev_res = openmc.deplete.ResultsList(op.output_dir / "depletion_results.h5")
# Re-create depletion operator and load previous results
op = dummy_operator.DummyOperator(prev_res)
op.output_dir = output_dir
# Perform restarts simulation using the MCNPX/MCNP6 algorithm
openmc.deplete.cecm(op, dt, power, print_out=False)
# Load the files
res = openmc.deplete.ResultsList(op.output_dir / "depletion_results.h5")
_, y1 = res.get_atoms("1", "1")
_, y2 = res.get_atoms("1", "2")
# Mathematica solution
s1 = [1.86872629872102, 1.395525772416039]
s2 = [2.18097439443550, 2.69429754646747]
assert y1[1] == approx(s1[0])
assert y2[1] == approx(s1[1])
assert y1[3] == approx(s2[0])
assert y2[3] == approx(s2[1])
def test_restart_predictor_cecm(run_in_tmpdir):
"""Integral regression test of integrator algorithm using predictor
for the first run then CE/CM for the restart run."""
op = dummy_operator.DummyOperator()
output_dir = "test_restart_predictor_cecm"
op.output_dir = output_dir
# Perform simulation using the predictor algorithm
dt = [0.75]
power = 1.0
openmc.deplete.predictor(op, dt, power, print_out=False)
# Load the files
prev_res = openmc.deplete.ResultsList(op.output_dir / "depletion_results.h5")
# Re-create depletion operator and load previous results
op = dummy_operator.DummyOperator(prev_res)
op.output_dir = output_dir
# Perform restarts simulation using the MCNPX/MCNP6 algorithm
openmc.deplete.cecm(op, dt, power, print_out=False)
# Load the files
res = openmc.deplete.ResultsList(op.output_dir / "depletion_results.h5")
_, y1 = res.get_atoms("1", "1")
_, y2 = res.get_atoms("1", "2")
# Test solution
s1 = [2.46847546272295, 0.986431226850467]
s2 = [3.09106948392, 0.607102912398]
assert y1[1] == approx(s1[0])
assert y2[1] == approx(s1[1])
assert y1[2] == approx(s2[0])
assert y2[2] == approx(s2[1])
def test_restart_cecm_predictor(run_in_tmpdir):
"""Integral regression test of integrator algorithm using CE/CM for the
first run then predictor for the restart run."""
op = dummy_operator.DummyOperator()
output_dir = "test_restart_cecm_predictor"
op.output_dir = output_dir
# Perform simulation using the MCNPX/MCNP6 algorithm
dt = [0.75]
power = 1.0
openmc.deplete.cecm(op, dt, power, print_out=False)
# Load the files
prev_res = openmc.deplete.ResultsList(op.output_dir / "depletion_results.h5")
# Re-create depletion operator and load previous results
op = dummy_operator.DummyOperator(prev_res)
op.output_dir = output_dir
# Perform restarts simulation using the predictor algorithm
openmc.deplete.predictor(op, dt, power, print_out=False)
# Load the files
res = openmc.deplete.ResultsList(op.output_dir / "depletion_results.h5")
_, y1 = res.get_atoms("1", "1")
_, y2 = res.get_atoms("1", "2")
# Test solution
s1 = [1.86872629872102, 1.395525772416039]
s2 = [3.32776806576, 2.391425905]
assert y1[1] == approx(s1[0])
assert y2[1] == approx(s1[1])
assert y1[2] == approx(s2[0])
assert y2[2] == approx(s2[1])

View file

@ -22,8 +22,8 @@ def test_get_atoms(res):
n_ref = [6.6747328233649218e+08, 3.5421791038348462e+14,
3.6208592242443462e+14, 3.3799758969347038e+14]
np.testing.assert_array_equal(t, t_ref)
np.testing.assert_array_equal(n, n_ref)
np.testing.assert_allclose(t, t_ref)
np.testing.assert_allclose(n, n_ref)
def test_get_reaction_rate(res):
"""Tests evaluating reaction rate."""
@ -35,8 +35,8 @@ def test_get_reaction_rate(res):
xs_ref = np.array([4.0594392323131994e-05, 3.9249546927524987e-05,
3.8394587728581798e-05, 4.1521845978371697e-05])
np.testing.assert_array_equal(t, t_ref)
np.testing.assert_array_equal(r, n_ref * xs_ref)
np.testing.assert_allclose(t, t_ref)
np.testing.assert_allclose(r, n_ref * xs_ref)
def test_get_eigenvalue(res):
@ -47,5 +47,5 @@ def test_get_eigenvalue(res):
k_ref = [1.181281798790367, 1.1798750921988739, 1.1965943696058159,
1.2207119847790813]
np.testing.assert_array_equal(t, t_ref)
np.testing.assert_array_equal(k, k_ref)
np.testing.assert_allclose(t, t_ref)
np.testing.assert_allclose(k, k_ref)

View file

@ -0,0 +1,148 @@
from math import sqrt, pi
import openmc
from pytest import fixture, approx
@fixture(scope='module')
def box_model():
model = openmc.model.Model()
m = openmc.Material()
m.add_nuclide('U235', 1.0)
m.set_density('g/cm3', 1.0)
box = openmc.model.get_rectangular_prism(10., 10., boundary_type='vacuum')
c = openmc.Cell(fill=m, region=box)
model.geometry.root_universe = openmc.Universe(cells=[c])
model.settings.particles = 100
model.settings.batches = 10
model.settings.inactive = 0
model.settings.source = openmc.Source(space=openmc.stats.Point())
return model
def test_legendre():
n = 5
f = openmc.LegendreFilter(n)
assert f.order == n
assert f.bins[0] == 'P0'
assert f.bins[-1] == 'P5'
assert len(f.bins) == n + 1
# Make sure __repr__ works
repr(f)
# to_xml_element()
elem = f.to_xml_element()
assert elem.tag == 'filter'
assert elem.attrib['type'] == 'legendre'
assert elem.find('order').text == str(n)
def test_spatial_legendre():
n = 5
axis = 'x'
f = openmc.SpatialLegendreFilter(n, axis, -10., 10.)
assert f.order == n
assert f.axis == axis
assert f.minimum == -10.
assert f.maximum == 10.
assert f.bins[0] == 'P0'
assert f.bins[-1] == 'P5'
assert len(f.bins) == n + 1
# Make sure __repr__ works
repr(f)
# to_xml_element()
elem = f.to_xml_element()
assert elem.tag == 'filter'
assert elem.attrib['type'] == 'spatiallegendre'
assert elem.find('order').text == str(n)
assert elem.find('axis').text == str(axis)
def test_spherical_harmonics():
n = 3
f = openmc.SphericalHarmonicsFilter(n)
f.cosine = 'particle'
assert f.order == n
assert f.bins[0] == 'Y0,0'
assert f.bins[-1] == 'Y{0},{0}'.format(n, n)
assert len(f.bins) == (n + 1)**2
# Make sure __repr__ works
repr(f)
# to_xml_element()
elem = f.to_xml_element()
assert elem.tag == 'filter'
assert elem.attrib['type'] == 'sphericalharmonics'
assert elem.attrib['cosine'] == f.cosine
assert elem.find('order').text == str(n)
def test_zernike():
n = 4
f = openmc.ZernikeFilter(n, 0., 0., 1.)
assert f.order == n
assert f.bins[0] == 'Z0,0'
assert f.bins[-1] == 'Z{0},{0}'.format(n)
assert len(f.bins) == (n + 1)*(n + 2)//2
# Make sure __repr__ works
repr(f)
# to_xml_element()
elem = f.to_xml_element()
assert elem.tag == 'filter'
assert elem.attrib['type'] == 'zernike'
assert elem.find('order').text == str(n)
def test_first_moment(run_in_tmpdir, box_model):
plain_tally = openmc.Tally()
plain_tally.scores = ['flux', 'scatter']
# Create tallies with expansion filters
leg_tally = openmc.Tally()
leg_tally.filters = [openmc.LegendreFilter(3)]
leg_tally.scores = ['scatter']
leg_sptl_tally = openmc.Tally()
leg_sptl_tally.filters = [openmc.SpatialLegendreFilter(3, 'x', -5., 5.)]
leg_sptl_tally.scores = ['scatter']
sph_scat_filter = openmc.SphericalHarmonicsFilter(5)
sph_scat_filter.cosine = 'scatter'
sph_scat_tally = openmc.Tally()
sph_scat_tally.filters = [sph_scat_filter]
sph_scat_tally.scores = ['scatter']
sph_flux_filter = openmc.SphericalHarmonicsFilter(5)
sph_flux_filter.cosine = 'particle'
sph_flux_tally = openmc.Tally()
sph_flux_tally.filters = [sph_flux_filter]
sph_flux_tally.scores = ['flux']
zernike_tally = openmc.Tally()
zernike_tally.filters = [openmc.ZernikeFilter(3, r=10.)]
zernike_tally.scores = ['scatter']
# Add tallies to model and ensure they all use the same estimator
box_model.tallies = [plain_tally, leg_tally, leg_sptl_tally,
sph_scat_tally, sph_flux_tally, zernike_tally]
for t in box_model.tallies:
t.estimator = 'analog'
box_model.run()
# Check that first moment matches the score from the plain tally
with openmc.StatePoint('statepoint.10.h5') as sp:
# Get scores from tally without expansion filters
flux, scatter = sp.tallies[plain_tally.id].mean.ravel()
# Check that first moment matches
first_score = lambda t: sp.tallies[t.id].mean.ravel()[0]
assert first_score(leg_tally) == scatter
assert first_score(leg_sptl_tally) == scatter
assert first_score(sph_scat_tally) == scatter
assert first_score(sph_flux_tally) == approx(flux)
assert first_score(zernike_tally) == approx(scatter)

