Dear Fluka expert,
I have four questions regarding low neutron transport in fluka.
I would like to simulate a very simple situation.
This situation is the following:
* I have a monoenergetic source of neutron in air (for example 9 MeV)
* I want to score neutron and secondary particle fluences at 1 m from the source
I know that low energy neutrons use the multigroup formalism and scattering matrix.
However, I am wondering how multigroup formalism impacts the simulated energy in fluka for the primary/secondary particles and for the fluence score.
My questions are the following:
-If my primary neutrons are simulated at 9 MeV, as the corresponding energy group is [8.82-9.05] MeV, should I consider the primary particle has an energy of 8.94 MeV (average).
-If I want the total discretization of my fluence with the smallest energy mesh, should I describe fluka energy groups in my USRBDX score or is it treated automatically by putting 0.01 meV and 20 MeV for low neutron energy in WHAT4 and WHAT5 ?
-If I want fluences from secondary particles (gamma, neutron and charged particles), are they simulated like for gamma or electron transport or is it treated differently (with group or average factors for example).
-In my situation, (air + monoenergetic low neutron), is it possible to request pointwise sections for the transport? If yes, how can I do?
Thank you very much for your answer,
Salutations respectueuses,
Thomas Frosio
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Received on Tue Dec 11 2018 - 12:41:56 CET