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Modifications to support new function routine

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This commit is contained in:
Adam Nelson 2016-11-08 20:29:33 -05:00
parent 9eb73d8bfe
commit 8de82dcbd3
1 changed files with 14 additions and 15 deletions
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29
openmc/material.py
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@ -46,11 +46,10 @@ _PLOT_TYPES_MT = {'total': (1,), 'scatter': (1, 27), 'elastic': (2,),
'unity': (0,)}
# Operations to use when combining MTs the first np.add is used in reference
# to zero
_PLOT_TYPES_OP = {'total': (np.add,), 'scatter': (np.add, np.subtract),
'elastic': (np.add,),
'inelastic': (np.add, np.subtract, np.subtract),
'fission': (np.add,), 'absorption': (np.add,),
'capture': (np.add,), 'nu-fission': (np.add,),
_PLOT_TYPES_OP = {'total': (), 'scatter': (np.subtract,), 'elastic': (),
'inelastic': (np.subtract, np.subtract),
'fission': (), 'absorption': (),
'capture': (), 'nu-fission': (),
'nu-scatter': (np.add, np.add, np.add, np.add, np.add,
np.add, np.add, np.add, np.add, np.add,
np.add, np.add, np.add, np.add, np.add,
@ -62,9 +61,8 @@ _PLOT_TYPES_OP = {'total': (np.add,), 'scatter': (np.add, np.subtract),
np.add, np.add, np.add, np.add, np.add,
np.add, np.add, np.add, np.add, np.add,
np.add, np.add, np.add, np.add, np.add,
np.add, np.add, np.add, np.add, np.add,
np.add),
'unity': (np.add,)}
np.add, np.add, np.add, np.add, np.add),
'unity': ()}
# Whether or not to multiply the reaction by the yield as well
_PLOT_TYPES_YIELD = {'total': (False,), 'scatter': (False, False),
'elastic': (False,), 'inelastic': (False, False, False),
@ -656,6 +654,8 @@ class Material(object):
"""
import scipy.constants as sc
cv.check_type('library', library, openmc.data.DataLibrary)
# Expand elements in to nuclides
@ -698,7 +698,7 @@ class Material(object):
n = -1
for nuclide in nuclides.items():
n += 1
lib = library[nuclide[0]]
lib = library.get_by_materials(nuclide[0])
if lib is not None:
nuc = openmc.data.IncidentNeutron.from_hdf5(lib['path'])
awrs.append(nuc.atomic_weight_ratio)
@ -878,9 +878,9 @@ class Material(object):
for sab_name in self._sab:
sab = openmc.data.ThermalScattering.from_hdf5(
library[sab_name]['path'])
library.get_by_materials(sab_name)['path'])
for nuc in sab.nuclides:
sabs[nuc] = library[sab_name]['path']
sabs[nuc] = library.get_by_materials(sab_name)['path']
# Now we can create the data sets to be plotted
xs = []
@ -888,7 +888,7 @@ class Material(object):
n = -1
for nuclide in nuclides.items():
n += 1
lib = library[nuclide[0]]
lib = library.get_by_materials(nuclide[0])
if lib is not None:
nuc = openmc.data.IncidentNeutron.from_hdf5(lib['path'])
# Obtain the nearest temperature
@ -974,7 +974,7 @@ class Material(object):
prod.emission_mode == 'total':
func = openmc.data.Combination(
[nuc[mt].xs[nucT], prod.yield_],
[np.add, np.multiply])
[np.multiply])
funcs.append(func)
found_it = True
break
@ -984,8 +984,7 @@ class Material(object):
prod.emission_mode == 'prompt':
func = openmc.data.Combination(
[nuc[mt].xs[nucT],
prod.yield_],
[np.add, np.multiply])
prod.yield_], [np.multiply])
funcs.append(func)
found_it = True
break