Hello,
is there possibility to set the maximum neutron transport energy, Emax, in the input file, either xml or py?
Background: I compared depletion calculation results obtained with the different decay chain files. The Keff-values are the same (within stat.dev) for CASL and ENDF7-based chains, but different (lower) for the decay chain file based on ENDF8. This seems strange, since this difference is already at t=0.
In the openMC output I have found that Emax is set differently, depending on the XS-data read in:
For CASL and ENDFB7 decay chains:
Maximum neutron transport energy: 20000000 eV for Ag107
For ENDFB8-based chain:
Maximum neutron transport energy: 8100000 eV for Be7
Now I would like to limit Emax to 8.1 MeV in the depletion calculations with CASL and ENDFB7 decay chains, to see whether it indeed results in the lower Keff.
Related posts:
-
the impact of the Emax onto the neutron transport is commented here: how-openmc-deal-with-cross-sectional-data.
-
The Be7 xs upper limit is mentioned here: Warning while reading from ENDF/B-VII.1 - #3 by paulromano
Regards, Anton.