crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-27 13:45:36 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions

Make materials with actinides depletable by default

Browse source
This commit is contained in:
Paul Romano 2018-03-02 10:57:02 -06:00
parent 0508274a3d
commit f415700c86
1 changed files with 7 additions and 3 deletions
Download patch file Download diff file Expand all files Collapse all files

10
openmc/material.py
View file

@ -88,7 +88,7 @@ class Material(IDManagerMixin):
self.name = name
self.temperature = temperature
self._density = None
self._density_units = ''
self._density_units = 'sum'
self._depletable = False
self._paths = None
self._num_instances = None
@ -397,9 +397,13 @@ class Material(IDManagerMixin):
# If nuclide name doesn't look valid, give a warning
try:
openmc.data.zam(nuclide)
Z, _, _ = openmc.data.zam(nuclide)
except ValueError as e:
warnings.warn(str(e))
else:
# For actinides, have the material be depletable by default
if Z >= 89:
self.depletable = True
self._nuclides.append((nuclide, percent, percent_type))
@ -541,7 +545,7 @@ class Material(IDManagerMixin):
# Add naturally-occuring isotopes
element = openmc.Element(element)
for nuclide in element.expand(percent, percent_type, enrichment):
self._nuclides.append(nuclide)
self.add_nuclide(*nuclide)
def add_s_alpha_beta(self, name, fraction=1.0):
r"""Add an :math:`S(\alpha,\beta)` table to the material