View file

@ -15,9 +15,9 @@ def test_nuclides(uo2):
"""Test adding/removing nuclides."""
m = openmc.Material()
m.add_nuclide('U235', 1.0)
with pytest.raises(ValueError):
with pytest.raises(TypeError):
m.add_nuclide('H1', '1.0')
with pytest.raises(ValueError):
with pytest.raises(TypeError):
m.add_nuclide(1.0, 'H1')
with pytest.raises(ValueError):
m.add_nuclide('H1', 1.0, 'oa')

View file

@ -0,0 +1,212 @@
import numpy as np
import scipy as sp
import openmc
import openmc.capi
def test_t_percentile():
# Permutations include 1 DoF, 2 DoF, and > 2 DoF
# We will test 5 p-values at 3-DoF values
test_ps = [0.02, 0.4, 0.5, 0.6, 0.98]
test_dfs = [1, 2, 5]
# The reference solutions come from Scipy
ref_ts = [[sp.stats.t.ppf(p, df) for p in test_ps] for df in test_dfs]
test_ts = [[openmc.capi.math.t_percentile(p, df) for p in test_ps]
for df in test_dfs]
# The 5 DoF approximation in openmc.capi.math.t_percentile is off by up to
# 8e-3 from the scipy solution, so test that one separately with looser
# tolerance
assert np.allclose(ref_ts[:-1], test_ts[:-1])
assert np.allclose(ref_ts[-1], test_ts[-1], atol=1e-2)
def test_calc_pn():
max_order = 10
test_xs = np.linspace(-1., 1., num=5, endpoint=True)
# Reference solutions from scipy
ref_vals = np.array([sp.special.eval_legendre(n, test_xs)
for n in range(0, max_order + 1)])
test_vals = []
for x in test_xs:
test_vals.append(openmc.capi.math.calc_pn(max_order, x).tolist())
test_vals = np.swapaxes(np.array(test_vals), 0, 1)
assert np.allclose(ref_vals, test_vals)
def test_evaluate_legendre():
max_order = 10
# Coefficients are set to 1, but will incorporate the (2l+1)/2 norm factor
# for the reference solution
test_coeffs = [0.5 * (2. * l + 1.) for l in range(max_order + 1)]
test_xs = np.linspace(-1., 1., num=5, endpoint=True)
ref_vals = np.polynomial.legendre.legval(test_xs, test_coeffs)
# Set the coefficients back to 1s for the test values since
# evaluate legendre incorporates the (2l+1)/2 term on its own
test_coeffs = [1. for l in range(max_order + 1)]
test_vals = np.array([openmc.capi.math.evaluate_legendre(test_coeffs, x)
for x in test_xs])
assert np.allclose(ref_vals, test_vals)
def test_calc_rn():
max_order = 10
test_ns = np.array([i for i in range(0, max_order + 1)])
azi = 0.1 # Longitude
pol = 0.2 # Latitude
test_uvw = np.array([np.sin(pol) * np.cos(azi),
np.sin(pol) * np.sin(azi),
np.cos(pol)])
# Reference solutions from the equations
ref_vals = []
def coeff(n, m):
return np.sqrt((2. * n + 1) * sp.special.factorial(n - m) /
(sp.special.factorial(n + m)))
def pnm_bar(n, m, mu):
val = coeff(n, m)
if m != 0:
val *= np.sqrt(2.)
val *= sp.special.lpmv([m], [n], [mu])
return val[0]
ref_vals = []
for n in test_ns:
for m in range(-n, n + 1):
if m < 0:
ylm = pnm_bar(n, np.abs(m), np.cos(pol)) * \
np.sin(np.abs(m) * azi)
else:
ylm = pnm_bar(n, m, np.cos(pol)) * np.cos(m * azi)
# Un-normalize for comparison
ylm /= np.sqrt(2. * n + 1.)
ref_vals.append(ylm)
test_vals = []
test_vals = openmc.capi.math.calc_rn(max_order, test_uvw)
assert np.allclose(ref_vals, test_vals)
def test_calc_zn():
n = 10
