MCS ANALYSIS OF 1000 MWTH SODIUM-COOLED FAST REACTOR

Abstract

This paper describes the neutron transport calculations for the sodium-cooled fast reactors by using the new under-developing Monte Carlo code MCS in combination with various nuclear data libraries. MCS is a three dimensional (3D) continuous energy neutron/photon transport code based on the Monte Carlo code which was developed at Ulsan National Institute of Science and Technology (UNIST). A reference metallic fuel of Advanced Burner Reactor (MET-1000) core concept of 1000 MWth power rating was developed using MCS code to verify its capability for the fast reactor design options. MCS developed the 3D-whole core heterogeneous and homogenous models of MET-1000 core and several parameters of interest such as the effective neutron multiplication factor (keff), sodium void reactivity coefficient (KNa), doppler constant (KD) and control rod worth (KCR) reactivity coefficient are calculated. In addition, two typical states of nominal operation at Beginning Of Cycle (BOC) and Ending Of Cycle (EOC) were studied and the impact of nuclear data on safety-relevant parameters have observed by using the nuclear cross section library ENDF/BVII.0, ENDF/BVII.1 and JEFF3.3. The MCS results were observed by comparing with the reference results obtained from different participant institutions in the benchmark. Moreover, the discrepancies between the results in MCS and the reference were explained in this paper.