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Minor fission yield touch ups

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This commit is contained in:
Andrew Johnson 2020-03-18 20:08:03 -04:00
parent d1878a205e
commit 58b644cd3b
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1 changed files with 2 additions and 4 deletions
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6
openmc/deplete/nuclide.py
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@ -406,9 +406,7 @@ class FissionYieldDistribution(Mapping):
for g_index, energy in enumerate(energies):
prod_map = fission_yields[energy]
for prod_ix, product in enumerate(ordered_prod):
yield_val = prod_map.get(product)
yield_matrix[g_index, prod_ix] = (
0.0 if yield_val is None else yield_val)
yield_matrix[g_index, prod_ix] = prod_map.get(product, 0.0)
self.energies = tuple(energies)
self.products = tuple(ordered_prod)
self.yield_matrix = yield_matrix
@ -444,7 +442,7 @@ class FissionYieldDistribution(Mapping):
FissionYieldDistribution
"""
all_yields = {}
for elem_index, yield_elem in enumerate(element.iter("fission_yields")):
for yield_elem in element.iter("fission_yields"):
energy = float(yield_elem.get("energy"))
products = yield_elem.find("products").text.split()
yields = map(float, yield_elem.find("data").text.split())