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Removed old FIXME comment tags from tallies.py

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wbinventor@gmail.com 2016-02-11 17:17:36 -05:00
parent baad8a998a
commit e40fd13d80
6 changed files with 433 additions and 7 deletions
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8
openmc/tallies.py
View file

@ -887,7 +887,7 @@ class Tally(object):
# Create deep copy of other tally to use for array concatenation
other_copy = copy.deepcopy(other)
# FIXME: document and create vars for merge_filters, etc.
# Identify if filters, nuclides and scores are mergeable and/or equal
merge_filters = self._can_merge_filters(other)
merge_nuclides = self._can_merge_nuclides(other)
merge_scores = self._can_merge_scores(other)
@ -2224,8 +2224,6 @@ class Tally(object):
else:
filter2_bins = [filter2.get_bin(i) for i in range(filter2.num_bins)]
# FIXME: Why doesn't this swap data for sum and sum_sq???
# Adjust the mean data array to relect the new filter order
if self.mean is not None:
for bin1, bin2 in itertools.product(filter1_bins, filter2_bins):
@ -2297,8 +2295,6 @@ class Tally(object):
self.nuclides[nuclide1_index] = nuclide2
self.nuclides[nuclide2_index] = nuclide1
# FIXME: Why doesn't this swap data for sum and sum_sq???
# Adjust the mean data array to relect the new nuclide order
if self.mean is not None:
nuclide1_mean = self.mean[:, nuclide1_index, :].copy()
@ -2371,8 +2367,6 @@ class Tally(object):
self.scores[score1_index] = score2
self.scores[score2_index] = score1
# FIXME: Why doesn't this swap data for sum and sum_sq???
# Adjust the mean data array to relect the new nuclide order
if self.mean is not None:
score1_mean = self.mean[:, :, score1_index].copy()

148
tests/test_tally_arithmetic/geometry.xml Normal file
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@ -0,0 +1,148 @@
<?xml version='1.0' encoding='utf-8'?>
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<cell id="9" material="9" region="(((6 -7) 32) -38)" universe="0" />
<lattice id="100" name="Fuel assembly (lower half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
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1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 </universes>
</lattice>
<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
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3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
</lattice>
<lattice id="200" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
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</lattice>
<lattice id="201" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
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</lattice>
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</geometry>

1
tests/test_tally_arithmetic/inputs_test.dat Normal file
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@ -0,0 +1 @@
57384883e37964076aa82c19fa542434331cdb09735d710485b5aa0ca3445d543729e40cb9c7b6a70e7101ef186923eb1ff6315c73b01ff257052838add68fc7

