From 927cbdac14d2324c6d87f9f762355c47cc6870e0 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 13 Nov 2018 10:49:04 -0600 Subject: [PATCH] Find nu properly for nuclides with first-, second-, etc. chance fission --- openmc/data/fission_energy.py | 4 ++-- 1 file changed, 2 insertions(+), 2 deletions(-) diff --git a/openmc/data/fission_energy.py b/openmc/data/fission_energy.py index ee2d950786..95915650b8 100644 --- a/openmc/data/fission_energy.py +++ b/openmc/data/fission_energy.py @@ -279,11 +279,11 @@ class FissionEnergyRelease(EqualityMixin): # 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: + if 18 in incident_neutron and not incident_neutron[18].redundant: nu = [p.yield_ for p in incident_neutron[18].products if p.particle == 'neutron' and p.emission_mode in ('prompt', 'total')] - elif 19 in incident_neutron.reactions: + elif 19 in incident_neutron: nu = [p.yield_ for p in incident_neutron[19].products if p.particle == 'neutron' and p.emission_mode in ('prompt', 'total')]