crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-28 22:26:08 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions 5

Merge pull request #1722 from paulromano/element-fix-jeff33

Browse source 
Fix issue with assigning elemental carbon when using JEFF 3.3
This commit is contained in:
Amanda Lund 2020-12-08 10:22:53 -06:00 • committed by GitHub
commit 7cc62d8529
No known key found for this signature in database
GPG key ID: 4AEE18F83AFDEB23
1 changed files with 17 additions and 19 deletions
Download patch file Download diff file Expand all files Collapse all files

36
openmc/element.py
View file

@ -149,30 +149,28 @@ class Element(str):
mutual_nuclides = sorted(list(mutual_nuclides))
absent_nuclides = sorted(list(absent_nuclides))
# If all natural nuclides are present in the library,
# expand element using all natural nuclides
# If all naturally ocurring isotopes are present in the library,
# add them based on their abundance
if len(absent_nuclides) == 0:
for nuclide in mutual_nuclides:
abundances[nuclide] = NATURAL_ABUNDANCE[nuclide]
# If no natural elements are present in the library, check if the
# 0 nuclide is present. If so, set the abundance to 1 for this
# nuclide. Else, raise an error.
elif len(mutual_nuclides) == 0:
nuclide_0 = self + '0'
if nuclide_0 in library_nuclides:
abundances[nuclide_0] = 1.0
else:
msg = 'Unable to expand element {0} because the cross '\
'section library provided does not contain any of '\
'the natural isotopes for that element.'\
.format(self)
raise ValueError(msg)
# If some naturally occurring isotopes are not present in the
# library, check if the "natural" nuclide (e.g., C0) is present. If
# so, set the abundance to 1 for this nuclide.
elif (self + '0') in library_nuclides:
abundances[self + '0'] = 1.0
# If some, but not all, natural nuclides are in the library, add
# the mutual nuclides. For the absent nuclides, add them based on
# our knowledge of the common cross section libraries
# (ENDF, JEFF, and JENDL)
elif len(mutual_nuclides) == 0:
msg = ('Unable to expand element {} because the cross '
'section library provided does not contain any of '
'the natural isotopes for that element.'
.format(self))
raise ValueError(msg)
# If some naturally occurring isotopes are in the library, add them.
# For the absent nuclides, add them based on our knowledge of the
# common cross section libraries (ENDF, JEFF, and JENDL)
else:
# Add the mutual isotopes
for nuclide in mutual_nuclides: