Recent content by Marinaromany
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Normalization of MCNP F4:P photon flux tally to experimental counts
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...- Marinaromany
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- Forum: Nuclear Engineering