Dear FLUKA Experts,
A few months ago, I posted this question (DETECT Card - Spikes in the Spectrum - #4 by dcalzola) about stimulating energy deposition events in low-pressure gasses using the DETECT card, which was succinctly answered to my satisfaction
But lately, I’ve been working with MCNP 6.2 to reproduce this same simulation and I got stuck on which nuclear crosssection data to use. ENDF, JENDL or what?
So what nuclear data files (including the version) are used in FLUKA and how can I check this information in FLAIR?
I also understand that a single primary particle can undergo many collisions within the target region, depositing a different energy value per collision (belonging to different energy bins) of my detector.
So according to this image, what does dN/dE [1/GeV] mean? Is there any normalization to the NPS (number of particles simulated)?
Does anyone know the counterpart (f-tally) of DETECT in MCNP? I’m using the “F8” tally together with “E8”, which records pulses per NPS (i.e., energy deposition events in the assigned energy bins).
I’ll be grateful for any suggestions.