armi.physics.neutronics.isotopicDepletion.crossSectionTable module
-Module containing the CrossSectionTable class.
-The CrossSectionTable is useful for performing isotopic depletion analysis by storing one-group -cross sections of interest to such an analysis. This used to live alongside the -isotopicDepletionInterface, but that proved to be an unpleasant coupling between the ARMI composite -model and the physics code contained therein. Separating it out at least means that the composite -model doesn’t need to import the isotopicDepletionInterface to function.
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- -class armi.physics.neutronics.isotopicDepletion.crossSectionTable.CrossSectionTable(*args, **kwargs)[source] -
Bases:
-OrderedDictThis is a set of one group cross sections for use with isotopicDepletion analysis.
-It can also double as a reaction rate table.
-XStable is indexed by nucNames -(nG), (nF), (n2n), (nA), (nP) and (n3n) are expected -the cross sections are returned in barns
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- -rateTypes = ('nG', 'nF', 'n2n', 'nA', 'nP', 'n3n') -
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- -add(nucName, nG=0.0, nF=0.0, n2n=0.0, nA=0.0, nP=0.0, n3n=0.0)[source] -
Add one group cross sections to the table.
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- Parameters: -
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str (nucName -) – nuclide name – e.g. ‘U235’
-float (n3n -) – (n,gamma) cross section in barns
-float – (n,fission) cross section in barns
-float – (n,2n) cross section in barns
-float – (n,alpha) cross section in barns
-float – (n,proton) cross section in barns
-float – (n,3n) cross section in barns
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- -addMultiGroupXS(nucName, microMultiGroupXS, mgFlux, totalFlux=None)[source] -
Perform group collapse to one group cross sections and add to table.
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- Parameters: -
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str (nucName -) – nuclide name – e.g. ‘U235’
-XSCollection (microMultiGroupXS -) – micro cross sections, typically a XSCollection from an ISOTXS
-like (mgFlux - list) – The flux in each energy group
-float (totalFlux -) – The total flux. Optional argument for increased speed if already available.
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- -getXsecTable(headerFormat='$ xsecs for {}', tableFormat='\n{{mcnpId}} {nG:.5e} {nF:.5e} {n2n:.5e} {n3n:.5e} {nA:.5e} {nP:.5e}')[source] -
Make a cross section table for external depletion physics code input decks.
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- Parameters: -
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headerFormat (string (optional)) – This is the format in which the elements of the header with be returned – i.e. if you -use a .format() call with the case name you’ll return a formatted list of strings.
-tableFormat (string (optional)) – This is the format in which the elements of the table with be returned – i.e. if you -use a .format() call with mcnpId, nG, nF, n2n, n3n, nA, and nP you’ll get the format you -want. If you use a .format() call with the case name you’ll return a formatted list of -string elements
-Results –
-------- –
-output (list) – a list of string elements that together make a xsec card
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- -armi.physics.neutronics.isotopicDepletion.crossSectionTable.makeReactionRateTable(obj, nuclides: Optional[List] = None)[source] -
Generate a reaction rate table for given nuclides.
-Often useful in support of depletion.
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- Parameters: -
nuclides (list, optional) – list of nuclide names for which to generate the cross-section table. -If absent, use all nuclides obtained by self.getNuclides().
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--Notes
-This also used to do some caching on the block level but that has been removed -and the calls to this may therefore need to be re-optimized.
---See also
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-armi.physics.neutronics.isotopicDepletion.isotopicDepletionInterface.CrossSectionTable,armi.reactor.composites.Composite.getReactionRates