mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-28 14:15:42 -04:00
fixed formatting of python api created mgxs library, added example pincell_multigroup to xml folder, and removed c5g7 as that will be pushed to benchmarks instead once this is complete.
This commit is contained in:
Adam Nelson
parent
5e788cdffb
commit
5965e92e46
20 changed files with 47 additions and 529 deletions
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@ -1,12 +0,0 @@
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<?xml version="1.0"?>
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||||
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||||
<cmfd>
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||||
<begin>10</begin>
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<feedback>true</feedback>
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<mesh>
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<lower_left> 0.0 0.0 -100.0</lower_left>
|
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<albedo>1 0 0 1 1 1</albedo>
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</mesh>
|
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</cmfd>
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|
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@ -1,118 +0,0 @@
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<geometry>
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@ -1 +0,0 @@
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/home/nelsonag/cases/c5g7/materials.xml
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@ -1,29 +0,0 @@
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<?xml version="1.0"?>
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<plots>
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<plot>
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<id>1</id>
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<filename>mat</filename>
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<color>material</color>
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<origin>32.13 32.13 0</origin>
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<width>64.26 64.26</width>
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<type>slice</type>
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<pixels>1000 1000 </pixels>
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<!-- <col_spec id="1" rgb="255 0 0" />
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<col_spec id="3" rgb="0 255 0" />
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<col_spec id="4" rgb="0 0 255" />
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-->
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</plot>
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<plot>
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<id>2</id>
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<filename>cell</filename>
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<color>cell</color>
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<origin>32.13 32.13 0</origin>
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<width>64.26 64.26</width>
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<type>slice</type>
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<pixels>1000 1000 </pixels>
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</plot>
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</plots>
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@ -1,44 +0,0 @@
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<?xml version="1.0"?>
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<settings>
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<energy_mode>multi-group</energy_mode>
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<!--
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Define how many particles to run and for how many batches
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in an eigenvalue calculation mode
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-->
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<eigenvalue>
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<batches>2000</batches>
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<inactive>500</inactive>
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<particles>10000</particles>
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</eigenvalue>
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<!--
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Start with uniformally distributed neutron source
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with the default energy spectrum of a Maxwellian
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and isotropic distribution.
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-->
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<source>
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<space type="box">
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<parameters>
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0.0 21.42 -100
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42.84 64.26 100
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</parameters>
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</space>
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</source>
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<!-- Establish statepoints to aid in examining convergence -->
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<state_point>
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<interval> 2000 </interval>
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<source_write>true</source_write>
