Validation of the MCNP6 code for SFR shielding design analysis

In this paper, the uncertainty of the Monte Carlo code MCNP6 for the sodium-cooled fast reactor
(SFR) shielding design is studied. Shielding analysis, which ensures the radiation safety of the
core design, is challenging for the Monte Carlo modeling because it is associated with large
uncertainties. In order to evaluate the performance of the MCNP6 relative to the shielding design of
the SFR, four SFR shielding benchmarks from the Shielding Integral Benchmark Archive Database
benchmark suite, i.e. JANUS Phase VIII, SDT12, EURAC_Na and HARMO_Na were selected and analysed. In
this research, the weight window variance-reduction technique and the neutron data library
ENDF/B-VII.1 were used in the modeling of the benchmark problems. The results and the validation of
the MCNP6 models with the available measurement data are presented in this paper. These results
contribute to the assessment of radiological protection and shielding design of the Korean Prototype
Gen-IV Sodium-cooled Fas...

Source: Journal of Radiological Protection - December 4, 2018 Category: Physics Authors: Tuan Quoc Tran, Sanggeol Jeong, Khang Nhat Hoang Nguyen, Hyunsuk Lee, Sooyoung Choi, Peng Zhang, Min Jae Lee, Jae-Yong Lim and Deokjung Lee Source Type: research