Normalization of MCNP F4:P photon flux tally to experimental counts

[Marinaromany]

Hello everyone
I am using MCNP with a DT neutron source and I am interested in prompt gamma measurements. My detector is modeled as a simplified volume, and I am currently using an F4:P tally with energy bins to obtain the photon spectrum.

Since the F4 tally gives photon flux per source particle (ph/cm²/source), I would like to ask:

What is the correct way to convert or normalize an F4 photon flux tally to counts, so that it can be meaningfully compared with experimental spectra or reported as detector count

 

[Alex A]

Welcome to PF @Marinaromany,
It might be possible to do that with an F4 and a cross section multiplier but F8:p,e is a better way on the cell of the crystal, and the tally result is in total counts.