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</state_point>
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<output>
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<cross_sections>true</cross_sections>
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<summary>true</summary>
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<tallies>true</tallies>
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</output>
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<run_cmfd>true</run_cmfd>
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<cross_sections>../data.xml</cross_sections>
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</settings>
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@ -1,25 +0,0 @@
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<?xml version="1.0"?>
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<tallies>
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<tally id="1">
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<filter type="mesh" bins="1" />
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<filter type="energy" />
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<scores>flux</scores>
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</tally>
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<tally id="2">
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<filter type="mesh" bins="1"/>
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<scores>fission</scores>
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</tally>
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<mesh>
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<id>1</id>
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<type>regular</type>
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<lower_left> 0.0 0.0 -100.0 </lower_left>
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<upper_right> 64.26 64.26 100.0 </upper_right>
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<dimension> 51 51 1 </dimension>
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</mesh>
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<assume_separate>false</assume_separate>
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</tallies>
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@ -1,138 +0,0 @@
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<geometry>
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<pitch>1.26 1.26</pitch>
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|
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|
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 1 6 1 1 1 1 1 1 1 1 1 6 1 1 1
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|
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|
||||
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|
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|
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|
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|
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|
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|
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2 3 3 4 4 4 4 4 4 4 4 4 4 4 3 3 2
|
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|
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|
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|
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|
||||
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|
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|
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|
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<cell id="199" material="void" universe="199" /><cell id="202" material="void" universe="202" /></geometry>
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||||
|
|
@ -1 +0,0 @@
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../materials.xml
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@ -1,42 +0,0 @@
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<?xml version="1.0"?>
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<plots>
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|
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<plot>
|
||||
<id>1</id>
|
||||
<filename>mat</filename>
|
||||
<color>material</color>
|
||||
<origin>32.13 32.13 107.1</origin>
|
||||
<width>64.26 214.2</width>
|
||||
<type>slice</type>
|
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<pixels>1000 1000 </pixels>
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<!-- <col_spec id="1" rgb="255 0 0" />
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<col_spec id="2" rgb="0 0 0" />
|
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<col_spec id="3" rgb="0 255 0" />
|
||||
<col_spec id="4" rgb="0 0 255" />
|
||||
-->
|
||||
<basis>xz</basis>
|
||||
</plot>
|
||||
|
||||
<plot>
|
||||
<id>2</id>
|
||||
<filename>cell</filename>
|
||||
<color>cell</color>
|
||||
<origin>32.13 32.13 107.1</origin>
|
||||
<width>64.26 214.2</width>
|
||||
<type>slice</type>
|
||||
<pixels>1000 1000 </pixels>
|
||||
<basis>xz</basis>
|
||||
</plot>
|
||||
|
||||
<plot>
|
||||
<id>3</id>
|
||||
<filename>mat_xy</filename>
|
||||
<color>material</color>
|
||||
<origin>32.13 32.13 107.1</origin>
|
||||
<width>64.26 64.26</width>
|
||||
<type>slice</type>
|
||||
<pixels>1000 1000 </pixels>
|
||||
<basis>xy</basis>
|
||||
</plot>
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||||
|
||||
</plots>
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|
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@ -1,47 +0,0 @@
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<?xml version="1.0"?>
|
||||
<settings>
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||||
