def makeXsecTable(
compositeName,
xsType,
mgFlux,
isotxs,
headerFormat="$ xsecs for {}",
tableFormat="\n{mcnpId} {nG:.5e} {nF:.5e} {n2n:.5e} {n3n:.5e} {nA:.5e} {nP:.5e}",
):
"""
Make a cross section table for depletion physics input decks.
Parameters
----------
armiObject: armiObject
an armi object -- batch or block --
with a .p.xsType and a getMgFlux method
activeNuclides: list
a list of the nucNames of active isotopes
isotxs: isotxs object
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 string elements
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
See Also
--------
crossSectionTable.makeCrossSectionTable
Makes a table for arbitrary ArmiObjects
"""
xsTable = CrossSectionTable()
if not xsType or not sum(mgFlux) > 0:
return []
xsTable.setName(compositeName)
totalFlux = sum(mgFlux)
for nucLabel, nuc in isotxs.items():
if xsType != xsLibraries.getSuffixFromNuclideLabel(nucLabel):
continue
nucName = nuc.name
nb = nuclideBases.byName[nucName]
if isinstance(
nb, (nuclideBases.LumpNuclideBase, nuclideBases.DummyNuclideBase)
):
continue
microMultiGroupXS = isotxs[nucLabel].micros
if not isinstance(nb, nuclideBases.NaturalNuclideBase):
xsTable.addMultiGroupXS(nucName, microMultiGroupXS, mgFlux, totalFlux)
return xsTable.getXsecTable(headerFormat=headerFormat, tableFormat=tableFormat)
def __init__(self, xsCollection, xsCollectionKey):
nuclideBases.NuclideWrapper.__init__(self, xsCollection, xsCollectionKey)
self.xsId = xsLibraries.getSuffixFromNuclideLabel(xsCollectionKey)
self.source = 0.0
# 2D record... nucNames
# 4D record
self.isotxsMetadata = nuclearFileMetadata.NuclideMetadata()
self.gamisoMetadata = nuclearFileMetadata.NuclideMetadata()
self.pmatrxMetadata = nuclearFileMetadata.NuclideMetadata()
# 5D and 7D records
self.micros = xsCollections.XSCollection(parent=self)
self.gammaXS = xsCollections.XSCollection(parent=self)
self.neutronHeating = None
self.neutronDamage = None
self.gammaHeating = None
self.isotropicProduction = None
self.linearAnisotropicProduction = None
self.nOrderProductionMatrix = {}
XSNuclide._ensuredBurnInfo = False