rho = 0.5
phi = 0.5
# Reference solution from running the Fortran implementation
ref_vals = np.array([
1.00000000e+00, 2.39712769e-01, 4.38791281e-01,
2.10367746e-01, -5.00000000e-01, 1.35075576e-01,
1.24686873e-01, -2.99640962e-01, -5.48489101e-01,
8.84215021e-03, 5.68310892e-02, -4.20735492e-01,
-1.25000000e-01, -2.70151153e-01, -2.60091773e-02,
1.87022545e-02, -3.42888902e-01, 1.49820481e-01,
2.74244551e-01, -2.43159131e-02, -2.50357380e-02,
2.20500013e-03, -1.98908812e-01, 4.07587508e-01,
4.37500000e-01, 2.61708929e-01, 9.10321205e-02,
-1.54686328e-02, -2.74049397e-03, -7.94845816e-02,
4.75368705e-01, 7.11647284e-02, 1.30266162e-01,
3.37106977e-02, 1.06401886e-01, -7.31606787e-03,
-2.95625975e-03, -1.10250006e-02, 3.55194307e-01,
-1.44627826e-01, -2.89062500e-01, -9.28644588e-02,
-1.62557358e-01, 7.73431638e-02, -2.55329539e-03,
-1.90923851e-03, 1.57578403e-02, 1.72995854e-01,
-3.66267690e-01, -1.81657333e-01, -3.32521518e-01,
-2.59738162e-02, -2.31580576e-01, 4.20673902e-02,
-4.11710546e-04, -9.36449487e-04, 1.92156884e-02,
2.82515641e-02, -3.90713738e-01, -1.69280296e-01,
-8.98437500e-02, -1.08693628e-01, 1.78813094e-01,
-1.98191857e-01, 1.65964201e-02, 2.77013853e-04])
test_vals = openmc.capi.math.calc_zn(n, rho, phi)
assert np.allclose(ref_vals, test_vals)
def test_rotate_angle():
uvw0 = np.array([1., 0., 0.])
phi = 0.
mu = 0.
# reference: mu of 0 pulls the vector the bottom, so:
ref_uvw = np.array([0., 0., -1.])
test_uvw = openmc.capi.math.rotate_angle(uvw0, mu, phi)
assert np.array_equal(ref_uvw, test_uvw)
# Repeat for mu = 1 (no change)
mu = 1.
ref_uvw = np.array([1., 0., 0.])
test_uvw = openmc.capi.math.rotate_angle(uvw0, mu, phi)
assert np.array_equal(ref_uvw, test_uvw)
# Now to test phi is None
mu = 0.9
settings = openmc.capi.settings
settings.seed = 1
# When seed = 1, phi will be sampled as 1.9116495709698769
# The resultant reference is from hand-calculations given the above
ref_uvw = [0.9, 0.410813051297112, 0.1457142302040]
test_uvw = openmc.capi.math.rotate_angle(uvw0, mu)
assert np.allclose(ref_uvw, test_uvw)
def test_maxwell_spectrum():
settings = openmc.capi.settings
settings.seed = 1
T = 0.5
ref_val = 0.6129982175261098
test_val = openmc.capi.math.maxwell_spectrum(T)
assert ref_val == test_val
def test_watt_spectrum():
settings = openmc.capi.settings
settings.seed = 1
a = 0.5
b = 0.75
ref_val = 0.6247242713640233
test_val = openmc.capi.math.watt_spectrum(a, b)
assert ref_val == test_val
def test_broaden_wmp_polynomials():
# Two branches of the code to worry about, beta > 6 and otherwise
# beta = sqrtE * dopp
# First lets do beta > 6
test_E = 0.5
test_dopp = 100. # approximately U235 at room temperature
n = 6
ref_val = [2., 1.41421356, 1.0001, 0.70731891, 0.50030001, 0.353907]
test_val = openmc.capi.math.broaden_wmp_polynomials(test_E, test_dopp, n)
assert np.allclose(ref_val, test_val)
# now beta < 6
test_dopp = 5.
ref_val = [1.99999885, 1.41421356, 1.04, 0.79195959, 0.6224, 0.50346003]
test_val = openmc.capi.math.broaden_wmp_polynomials(test_E, test_dopp, n)
assert np.allclose(ref_val, test_val)

