- #1
Marinaromany
- 1
- 0
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
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
Last edited by a moderator: