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Evaluation of the Neutron Flux Distribution in an AmBe Irradiator using the MCNP-4C Code
the Neutron Flux Distribution an AmBe Irradiator the MCNP-4C Code
2010/10/15
The present work shows the evaluation of the flux and absorbed dose rate of neutrons in a 241AmBe Irradiator at IPEN facilities using the MCNP-4C transport code. The geometry of the 241AmBe source as ...