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Whoops, improperly weighted the data

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This commit is contained in:
Adam Nelson 2016-11-21 20:35:06 -05:00
parent 20ce145e36
commit 42baabd155
1 changed files with 8 additions and 7 deletions
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15
openmc/plotter.py
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@ -374,6 +374,8 @@ def _calculate_xs_nuclide(this, types, temperature=294., sab_name=None,
funcs.append(nuc[mt].xs[nucT])
elif mt in nuc:
if yields[i]:
# Get the total yield first if available. This will be
# used primarily for fission.
for prod in chain(nuc[mt].products,
nuc[mt].derived_products):
if prod.particle == 'neutron' and \
@ -385,7 +387,8 @@ def _calculate_xs_nuclide(this, types, temperature=294., sab_name=None,
break
else:
# Total doesn't exist so we have to create from
# prompt and delayed
# prompt and delayed. This is used for scatter
# multiplication.
func = None
for prod in chain(nuc[mt].products,
nuc[mt].derived_products):
@ -393,14 +396,12 @@ def _calculate_xs_nuclide(this, types, temperature=294., sab_name=None,
prod.emission_mode != 'total':
if func:
func = openmc.data.Combination(
[nuc[mt].xs[nucT], prod.yield_,
func], [np.multiply, np.add])
[prod.yield_, func], [np.add])
else:
func = openmc.data.Combination(
[nuc[mt].xs[nucT], prod.yield_],
[np.multiply])
func = prod.yield_
if func:
funcs.append(func)
funcs.append(openmc.data.Combination(
[func, nuc[mt].xs[nucT]], [np.multiply]))
else:
# If func is still None, then there were no
# products. In that case, assume the yield is