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Handle energy-dependent delayed neutron group probabilities in ENDF files.

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This commit is contained in:
Paul Romano 2016-10-05 15:08:59 -05:00
parent a7d8a49e07
commit cbd2637efc
1 changed files with 31 additions and 2 deletions
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33
openmc/data/reaction.py
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@ -419,8 +419,37 @@ def _get_fission_products_endf(ev):
dist = UncorrelatedAngleEnergy()
dist.energy = EnergyDistribution.from_endf(file_obj, params)
delayed_neutron = products[-6 + i]
delayed_neutron.yield_.y *= applicability.y[0]
delayed_neutron = products[1 + i]
yield_ = delayed_neutron.yield_
# Here we handle the fact that the delayed neutron yield is the
# product of the total delayed neutron yield and the
# "applicability" of the energy distribution law in file 5.
if isinstance(yield_, Tabulated1D):
if np.all(applicability.y == applicability.y[0]):
yield_.y *= applicability.y[0]
else:
# Get union energy grid and ensure energies are within
# interpolable range of both functions
max_energy = min(yield_.x[-1], applicability.x[-1])
energy = np.union1d(yield_.x, applicability.x)
energy = energy[energy <= max_energy]
# Calculate group yield
group_yield = yield_(energy) * applicability(energy)
delayed_neutron.yield_ = Tabulated1D(energy, group_yield)
elif isinstance(yield_, Polynomial):
if len(yield_) == 1:
delayed_neutron.yield_ = deepcopy(applicability)
delayed_neutron.yield_.y *= yield_.coef[0]
else:
if np.all(applicability.y == applicability.y[0]):
yield_.coef[0] *= applicability.y[0]
else:
raise NotImplementedError(
'Total delayed neutron yield and delayed group '
'probability are both energy-dependent.')
delayed_neutron.distribution.append(dist)
return products, derived_products