From b9ff205090520b718bbec7a26a07fa7d9361374a Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Thu, 1 Mar 2018 23:09:10 -0600 Subject: [PATCH] Don't put free neutron in depletion chain --- openmc/deplete/chain.py | 7 +++++++ 1 file changed, 7 insertions(+) diff --git a/openmc/deplete/chain.py b/openmc/deplete/chain.py index fbe6792227..1826ca9ca0 100644 --- a/openmc/deplete/chain.py +++ b/openmc/deplete/chain.py @@ -59,6 +59,10 @@ def replace_missing(product, decay_data): Z, A, state = openmc.data.zam(product) symbol = openmc.data.ATOMIC_SYMBOL[Z] + # Replace neutron with proton + if Z == 0 and A == 1: + return 'H1' + # First check if ground state is available if state: product = '{}{}'.format(symbol, A) @@ -167,6 +171,9 @@ class Chain(object): decay_data = {} for f in decay_files: data = openmc.data.Decay(f) + # Skip decay data for neutron itself + if data.nuclide['atomic_number'] == 0: + continue decay_data[data.nuclide['name']] = data print('Processing fission product yield sub-library files...')