<energy_mode>multi-group</energy_mode>
|
||||
<!--
|
||||
Define how many particles to run and for how many batches
|
||||
in an eigenvalue calculation mode
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||||
-->
|
||||
<eigenvalue>
|
||||
<batches>2000</batches>
|
||||
<inactive>500</inactive>
|
||||
<particles>1000</particles>
|
||||
</eigenvalue>
|
||||
|
||||
<uniform_fs>
|
||||
<lower_left> 0.0 21.42 0.0 </lower_left>
|
||||
<upper_right> 42.84 64.26 192.78 </upper_right>
|
||||
<dimension> 34 34 54 </dimension>
|
||||
</uniform_fs>
|
||||
|
||||
<!--
|
||||
Start with uniformally distributed neutron source
|
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with the default energy spectrum of a Maxwellian
|
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and isotropic distribution.
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-->
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||||
<source>
|
||||
<space type="box">
|
||||
<parameters>
|
||||
0.0 21.42 0.0
|
||||
42.84 64.26 192.78
|
||||
</parameters>
|
||||
</space>
|
||||
</source>
|
||||
|
||||
<!-- Establish statepoints -->
|
||||
<state_point>
|
||||
<interval>2000</interval>
|
||||
</state_point>
|
||||
|
||||
<output>
|
||||
<cross_sections>true</cross_sections>
|
||||
<summary>true</summary>
|
||||
<tallies>true</tallies>
|
||||
</output>
|
||||
|
||||
<cross_sections>../data.xml</cross_sections>
|
||||
|
||||
</settings>
|
||||
|
|
@ -1,33 +0,0 @@
|
|||
<?xml version="1.0"?>
|
||||
<tallies>
|
||||
|
||||
<tally id="1">
|
||||
<filter type="mesh" bins="1" />
|
||||
<filter type="energy" />
|
||||
<scores>flux</scores>
|
||||
</tally>
|
||||
|
||||
<tally id="2">
|
||||
<filter type="mesh" bins="2"/>
|
||||
<scores>fission</scores>
|
||||
</tally>
|
||||
|
||||
<mesh>
|
||||
<id>1</id>
|
||||
<type>rectangular</type>
|
||||
<lower_left> 0.0 0.0 0.0 </lower_left>
|
||||
<upper_right> 64.26 64.26 214.2 </upper_right>
|
||||
<dimension> 51 51 60 </dimension>
|
||||
</mesh>
|
||||
|
||||
<mesh>
|
||||
<id>2</id>
|
||||
<type>rectangular</type>
|
||||
<lower_left> 0.0 21.42 0.0 </lower_left>
|
||||
<upper_right> 42.84 64.26 192.78 </upper_right>
|
||||
<dimension> 34 34 54 </dimension>
|
||||
</mesh>
|
||||
|
||||
<assume_separate>false</assume_separate>
|
||||
|
||||
</tallies>
|
||||
|
|
@ -1 +0,0 @@
|
|||
/home/nelsonag/cases/c5g7/materials.xml
|
||||
|
|
@ -1,16 +0,0 @@
|
|||
<?xml version="1.0"?>
|
||||
<tallies>
|
||||
|
||||
<tally id="1">
|
||||
<filter type="cell" bins="1 2" />
|
||||
<filter type="energy" />
|
||||
<scores>flux</scores>
|
||||
</tally>
|
||||
|
||||
<tally id="2">
|
||||
<filter type="energy" />
|
||||
<filter type="energyout" />
|
||||
<scores>scatter</scores>
|
||||
</tally>
|
||||
|
||||
</tallies>
|
||||
|
|
@ -41,6 +41,6 @@
|
|||
|
||||
<survival_biasing>false</survival_biasing>
|
||||
|
||||
<cross_sections>../data.xml</cross_sections>
|
||||
<cross_sections>./mg_cross_sections.xml</cross_sections>
|
||||
|
||||
</settings>
|
||||
13
examples/xml/pincell_multigroup/tallies.xml
Normal file
13
examples/xml/pincell_multigroup/tallies.xml
Normal file
|
|
@ -0,0 +1,13 @@
|
|||
<?xml version="1.0"?>
|
||||
<tallies>
|
||||
<mesh id="1" type="regular">
|
||||
<dimension>100 100 1</dimension>
|
||||
<lower_left>-0.63 -0.63 -1e+50</lower_left>
|
||||
<upper_right>0.63 0.63 1e+50</upper_right>
|
||||
</mesh>
|
||||
<tally id="1" name="tally 1">
|
||||
<filter type="energy" />
|
||||
<filter bins="1" type="mesh" />
|
||||
<scores>flux fission nu-fission</scores>
|
||||
</tally>
|
||||
</tallies>
|
||||
|
|
@ -24,37 +24,49 @@ def ndarray_to_string(arr):
|
|||
|
||||
shape = arr.shape
|
||||
ndim = arr.ndim
|
||||
text = ''
|
||||
tab = ' '
|
||||
indent = '\n' + tab + tab
|
||||
text = indent
|
||||
|
||||
if ndim == 1:
|
||||
text += ' '.join(map(str, arr[:]))
|
||||
text += tab
|
||||
for i in range(shape[0]):
|
||||
text += '{:.7E} '.format(arr[i])
|
||||
text += indent
|
||||
elif ndim == 2:
|
||||
for i in xrange(shape[0]):
|
||||
text += ' '.join(map(str, arr[i,:]))
|
||||
text += '\n'
|
||||
for i in range(shape[0]):
|
||||
text += tab
|
||||
for j in range(shape[1]):
|
||||
text += '{:.7E} '.format(arr[i,j])
|
||||
text += indent
|
||||
elif ndim == 3:
|
||||
for i in xrange(shape[0]):
|
||||
for j in xrange(shape[1]):
|
||||
text += ' '.join(map(str, arr[i,j,:]))
|
||||
text += '\n'
|
||||
for i in range(shape[0]):
|
||||
for j in range(shape[1]):
|
||||
text += tab
|
||||
for k in range(shape[2]):
|
||||
text += '{:.7E} '.format(arr[i,j,k])
|
||||
text += indent
|
||||
elif ndim == 4:
|
||||
for i in xrange(shape[0]):
|
||||
for j in xrange(shape[1]):
|
||||
for k in xrange(shape[2]):
|
||||
text += ' '.join(map(str, arr[i,j,k,:]))
|
||||
text += '\n'
|
||||
for i in range(shape[0]):
|
||||
for j in range(shape[1]):
|
||||
for k in range(shape[2]):
|
||||
text += tab
|
||||
for l in range(shape[3]):
|
||||
text += '{:.7E} '.format(arr[i,j,k,l])
|
||||
text += indent
|
||||
elif ndim == 5:
|
||||
for i in xrange(shape[0]):
|
||||
for j in xrange(shape[1]):
|
||||
for k in xrange(shape[2]):
|
||||
for l in xrange(shape[3]):
|
||||
text += ' '.join(map(str, arr[i,j,k,l,:]))
|
||||
text += '\n'
|
||||
for i in range(shape[0]):
|
||||
for j in range(shape[1]):
|
||||
for k in range(shape[2]):
|
||||
for l in range(shape[3]):
|
||||
text += tab
|
||||
for m in range(shape[4]):
|
||||
text += '{:.7E} '.format(arr[i,j,k,l,m])
|
||||
text += indent
|
||||
|
||||
return text
|
||||
|
||||
|
||||
|
||||
class Xsdata(object):
|
||||
"""A multi-group cross section data set (xsdata) providing all the
|
||||
multi-group data necessary for a multi-group OpenMC calculation.
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue