Full core analysis of IRIS reactor by using MCNPX.

Abstract

This paper describes neutronic analysis for fresh fuelled IRIS (International Reactor Innovative and Secure) reactor by MCNPX code. The analysis included criticality calculations, radial power and axial power distribution, nuclear peaking factor and axial offset percent at the beginning of fuel cycle. The effective multiplication factor obtained by MCNPX… (More)
DOI: 10.1016/j.apradiso.2016.03.031

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