View file

@ -0,0 +1,116 @@
import numpy as np
import openmc
import pytest
@pytest.fixture(scope='module')
def pincell1(uo2, water):
cyl = openmc.ZCylinder(R=0.35)
fuel = openmc.Cell(fill=uo2, region=-cyl)
moderator = openmc.Cell(fill=water, region=+cyl)
univ = openmc.Universe(cells=[fuel, moderator])
univ.fuel = fuel
univ.moderator = moderator
return univ
@pytest.fixture(scope='module')
def pincell2(uo2, water):
cyl = openmc.ZCylinder(R=0.4)
fuel = openmc.Cell(fill=uo2, region=-cyl)
moderator = openmc.Cell(fill=water, region=+cyl)
univ = openmc.Universe(cells=[fuel, moderator])
univ.fuel = fuel
univ.moderator = moderator
return univ
@pytest.fixture(scope='module')
def zr():
zr = openmc.Material()
zr.add_element('Zr', 1.0)
zr.set_density('g/cm3', 1.0)
return zr
@pytest.fixture(scope='module')
def rlat2(pincell1, pincell2, uo2, water, zr):
"""2D Rectangular lattice for testing."""
all_zr = openmc.Cell(fill=zr)
pitch = 1.2
n = 3
u1, u2 = pincell1, pincell2
lattice = openmc.RectLattice()
lattice.lower_left = (-pitch*n/2, -pitch*n/2)
lattice.pitch = (pitch, pitch)
lattice.outer = openmc.Universe(cells=[all_zr])
lattice.universes = [
[u1, u2, u1],
[u2, u1, u2],
[u2, u1, u1]
]
return lattice
@pytest.fixture(scope='module')
def rlat3(pincell1, pincell2, uo2, water, zr):
"""3D Rectangular lattice for testing."""
# Create another universe for top layer
hydrogen = openmc.Material()
hydrogen.add_element('H', 1.0)
hydrogen.set_density('g/cm3', 0.09)
h_cell = openmc.Cell(fill=hydrogen)
u3 = openmc.Universe(cells=[h_cell])
all_zr = openmc.Cell(fill=zr)
pitch = 1.2
n = 3
u1, u2 = pincell1, pincell2
lattice = openmc.RectLattice()
lattice.lower_left = (-pitch*n/2, -pitch*n/2, -10.0)
lattice.pitch = (pitch, pitch, 10.0)
lattice.outer = openmc.Universe(cells=[all_zr])
lattice.universes = [
[[u1, u2, u1],
[u2, u1, u2],
[u2, u1, u1]],
[[u3, u1, u2],
[u1, u3, u2],
[u2, u1, u1]]
]
return lattice
def test_mesh2d(rlat2):
shape = np.array(rlat2.shape)
width = shape*rlat2.pitch
mesh1 = openmc.Mesh.from_rect_lattice(rlat2)
assert np.array_equal(mesh1.dimension, (3, 3))
assert np.array_equal(mesh1.lower_left, rlat2.lower_left)
assert np.array_equal(mesh1.upper_right, rlat2.lower_left + width)
mesh2 = openmc.Mesh.from_rect_lattice(rlat2, division=3)
assert np.array_equal(mesh2.dimension, (9, 9))
assert np.array_equal(mesh2.lower_left, rlat2.lower_left)
assert np.array_equal(mesh2.upper_right, rlat2.lower_left + width)
def test_mesh3d(rlat3):
shape = np.array(rlat3.shape)
width = shape*rlat3.pitch
mesh1 = openmc.Mesh.from_rect_lattice(rlat3)
assert np.array_equal(mesh1.dimension, (3, 3, 2))
assert np.array_equal(mesh1.lower_left, rlat3.lower_left)
assert np.array_equal(mesh1.upper_right, rlat3.lower_left + width)
mesh2 = openmc.Mesh.from_rect_lattice(rlat3, division=3)
assert np.array_equal(mesh2.dimension, (9, 9, 6))
assert np.array_equal(mesh2.lower_left, rlat3.lower_left)
assert np.array_equal(mesh2.upper_right, rlat3.lower_left + width)

