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Add nuclides and elements properties on openmc.Material

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This commit is contained in:
Paul Romano 2016-05-04 11:32:23 -06:00
parent 879728ea5d
commit 7eae7a629d
1 changed files with 16 additions and 0 deletions
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16
openmc/material.py
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@ -50,6 +50,14 @@ class Material(object):
Units used for `density`. Can be one of 'g/cm3', 'g/cc', 'kg/cm3',
'atom/b-cm', 'atom/cm3', 'sum', or 'macro'. The 'macro' unit only
applies in the case of a multi-group calculation.
elements : collections.OrderedDict
Dictionary whose keys are element names and values are 3-tuples
consisting of an :class:`openmc.Element` instance, the percent density,
and the percent type (atom or weight fraction).
nuclides : collections.OrderedDict
Dictionary whose keys are nuclide names and values are 3-tuples
consisting of an :class:`openmc.Nuclide` instance, the percent density,
and the percent type (atom or weight fraction).
"""
@ -187,6 +195,14 @@ class Material(object):
def density_units(self):
return self._density_units
@property
def elements(self):
return self._elements
@property
def nuclides(self):
return self._nuclides
@property
def convert_to_distrib_comps(self):
return self._convert_to_distrib_comps