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What is Neutron Flux Analysis in AmBe Irradiator about?

This document summarizes a study that used the MCNP-4C Monte Carlo code to model and simulate a neutron irradiator facility with multiple configurations of Americium-Beryllium (AmBe) neutron sources. The simulations evaluated the neutron flux distribution and absorbed dose rates in the irradiator. Results showed that increasing the number of AmBe sources from two to eight led to higher neutron fluxes and absorbed dose rates throughout the irradiator, particularly in the fast neutron configuration.

Author

Mohammad Ramzy

Language

EN