|Message: Re: Best model for fission n,g production||Not Logged In (login)|
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Could really do with more help on this question. At the moment I'm trying to benchmark Geant4 / MCNP-X for a simple fission problem:
1.2 MeV neutron source -> block of u235.
I'm tallying neutron / gamma number as a function of energy (time integrated) and as a function of time (energyintegrated); tally surface is just a thin sphere surface around the problem.
The G4NeutronHPFission produces delayed neutrons and gammas but at a much lower intensity than MCNP-X, G4ParaFissionModel and G4LFission don't produce any delayed gammas at all?
The gamma spectrum from U235 using 4NuetronHPFission doesn't compare well either; the MCNP-X matches literature better but has discontinuities in it (I'm told it's related to their multi-compound model); nevertheless niether looks like it nails the problem.
I'd really appreciate some advice on this...I'm specifically interested in delayed gammas and neutrons.