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Fixed typo in mgxs.py and modified all tests except distribcell

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This commit is contained in:
Miriam 2020-10-07 19:36:03 +00:00
parent 679be77c6c
commit 6b3374a15e
11 changed files with 1301 additions and 1045 deletions
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2
openmc/mgxs/mgxs.py
View file

@ -2975,7 +2975,7 @@ class DiffusionCoefficient(TransportXS):
if not nu:
self._rxn_type = 'diffusion-coefficient'
else:
self._rxn_type = 'nu-diffision-coefficient'
self._rxn_type = 'nu-diffusion-coefficient'
@property

104
tests/regression_tests/mgxs_library_condense/inputs_true.dat
View file

@ -76,7 +76,7 @@
<filter id="66" type="meshsurface">
<bins>1</bins>
</filter>
<filter id="73" type="delayedgroup">
<filter id="77" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
@ -422,55 +422,79 @@
<estimator>tracklength</estimator>
</tally>
<tally id="58">
<filters>1 73 2</filters>
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="59">
<filters>1 73 52</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="60">
<filters>1 73 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="61">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="62">
<filters>1 73 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="63">
<filters>1 73</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="64">
<filters>1 73</filters>
<nuclides>total</nuclides>
<scores>decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="65">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="60">
<filters>1 5 6</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="61">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="62">
<filters>1 77 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="63">
<filters>1 77 52</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="64">
<filters>1 77 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="65">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="66">
<filters>1 73 2 5</filters>
<filters>1 77 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="67">
<filters>1 77</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="68">
<filters>1 77</filters>
<nuclides>total</nuclides>
<scores>decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="69">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="70">
<filters>1 77 2 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>

10
tests/regression_tests/mgxs_library_condense/results_true.dat
View file

@ -221,6 +221,16 @@
3 2 1 1 0 total 1.056682 0.124372
2 2 1 1 1 total 0.282075 0.053614
7 2 2 1 0 total 1.070487 0.130335
6 2 2 1 1 total 0.301100 0.036907
mesh 1 group in nuclide mean std. dev.
x y z
1 1 1 1 0 total 1.074807 0.098944
0 1 1 1 1 total 0.303789 0.059060
5 1 2 1 0 total 1.085284 0.132314
4 1 2 1 1 total 0.299594 0.054735
3 2 1 1 0 total 1.056682 0.124372
2 2 1 1 1 total 0.282075 0.053614
7 2 2 1 0 total 1.070487 0.130335
6 2 2 1 1 total 0.301100 0.036907
mesh 1 delayedgroup group in nuclide mean std. dev.
x y z

104
tests/regression_tests/mgxs_library_hdf5/inputs_true.dat
View file

@ -76,7 +76,7 @@
<filter id="66" type="meshsurface">
<bins>1</bins>
</filter>
<filter id="73" type="delayedgroup">
<filter id="77" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
@ -422,55 +422,79 @@
<estimator>tracklength</estimator>
</tally>
<tally id="58">
<filters>1 73 2</filters>
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="59">
<filters>1 73 52</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="60">
<filters>1 73 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="61">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="62">
<filters>1 73 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="63">
<filters>1 73</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="64">
<filters>1 73</filters>
<nuclides>total</nuclides>
<scores>decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="65">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="60">
<filters>1 5 6</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="61">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="62">
<filters>1 77 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="63">
<filters>1 77 52</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="64">
<filters>1 77 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="65">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="66">
<filters>1 73 2 5</filters>
<filters>1 77 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="67">
<filters>1 77</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="68">
<filters>1 77</filters>
<nuclides>total</nuclides>
<scores>decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="69">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="70">
<filters>1 77 2 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>

5
tests/regression_tests/mgxs_library_hdf5/results_true.dat
View file

@ -144,6 +144,11 @@ domain=1 type=current
[2.54950976e-02 2.35372046e-02 0.00000000e+00 0.00000000e+00
4.66261729e-02 4.14728827e-02 0.00000000e+00 0.00000000e+00]]]
domain=1 type=diffusion-coefficient
[[3.03788848e-01 -2.11056360e+01]
[1.07480743e+00 1.14272636e+01]]
[[5.90602575e-02 3.45906931e+02]
[9.89437598e-02 1.55214591e+01]]
domain=1 type=nu-diffusion-coefficient
[[3.03788848e-01 -2.11056360e+01]
[1.07480743e+00 1.14272636e+01]]
[[5.90602575e-02 3.45906931e+02]