View file

@ -0,0 +1,161 @@
#!/usr/bin/env python
from math import pi
import numpy as np
from numpy.linalg import norm
import openmc
import openmc.model
import pytest
import scipy.spatial
_PACKING_FRACTION = 0.35
_RADIUS = 4.25e-2
domain_params = [
{'shape': 'cube', 'length': 0.75, 'radius': 0., 'volume': 0.75**3},
{'shape': 'cylinder', 'length': 0.5, 'radius': 0.5, 'volume': 0.5*pi*0.5**2},
{'shape': 'sphere', 'length': 0., 'radius': 0.5, 'volume': 4/3*pi*0.5**3}
]
@pytest.fixture(scope='module', params=domain_params,
ids=['cube', 'cylinder', 'sphere'])
def domain(request):
return request.param
@pytest.fixture(scope='module')
def triso_universe():
sphere = openmc.Sphere(R=_RADIUS)
cell = openmc.Cell(region=-sphere)
univ = openmc.Universe(cells=[cell])
return univ
@pytest.fixture(scope='module')
def trisos(domain, triso_universe):
trisos = openmc.model.pack_trisos(
radius=_RADIUS,
fill=triso_universe,
domain_shape=domain['shape'],
domain_length=domain['length'],
domain_radius=domain['radius'],
domain_center=(0., 0., 0.),
initial_packing_fraction=0.2,
packing_fraction=_PACKING_FRACTION
)
return trisos
def test_overlap(trisos):
"""Check that no TRISO particles overlap."""
centers = [t.center for t in trisos]
# Create KD tree for quick nearest neighbor search
tree = scipy.spatial.cKDTree(centers)
# Find distance to nearest neighbor for all particles
d = tree.query(centers, k=2)[0]
# Get the smallest distance between any two particles
d_min = min(d[:, 1])
assert d_min > 2*_RADIUS or d_min == pytest.approx(2*_RADIUS)
def test_contained(trisos, domain):
"""Make sure all particles are entirely contained within the domain."""
if domain['shape'] == 'cube':
x = max(np.hstack([abs(t.center) for t in trisos])) + _RADIUS
assert x < 0.5*domain['length'] or x == pytest.approx(0.5*domain['length'])
elif domain['shape'] == 'cylinder':
r = max([norm(t.center[0:2]) for t in trisos]) + _RADIUS
z = max([abs(t.center[2]) for t in trisos]) + _RADIUS
assert r < domain['radius'] or r == pytest.approx(domain['radius'])
assert z < 0.5*domain['length'] or z == pytest.approx(0.5*domain['length'])
elif domain['shape'] == 'sphere':
r = max([norm(t.center) for t in trisos]) + _RADIUS
assert r < domain['radius'] or r == pytest.approx(domain['radius'])
def test_packing_fraction(trisos, domain):
"""Check that the actual PF is close to the requested PF."""
pf = len(trisos)*4/3*pi*_RADIUS**3/domain['volume']
assert pf == pytest.approx(_PACKING_FRACTION, rel=1e-2)
def test_n_particles(triso_universe):
"""Check that the function returns the correct number of particles"""
trisos = openmc.model.pack_trisos(
radius=_RADIUS, fill=triso_universe, domain_shape='cube',
domain_length=1.0, n_particles=800
)
assert len(trisos) == 800
def test_triso_lattice(triso_universe):
trisos = openmc.model.pack_trisos(
radius=_RADIUS, fill=triso_universe, domain_shape='cube',
domain_length=1.0, domain_center=(0., 0., 0.), packing_fraction=0.2
