Evaluation of the neutron flux distribution in an AmBe irradiator using the MCNP-4C code

Abstract

The present work shows the evaluation of the flux and absorbed dose rate of neutrons in a 241 AmBe Irradiator at IPEN facilities using the MCNP-4C transport code. The geometry of the 241AmBe source as well as the Irradiator design, constituted of 2 neutrons sources, were modeled. In addition, four and eight sources of 241AmBe were also considered for checking the viability to increase the Irradiator performance. The results show an increase for both flux and absorbed dose rate, mainly for the fast configuration.