Verification of MCS Monte Carlo Code for the JRTR Research Reactor

Abstract

The focus of this paper is the verification of UNIST Monte Carlo code MCS modelling capabilities for research reactor applications. The Jordan Research and Training Reactor (JRTR), a pool-tank type material testing research (MTR) reactor with flat fuel-plate assemblies, is modeled in MCS and MCNP6.1 under the same modeling assumptions. This study deals with the calculation of the effective multiplication factor (keff), kinetic parameters, neutron flux, burn up and control rod worth of JRTR model. The MCS calculation results of these parameters are analyzed and compared with reference data from MCNP6.1. Eventually, this study shows very good agreement between MCS and MCNP6.1 and the good performance of MCS modelling capabilities for whole core MTR calculations is therefore demonstrated.