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Changes in data/reaction.py from PullRequest Inc. review

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This commit is contained in:
Paul Romano 2020-04-15 06:51:00 -05:00
parent 14d22b9fe3
commit bea3e07fea
3 changed files with 10 additions and 8 deletions
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4
openmc/data/neutron.py
View file

@ -20,7 +20,7 @@ from .function import Tabulated1D, Sum, ResonancesWithBackground
from .grid import linearize, thin
from .njoy import make_ace
from .product import Product
from .reaction import Reaction, _get_photon_products_ace
from .reaction import Reaction, _get_photon_products_ace, FISSION_MTS
from . import resonance as res
from . import resonance_covariance as res_cov
from .urr import ProbabilityTables
@ -543,7 +543,7 @@ class IncidentNeutron(EqualityMixin):
data.reactions[rx.mt] = rx
# Read total nu data if available
if rx.mt in (18, 19, 20, 21, 38) and 'total_nu' in group:
if rx.mt in FISSION_MTS and 'total_nu' in group:
tgroup = group['total_nu']
rx.derived_products.append(Product.from_hdf5(tgroup))

12
openmc/data/reaction.py
View file

@ -64,6 +64,8 @@ REACTION_NAME.update({i: '(n,3He{})'.format(i - 750) for i in range(750, 799)})
REACTION_NAME.update({i: '(n,a{})'.format(i - 800) for i in range(800, 849)})
REACTION_NAME.update({i: '(n,2n{})'.format(i - 875) for i in range(875, 891)})
FISSION_MTS = (18, 19, 20, 21, 38)
def _get_products(ev, mt):
"""Generate products from MF=6 in an ENDF evaluation
@ -492,7 +494,7 @@ def _get_activation_products(ev, rx):
# Determine if file 9/10 are present
present = {9: False, 10: False}
for i in range(n_states):
for _ in range(n_states):
if decay_sublib:
items = get_cont_record(file_obj)
else:
@ -1021,7 +1023,7 @@ class Reaction(EqualityMixin):
neutron.yield_ = yield_
rx.products.append(neutron)
else:
assert mt in (18, 19, 20, 21, 38)
assert mt in FISSION_MTS
rx.products, rx.derived_products = _get_fission_products_ace(ace)
for p in rx.products:
@ -1126,13 +1128,13 @@ class Reaction(EqualityMixin):
# Get fission product yields (nu) as well as delayed neutron energy
# distributions
if mt in (18, 19, 20, 21, 38):
if mt in FISSION_MTS:
rx.products, rx.derived_products = _get_fission_products_endf(ev)
if (6, mt) in ev.section:
# Product angle-energy distribution
for product in _get_products(ev, mt):
if mt in (18, 19, 20, 21, 38) and product.particle == 'neutron':
if mt in FISSION_MTS and product.particle == 'neutron':
rx.products[0].applicability = product.applicability
rx.products[0].distribution = product.distribution
else:
@ -1177,7 +1179,7 @@ class Reaction(EqualityMixin):
for dist in neutron.distribution:
dist.angle = AngleDistribution.from_endf(ev, mt)
if mt in (18, 19, 20, 21, 38) and (5, mt) in ev.section:
if mt in FISSION_MTS and (5, mt) in ev.section:
# For fission reactions,
rx.products[0].applicability = neutron.applicability
rx.products[0].distribution = neutron.distribution

2
openmc/deplete/chain.py
View file

@ -316,7 +316,7 @@ class Chain:
nuclide.reactions.append(ReactionTuple(
name, daughter, q_value, 1.0))
if any(mt in reactions_available for mt in [18, 19, 20, 21, 38]):
if any(mt in reactions_available for mt in openmc.data.FISSION_MTS):
if parent in fpy_data:
q_value = reactions[parent][18]
nuclide.reactions.append(