246
tests/test_tally_arithmetic/materials.xml Normal file
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@ -0,0 +1,246 @@
<?xml version='1.0' encoding='utf-8'?>
<materials>
<default_xs>71c</default_xs>
<material id="1" name="Fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U-234" />
<nuclide ao="0.00048218" name="U-235" />
<nuclide ao="9.0402e-05" name="U-236" />
<nuclide ao="0.021504" name="U-238" />
<nuclide ao="7.3733e-06" name="Np-237" />
<nuclide ao="1.5148e-06" name="Pu-238" />
<nuclide ao="0.00013955" name="Pu-239" />
<nuclide ao="3.4405e-05" name="Pu-240" />
<nuclide ao="2.1439e-05" name="Pu-241" />
<nuclide ao="3.7422e-06" name="Pu-242" />
<nuclide ao="4.5041e-07" name="Am-241" />
<nuclide ao="9.2301e-09" name="Am-242m" />
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<nuclide ao="1.0485e-07" name="Cm-242" />
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<nuclide ao="8.8756e-08" name="Cm-244" />
<nuclide ao="3.5285e-09" name="Cm-245" />
<nuclide ao="2.6497e-05" name="Mo-95" />
<nuclide ao="3.2772e-05" name="Tc-99" />
<nuclide ao="3.0742e-05" name="Ru-101" />
<nuclide ao="2.3505e-06" name="Ru-103" />
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<nuclide ao="1.5369e-09" name="Gd-155" />
<nuclide ao="0.045737" name="O-16" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H-1" wo="0.035887" />
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<nuclide name="Ni-61" wo="0.000722605975" />
<nuclide name="Ni-62" wo="0.002342513875" />
<nuclide name="Ni-64" wo="0.0006157116" />
<nuclide name="Mn-55" wo="0.0135739" />
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<nuclide name="Si-29" wo="0.000328078746" />
<nuclide name="Si-30" wo="0.0002239677" />
<nuclide name="Cr-50" wo="0.005382452306" />
<nuclide name="Cr-52" wo="0.107931450781" />
<nuclide name="Cr-53" wo="0.012474806806" />
<nuclide name="Cr-54" wo="0.003163190107" />
<sab name="HH2O" xs="71t" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H-1" wo="0.0162913" />
<nuclide name="O-16" wo="0.1292776" />
<nuclide name="B-10" wo="5.25228e-05" />
<nuclide name="B-11" wo="0.000239272" />
<nuclide name="Zr-90" wo="0.43313403903" />
<nuclide name="Zr-91" wo="0.09549277374" />
<nuclide name="Zr-92" wo="0.14759527104" />
<nuclide name="Zr-94" wo="0.15280552077" />
<nuclide name="Zr-96" wo="0.02511169542" />
<sab name="HH2O" xs="71t" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H-1" wo="0.0292856" />
<nuclide name="O-16" wo="0.2323919" />
<nuclide name="B-10" wo="9.44159e-05" />
<nuclide name="B-11" wo="0.00043012" />
<nuclide name="Zr-90" wo="0.3741373658" />
<nuclide name="Zr-91" wo="0.0824858164" />
<nuclide name="Zr-92" wo="0.1274914944" />
<nuclide name="Zr-94" wo="0.1319920622" />
<nuclide name="Zr-96" wo="0.0216912612" />
<sab name="HH2O" xs="71t" />
</material>
<material id="2" name="Cladding">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr-90" />
<nuclide ao="0.1122" name="Zr-91" />
<nuclide ao="0.1715" name="Zr-92" />
<nuclide ao="0.1738" name="Zr-94" />
<nuclide ao="0.028" name="Zr-96" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H-1" />
<nuclide ao="1.0" name="O-16" />
<nuclide ao="0.000649" name="B-10" />
<nuclide ao="0.002689" name="B-11" />
<sab name="HH2O" xs="71t" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H-1" />
<nuclide ao="1.0" name="O-16" />
<nuclide ao="0.000649" name="B-10" />
<nuclide ao="0.002689" name="B-11" />
<sab name="HH2O" xs="71t" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe-54" wo="0.05437098" />
<nuclide name="Fe-56" wo="0.88500663" />
<nuclide name="Fe-57" wo="0.0208008" />
<nuclide name="Fe-58" wo="0.00282159" />
<nuclide name="Ni-58" wo="0.0067198" />
<nuclide name="Ni-60" wo="0.0026776" />
<nuclide name="Ni-61" wo="0.0001183" />
<nuclide name="Ni-62" wo="0.0003835" />
<nuclide name="Ni-64" wo="0.0001008" />
<nuclide name="Mn-55" wo="0.01" />
<nuclide name="Mo-92" wo="0.000849" />
<nuclide name="Mo-94" wo="0.0005418" />
<nuclide name="Mo-95" wo="0.0009438" />
<nuclide name="Mo-96" wo="0.0010002" />
<nuclide name="Mo-97" wo="0.0005796" />
<nuclide name="Mo-98" wo="0.0014814" />
<nuclide name="Mo-100" wo="0.0006042" />
<nuclide name="Si-28" wo="0.00367464" />
<nuclide name="Si-29" wo="0.00019336" />
<nuclide name="Si-30" wo="0.000132" />
<nuclide name="Cr-50" wo="0.00010435" />
<nuclide name="Cr-52" wo="0.002092475" />
<nuclide name="Cr-53" wo="0.00024185" />
<nuclide name="Cr-54" wo="6.1325e-05" />
<nuclide name="C-Nat" wo="0.0025" />
<nuclide name="Cu-63" wo="0.0013696" />
<nuclide name="Cu-65" wo="0.0006304" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H-1" wo="0.0095661" />
<nuclide name="O-16" wo="0.0759107" />
<nuclide name="B-10" wo="3.08409e-05" />
<nuclide name="B-11" wo="0.000140499" />
<nuclide name="Fe-54" wo="0.035620772088" />
