Regular Article

Current capabilities and future developments of Monte Carlo code MCS

¹ Department of Nuclear Engineering, Ulsan National Institute of Science and Technology, 50 UNIST-gil, Eonyang-eup,Ulju-gun, Ulsan, 44919, Republic of Korea
² Advanced Nuclear Technology and Services, 406-21 Jonga-ro, Jung-gu, Ulsan, 44429, Republic of Korea

^* e-mail: deokjung@unist.ac.kr

Received: 18 August 2024
Received in final form: 28 January 2025
Accepted: 30 January 2025
Published online: 4 March 2025

Abstract

The Monte Carlo code, MCS was developed at the Ulsan National Institute of Science and Technology (UNIST) in 2011. In the initial development phase, the primary focus was on developing a Monte Carlo code for the high-fidelity multicycle analysis of large-scale power reactors, especially pressurized water reactors. For the power reactor analysis, capabilities including refueling and shuffling of fuel assemblies, on-the-fly Doppler broadening of neutron cross-sections, and multiphysics coupling were implemented in the MCS. Beyond reactor analysis and capabilities, MCS has been developed to extend its applications. The MCS has been used for radiation shielding, group constants generation, sensitivity, uncertainty, and transient analysis. This study provides a general overview of MCS capabilities.