104
tests/regression_tests/mgxs_library_mesh/inputs_true.dat
View file

@ -56,7 +56,7 @@
<filter id="66" type="meshsurface">
<bins>1</bins>
</filter>
<filter id="73" type="delayedgroup">
<filter id="77" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
@ -402,55 +402,79 @@
<estimator>tracklength</estimator>
</tally>
<tally id="58">
<filters>1 73 2</filters>
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="59">
<filters>1 73 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="60">
<filters>1 73 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="61">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="62">
<filters>1 73 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="63">
<filters>1 73</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="64">
<filters>1 73</filters>
<nuclides>total</nuclides>
<scores>decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="65">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="60">
<filters>1 5 6</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="61">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="62">
<filters>1 77 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="63">
<filters>1 77 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="64">
<filters>1 77 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="65">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="66">
<filters>1 73 2 5</filters>
<filters>1 77 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="67">
<filters>1 77</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="68">
<filters>1 77</filters>
<nuclides>total</nuclides>
<scores>decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="69">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="70">
<filters>1 77 2 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>

10
tests/regression_tests/mgxs_library_mesh/results_true.dat
View file

@ -222,6 +222,16 @@
3 2 1 1 1 P1 total 4.473154 0.305332
6 2 2 1 1 P0 total 30.771010 11.932125
7 2 2 1 1 P1 total 4.590355 0.194749
mesh 1 group in legendre nuclide mean std. dev.
x y z
0 1 1 1 1 P0 total 18.968331 9.251702
1 1 1 1 1 P1 total 4.240624 0.416071
4 1 2 1 1 P0 total 22.712655 9.499755
5 1 2 1 1 P1 total 4.386613 0.231699
2 2 1 1 1 P0 total 26.698250 14.801556
3 2 1 1 1 P1 total 4.470037 0.305568
6 2 2 1 1 P0 total 31.429164 12.489145
7 2 2 1 1 P1 total 4.592270 0.194140
mesh 1 delayedgroup group in nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 0.000007 4.734745e-07

1110
tests/regression_tests/mgxs_library_no_nuclides/inputs_true.dat
View file

File diff suppressed because it is too large Load diff

15
tests/regression_tests/mgxs_library_no_nuclides/results_true.dat
View file

@ -132,6 +132,11 @@
2 1 1 P0 total 10.942878 12.704137
3 1 1 P1 total 0.918041 0.075837
0 1 2 P0 total 1.370855 0.292448
1 1 2 P1 total 0.516916 0.050251
material group in legendre nuclide mean std. dev.
2 1 1 P0 total 10.942878 12.704137
3 1 1 P1 total 0.918041 0.075837
0 1 2 P0 total 1.370855 0.292448
1 1 2 P1 total 0.516916 0.050251
material delayedgroup group in nuclide mean std. dev.
1 1 1 1 total 0.000004 2.897486e-07
@ -338,6 +343,11 @@
2 2 1 P0 total 92.158584 948.055013
3 2 1 P1 total 1.209886 0.097583
0 2 2 P0 total 73.145434 834.775399
1 2 2 P1 total 1.068256 0.148711
material group in legendre nuclide mean std. dev.
2 2 1 P0 total 92.158584 948.055013
3 2 1 P1 total 1.209886 0.097583
0 2 2 P0 total 73.145434 834.775399
1 2 2 P1 total 1.068256 0.148711
material delayedgroup group in nuclide mean std. dev.
1 2 1 1 total 0.0 0.0
@ -544,6 +554,11 @@
2 3 1 P0 total 13.561252 21.988396
3 3 1 P1 total 1.176515 0.154807
0 3 2 P0 total -2.459765 6.393743
1 3 2 P1 total 0.222261 0.040518
material group in legendre nuclide mean std. dev.
2 3 1 P0 total 13.561252 21.988396
3 3 1 P1 total 1.176515 0.154807
0 3 2 P0 total -2.459765 6.393743
1 3 2 P1 total 0.222261 0.040518
material delayedgroup group in nuclide mean std. dev.
1 3 1 1 total 0.0 0.0

880
tests/regression_tests/mgxs_library_nuclides/inputs_true.dat
View file

File diff suppressed because it is too large Load diff

2
tests/regression_tests/mgxs_library_nuclides/results_true.dat
View file

@ -1 +1 @@
be71bd208f38ec578b20eae0f0aa3ecd6e2a6215ea007c78c76e327a143ca942ec813022c6c426af1dff2dcc686efd1636d96993505a8771529d85ecaa96ad95
14f7fb2e399a4ad124b25b88dda5104d43cca9192aa1c17261da40bcc0e4394e56781f42f79c90107d0ff6b3e901f034bed09b037670e60b9ac4009b3805e17d