<nuclide name="Fe-56" wo="0.579805982228" />
<nuclide name="Fe-57" wo="0.01362750048" />
<nuclide name="Fe-58" wo="0.001848545204" />
<nuclide name="Ni-58" wo="0.055298376566" />
<nuclide name="Ni-60" wo="0.022034425592" />
<nuclide name="Ni-61" wo="0.000973510811" />
<nuclide name="Ni-62" wo="0.003155886695" />
<nuclide name="Ni-64" wo="0.000829500336" />
<nuclide name="Mn-55" wo="0.018287" />
<nuclide name="Si-28" wo="0.00839976771" />
<nuclide name="Si-29" wo="0.00044199679" />
<nuclide name="Si-30" wo="0.0003017355" />
<nuclide name="Cr-50" wo="0.007251360806" />
<nuclide name="Cr-52" wo="0.145407678031" />
<nuclide name="Cr-53" wo="0.016806340306" />
<nuclide name="Cr-54" wo="0.004261520857" />
<sab name="HH2O" xs="71t" />
</material>
<material id="7" name="Upper radial reflector /Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H-1" wo="0.0086117" />
<nuclide name="O-16" wo="0.0683369" />
<nuclide name="B-10" wo="2.77638e-05" />
<nuclide name="B-11" wo="0.000126481" />
<nuclide name="Fe-54" wo="0.035953677186" />
<nuclide name="Fe-56" wo="0.585224740891" />
<nuclide name="Fe-57" wo="0.01375486056" />
<nuclide name="Fe-58" wo="0.001865821363" />
<nuclide name="Ni-58" wo="0.055815129186" />
<nuclide name="Ni-60" wo="0.022240333032" />
<nuclide name="Ni-61" wo="0.000982608081" />
<nuclide name="Ni-62" wo="0.003185377845" />
<nuclide name="Ni-64" wo="0.000837251856" />
<nuclide name="Mn-55" wo="0.0184579" />
<nuclide name="Si-28" wo="0.00847831314" />
<nuclide name="Si-29" wo="0.00044612986" />
<nuclide name="Si-30" wo="0.000304557" />
<nuclide name="Cr-50" wo="0.00731912987" />
<nuclide name="Cr-52" wo="0.146766614995" />
<nuclide name="Cr-53" wo="0.01696340737" />
<nuclide name="Cr-54" wo="0.004301347765" />
<sab name="HH2O" xs="71t" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H-1" wo="0.0011505" />
<nuclide name="O-16" wo="0.0091296" />
<nuclide name="B-10" wo="3.70915e-06" />
<nuclide name="B-11" wo="1.68974e-05" />
<nuclide name="Fe-54" wo="0.03855611055" />
<nuclide name="Fe-56" wo="0.627585036425" />
<nuclide name="Fe-57" wo="0.014750478" />
<nuclide name="Fe-58" wo="0.002000875025" />
<nuclide name="Ni-58" wo="0.059855207342" />
<nuclide name="Ni-60" wo="0.023850159704" />
<nuclide name="Ni-61" wo="0.001053732407" />
<nuclide name="Ni-62" wo="0.003415945715" />
<nuclide name="Ni-64" wo="0.000897854832" />
<nuclide name="Mn-55" wo="0.019794" />
<nuclide name="Si-28" wo="0.00909197802" />
<nuclide name="Si-29" wo="0.00047842098" />
<nuclide name="Si-30" wo="0.000326601" />
<nuclide name="Cr-50" wo="0.007848910646" />
<nuclide name="Cr-52" wo="0.157390026871" />
<nuclide name="Cr-53" wo="0.018191270146" />
<nuclide name="Cr-54" wo="0.004612692337" />
<sab name="HH2O" xs="71t" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H-1" wo="0.0245014" />
<nuclide name="O-16" wo="0.1944274" />
<nuclide name="B-10" wo="7.89917e-05" />
<nuclide name="B-11" wo="0.000359854" />
<nuclide name="Fe-54" wo="0.030411411144" />
<nuclide name="Fe-56" wo="0.495012237964" />
<nuclide name="Fe-57" wo="0.01163454624" />
<nuclide name="Fe-58" wo="0.001578204652" />
<nuclide name="Ni-58" wo="0.047211231662" />
<nuclide name="Ni-60" wo="0.018811987544" />
<nuclide name="Ni-61" wo="0.000831139127" />
<nuclide name="Ni-62" wo="0.002694352115" />
<nuclide name="Ni-64" wo="0.000708189552" />
<nuclide name="Mn-55" wo="0.0156126" />
<nuclide name="Si-28" wo="0.007171335558" />
<nuclide name="Si-29" wo="0.000377356542" />
<nuclide name="Si-30" wo="0.0002576079" />
<nuclide name="Cr-50" wo="0.006190885148" />
<nuclide name="Cr-52" wo="0.124142524198" />
<nuclide name="Cr-53" wo="0.014348496148" />
<nuclide name="Cr-54" wo="0.003638294506" />
<sab name="HH2O" xs="71t" />
</material>
</materials>

16
tests/test_tally_arithmetic/settings.xml Normal file
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<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
</eigenvalue>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
<output>
<summary>true</summary>
</output>
</settings>

21
tests/test_tally_arithmetic/tallies.xml Normal file
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<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1" type="regular">
<dimension>2 2 2</dimension>
<lower_left>-160.0 -160.0 -183.0</lower_left>
<upper_right>160.0 160.0 183.0</upper_right>
</mesh>
<tally id="10000" name="tally 1">
<filter bins="1 3" type="material" />
<filter bins="0.0 2.53e-07 0.001 1.0 20.0" type="energy" />
<filter bins="60" type="distribcell" />
<nuclides>U-235 Pu-239</nuclides>
<scores>nu-fission total</scores>
</tally>
<tally id="10001" name="tally 2">
<filter bins="0.0 2.53e-07 0.001 1.0 20.0" type="energy" />
<filter bins="1" type="mesh" />
<nuclides>U-238 U-235</nuclides>
<scores>total fission</scores>
</tally>
</tallies>