Monte Carlo Whole-core Depletion Analysis of Yonggwang Unit 3 Cycles 1 and 2

Abstract

This paper presents a whole-core depletion analysis of Yonggwang Unit 3, cycles 1 and 2, by using MCS code. The Monte Carlo code, MCS, was developed by the COmputational Reactor physics and Experiment laboratory (CORE) at the Ulsan National Institute of Science and Technology (UNIST) for solving complex geometry whole-core problems. The MCS code can treat three-dimensional whole-core geometries with universes and lattices, and neutron physics with a probability-table, free-gas treatment, S(α,β) thermal scattering, and Doppler Broadening Rejection Correction. The purpose of this paper is to present the capability of MCS for solving a commercial pressurized water reactor problem. Yonggwang Unit 3, cycles 1 and 2, were selected to demonstrate the accuracy of MCS for whole-core depletion analysis. The Hot Zero Power (HZP) and Hot Full Power (HFP) conditions were simulated in cycle 1. The simulated results, such as power distributions, coolant density, fuel density, and critical boron concentrations, are compared with results from the two-step code systems, STREAM/RAST-K and DIT/ROCS.