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Bump up test from 1 MeV -> 5 MeV for 458 bug

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This commit is contained in:
Paul Romano 2018-08-06 22:01:54 -05:00
parent d9afa804b8
commit 95108ce311
1 changed files with 24 additions and 21 deletions
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45
openmc/data/fission_energy.py
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@ -224,8 +224,8 @@ class FissionEnergyRelease(EqualityMixin):
raise ValueError('The atomic mass of the ENDF evaluation does '
'not match the given IncidentNeutron.')
if ev.target['isomeric_state'] != incident_neutron.metastable:
raise ValueError('The metastable state of the ENDF evaluation does '
'not match the given IncidentNeutron.')
raise ValueError('The metastable state of the ENDF evaluation '
'does not match the given IncidentNeutron.')
if not ev.target['fissionable']:
raise ValueError('The ENDF evaluation is not fissionable.')
@ -234,8 +234,8 @@ class FissionEnergyRelease(EqualityMixin):
file_obj = StringIO(ev.section[1, 458])
# Read first record and check whether any components appear as tabulated
# functions
# Read first record and check whether any components appear as
# tabulated functions
items = get_cont_record(file_obj)
lfc = items[3]
nfc = items[5]
@ -253,13 +253,14 @@ class FissionEnergyRelease(EqualityMixin):
if name in ('recoverable', 'total'):
continue
# In ENDF/B-VII.1, data for 2nd-order coefficients were mistakenly not
# converted from MeV to eV. Check for this error and fix it if present.
# In ENDF/B-VII.1, data for 2nd-order coefficients were mistakenly
# not converted from MeV to eV. Check for this error and fix it if
# present.
if npoly == 2: # Only check 2nd-order data.
# If a 1 MeV neutron causes a change of more than 100 MeV, we know
# something is wrong.
# If a 5 MeV neutron causes a change of more than 100 MeV, we
# know something is wrong.
second_order = coeffs[2]
if abs(second_order) * 1e12 > 1e8:
if abs(second_order) * (5e6)**2 > 1e8:
# If we found the error, reduce 2nd-order coeff by 10**6.
coeffs[2] /= EV_PER_MEV
@ -277,25 +278,27 @@ class FissionEnergyRelease(EqualityMixin):
elif name == 'neutrinos':
func = Polynomial((zeroth_order, -0.105))
elif name == 'prompt_neutrons':
# Prompt neutrons require nu-data. It is not clear from ENDF-102
# whether prompt or total nu value should be used, but the delayed
# neutron fraction is so small that the difference is negligible.
# MT=18 (n, fission) might not be available so try MT=19 (n, f) as
# well.
# Prompt neutrons require nu-data. It is not clear from
# ENDF-102 whether prompt or total nu value should be used, but
# the delayed neutron fraction is so small that the difference
# is negligible. MT=18 (n, fission) might not be available so
# try MT=19 (n, f) as well.
if 18 in incident_neutron.reactions:
nu = [p.yield_ for p in incident_neutron[18].products
if p.particle == 'neutron'
and p.emission_mode in ('prompt', 'total')]
if p.particle == 'neutron'
and p.emission_mode in ('prompt', 'total')]
elif 19 in incident_neutron.reactions:
nu = [p.yield_ for p in incident_neutron[19].products
if p.particle == 'neutron'
and p.emission_mode in ('prompt', 'total')]
if p.particle == 'neutron'
and p.emission_mode in ('prompt', 'total')]
else:
raise ValueError('IncidentNeutron data has no fission '
'reaction.')
'reaction.')
if len(nu) == 0:
raise ValueError('Nu data is needed to compute fission energy '
'release with the Sher-Beck format.')
raise ValueError(
'Nu data is needed to compute fission energy '
'release with the Sher-Beck format.'
)
if len(nu) > 1:
raise ValueError('Ambiguous prompt/total nu value.')