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Shortened nuclide slice block and added docstring to Tally.slice

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This commit is contained in:
Will Boyd 2015-08-02 23:52:36 -07:00
parent 587062ad39
commit 79055493e0
1 changed files with 59 additions and 11 deletions
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70
openmc/tallies.py
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@ -2064,16 +2064,70 @@ class Tally(object):
A new derived tally which is the absolute value of this tally.
"""
new_tally = copy.deepcopy(self)
new_tally._mean = np.abs(new_tally.mean)
return new_tally
def __neg__(self):
"""The negated value of this tally.
Returns
-------
Tally
A new derived tally which is the negated value of this tally.
"""
new_tally = self * -1
return new_tally
def slice(self, scores=[], filters=[], filter_bins=[], nuclides=[]):
"""
def get_slice(self, scores=[], filters=[], filter_bins=[], nuclides=[]):
"""Build a sliced tally for the specified filters, scores and nuclides.
This method constructs a new tally to encapsulate a subset of the data
represented by this tally. The subset of data to included in the tally
slice is determined by the scores, filters and nuclides specified in
the input parameters.
Parameters
----------
scores : list
A list of one or more score strings
(e.g., ['absorption', 'nu-fission']; default is [])
filters : list
A list of filter type strings
(e.g., ['mesh', 'energy']; default is [])
filter_bins : list
A list of the filter bins corresponding to the filter_types
parameter (e.g., [1, (0., 0.625e-6)]; default is []). Each bin in
the list is the integer ID for 'material', 'surface', 'cell',
'cellborn', and 'universe' Filters. Each bin is an integer for the
cell instance ID for 'distribcell Filters. Each bin is a 2-tuple of
floats for 'energy' and 'energyout' filters corresponding to the
energy boundaries of the bin of interest. The bin is a (x,y,z)
3-tuple for 'mesh' filters corresponding to the mesh cell of
interest. The order of the bins in the list must correspond of the
filter_types parameter.
nuclides : list
A list of nuclide name strings
(e.g., ['U-235', 'U-238']; default is [])
Returns
-------
Tally
A new tally which encapsulates the subset of data requested in the
order each filter, nuclide and score is listed in the parameters.
Raises
------
ValueError
When this method is called before the Tally is populated with data
by the StatePoint.read_results() method.
"""
# Ensure that StatePoint.read_results() was called first
@ -2116,15 +2170,9 @@ class Tally(object):
# Determine the nuclide indices from any of the requested nuclides
for nuclide in self.nuclides:
if isinstance(nuclide, Nuclide):
if nuclide.name not in nuclides:
nuclide_index = self.get_nuclide_index(nuclide.name)
nuclide_indices.append(nuclide_index)
else:
if nuclide not in nuclides:
nuclide_index = self.get_nuclide_index(nuclide)
nuclide_indices.append(nuclide_index)
if nuclide.name not in nuclides:
nuclide_index = self.get_nuclide_index(nuclide.name)
nuclide_indices.append(nuclide_index)
# Loop over indices in reverse to remove excluded Nuclides
for nuclide_index in nuclide_indices[::-1]: