Advice Needed on Fission Fragment Yields for Pu-239 and Coupling GEF with Geant4

Physics Processes, Models and Cross Sections
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_Geant4 Version:_11.3.0
_Operating System:_Ubuntu
_Compiler/Version:_gcc
_CMake Version:_3.22.1

Hello everyone,

I am currently working on a Geant4 simulation to model a fission chamber, and I need to simulate the production of fission fragments, particularly for Pu-239.

I would like to ask the community for advice on the following:

  1. Fission fragment yield data for Pu-239: Does anyone have experience obtaining fission fragment yield data for Pu-239 from JEFF3.3 database that can be used directly in Geant4? Moreover, I would like to know if the existing fission yield data are:
  • Interpolated between measurements at different neutron energies, or
  • If the yields are assumed to be constant across different energies.
  1. Coupling Geant4 with GEF: Alternatively, I am considering coupling Geant4 with the GEF (General Description of Fission Observables) code to generate fission fragment yields myself. Has anyone here successfully integrated GEF with Geant4? If so, I would greatly appreciate any guidance on:
  • How to extract and format the output from GEF for use within Geant4.
  • Any recommended tools, scripts, or strategies to facilitate this coupling.
  • Any common pitfalls or challenges I should be aware of during this process.
    Any insights, suggestions, or resources would be highly appreciated. Thank you in advance for your help !