crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-28 06:05:58 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions 5

Use MT=101 for "absorption" in ESZ block for IncidentNeutron.from_ace

Browse source
This commit is contained in:
Paul Romano 2018-11-12 07:52:07 -06:00
parent a6a95b2d33
commit d1e427ed9a
1 changed files with 2 additions and 2 deletions
Download patch file Download diff file Expand all files Collapse all files

4
openmc/data/neutron.py
View file

@ -641,10 +641,10 @@ class IncidentNeutron(EqualityMixin):
data.reactions[1] = total
if np.count_nonzero(absorption_xs) > 0:
absorption = Reaction(27)
absorption = Reaction(101)
absorption.xs[strT] = Tabulated1D(energy, absorption_xs)
absorption.redundant = True
data.reactions[27] = absorption
data.reactions[101] = absorption
# Read each reaction
n_reaction = ace.nxs[4] + 1