Dear Guojun Hu,
One thing you may want to consider depending on the quantity you want to score is that materials
are "static" in a standalone FLUKA calculation. If in the system you want to describe the fluence and reaction rates are high,
then the macroscopic cross section changes due to the fuel burnout will not be reflected in the transport. If you describe a
system with small reaction rate (experimental ADS) then you should not be bothered by this limitation.
Another thing to consider, is that some neutronic parameters like the keff of the system cannot
be calculated with FLUKA, also delayed neutron production (I think) is not implemented in FLUKA
if you want to look at the kinetic parameters....
A last tip if your system if close to criticality and that you want to have reasonable transport time
per starting particle is to consider forcing the fission neutron production to be 1 via the
LOW-NEUT card (proper weight adjustment is performed in this case) as it avoids never ending histories....
Hoping this help
Joachim
Received on Fri Jul 06 2012 - 11:08:37 CEST
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