Evaluation of the MCNP6 Code for SFR Shielding Analysis

Abstract

The Prototype Generation-IV Sodium-cooled Fast Reactor (PGSFR) design is being conducted by KAERI with support of Korean government. Shielding analysis, which ensures the radiation safety of the core design, is challenging for the Monte Carlo modeling, since it is associated with large uncertainties. In order to evaluate the performance of the Monte Carlo code MCNP6 for the shielding design of PGSFR. Four SFR shielding benchmarks were selected and analyzed from the SINBAD benchmark suit, such as JANUS Phase VIII, SDT12, EURAC_Na and HARMO_Na. In this research, the Weight Window variance reduction technique and the latest neutron data library ENDF/B-VII.1 was used in the modelling of the benchmark problems. The results and the validation of MCNP6 models with available measurement data are presented in this paper. The results obtained in this research would be a basis for further analysis of the Korean PGSFR shielding design.