)
lower_left = np.array((-.5, -.5, -.5))
upper_right = np.array((.5, .5, .5))
shape = (3, 3, 3)
pitch = (upper_right - lower_left)/shape
background = openmc.Material()
lattice = openmc.model.create_triso_lattice(
trisos, lower_left, pitch, shape, background
)
def test_domain_input(triso_universe):
# Invalid domain shape
with pytest.raises(ValueError):
trisos = openmc.model.pack_trisos(
radius=1, fill=triso_universe, n_particles=100,
domain_shape='circle'
)
# Don't specify domain length on a cube
with pytest.raises(ValueError):
trisos = openmc.model.pack_trisos(
radius=1, fill=triso_universe, n_particles=100,
domain_shape='cube'
)
# Don't specify domain radius on a sphere
with pytest.raises(ValueError):
trisos = openmc.model.pack_trisos(
radius=1, fill=triso_universe, n_particles=100,
domain_shape='sphere'
)
def test_packing_fraction_input(triso_universe):
# Provide neither packing fraction nor number of particles
with pytest.raises(ValueError):
trisos = openmc.model.pack_trisos(
radius=1, fill=triso_universe, domain_shape='cube',
domain_length=10
)
# Provide both packing fraction and number of particles
with pytest.raises(ValueError):
trisos = openmc.model.pack_trisos(
radius=1, fill=triso_universe, domain_shape='cube',
domain_length=10, n_particles=100, packing_fraction=0.2
)
# Specify a packing fraction that is too high for CRP
with pytest.raises(ValueError):
trisos = openmc.model.pack_trisos(
radius=1, fill=triso_universe, domain_shape='cube',
domain_length=10, packing_fraction=1
)
# Specify a packing fraction that is too high for RSP
with pytest.raises(ValueError):
trisos = openmc.model.pack_trisos(
radius=1, fill=triso_universe, domain_shape='cube',
domain_length=10, packing_fraction=0.5,
initial_packing_fraction=0.4
)

View file

@ -0,0 +1,45 @@
"""Regression tests for openmc.deplete.Results.transfer_volumes method.
"""
from pytest import approx
import openmc.deplete
from tests import dummy_operator
def test_transfer_volumes(run_in_tmpdir):
"""Unit test of volume transfer in restart calculations."""
op = dummy_operator.DummyOperator()
op.output_dir = "test_transfer_volumes"
# Perform simulation using the predictor algorithm
dt = [0.75]
power = 1.0
openmc.deplete.predictor(op, dt, power, print_out=False)
# Load the files
res = openmc.deplete.ResultsList(op.output_dir / "depletion_results.h5")
# Create a dictionary of volumes to transfer
res[0].volume['1'] = 1.5
res[0].volume['2'] = 2.5
# Create dummy geometry
mat1 = openmc.Material(material_id=1)
mat1.depletable = True
mat2 = openmc.Material(material_id=2)
cell = openmc.Cell()
cell.fill = [mat1, mat2]
root = openmc.Universe()
root.add_cell(cell)
geometry = openmc.Geometry(root)
# Transfer volumes
res[0].transfer_volumes(geometry)
assert mat1.volume == 1.5
assert mat2.volume is None

View file

@ -59,7 +59,6 @@ def test_plot(run_in_tmpdir, sphere_model):
pixels=(10, 10),
color_by='material',
colors=colors,
filename='test.png'
)