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Fixed He4 and H3 issue where temperatures were not being added. This was due to an issue where when the different temperatures were reading the absorption xs from ACE, it was being stored even if it was a 0. array. At the same time, the base h5 file was read by from_hdf5 which never had the derived absorption xs created for these nuclides

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This commit is contained in:
Adam Nelson 2016-09-02 17:12:43 -04:00
parent b56ceaa0f6
commit c4744ec638
1 changed files with 7 additions and 6 deletions
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13
openmc/data/neutron.py
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@ -472,8 +472,8 @@ class IncidentNeutron(EqualityMixin):
tgroup = group['total_nu']
rx.derived_products.append(Product.from_hdf5(tgroup))
# Build summed reactions. Start from the highest MT number because high
# MTs never depend on lower MTs.
# Build summed reactions. Start from the highest MT number because
# high MTs never depend on lower MTs.
for mt_sum in sorted(SUM_RULES, reverse=True):
if mt_sum not in data:
rxs = [data[mt] for mt in SUM_RULES[mt_sum] if mt in data]
@ -545,7 +545,7 @@ class IncidentNeutron(EqualityMixin):
energy = ace.xss[ace.jxs[1]:ace.jxs[1] + n_energy]
data.energy[strT] = energy
total_xs = ace.xss[ace.jxs[1] + n_energy:ace.jxs[1] + 2 * n_energy]
absorption_xs = ace.xss[ace.jxs[1] + 2*n_energy:ace.jxs[1] +
absorption_xs = ace.xss[ace.jxs[1] + 2 * n_energy:ace.jxs[1] +
3 * n_energy]
# Create summed reactions (total and absorption)
@ -553,9 +553,10 @@ class IncidentNeutron(EqualityMixin):
total.xs[strT] = Tabulated1D(energy, total_xs)
data.summed_reactions[1] = total
absorption = Reaction(27)
absorption.xs[strT] = Tabulated1D(energy, absorption_xs)
data.summed_reactions[27] = absorption
if np.count_nonzero(absorption_xs) > 0:
absorption = Reaction(27)
absorption.xs[strT] = Tabulated1D(energy, absorption_xs)
data.summed_reactions[27] = absorption
# Read each reaction
n_reaction = ace.nxs[4] + 1