Hello, Geant4 experts,
I’m looking for guidance on how to calculate the effective fast-neutron removal cross section (Σᵣ) as a function of neutron energy.
My goal is to simulate monoenergetic neutron beams (for example, 0.5–5 MeV) through a slab, record the number of **incident and transmitted neutrons then calculation of FNRC
**
Could someone please guide me on which example would be the best starting point for this type of calculation