PRELIMINARY CORE NEUTRONICS DESIGN FOR THE MALAYSIAN MPR BASED ON THE 30MWTH HANARO REACTOR

Abstract

This paper presents a benchmarking study of the 30 MWth South Korean HANARO reactor to provide reference data for future conceptual studies of a Malaysian Multi-Purpose Research Reactor (MPR). The analysis, performed using the MCNPX 2.7 Monte Carlo radiation transport code, involved constructing a detailed HANARO core model and simulating key neutronic behavior, including criticality, neutron flux distribution, and fuel burnup. Simulation results were rigorously validated against experimental measurements at various irradiation sites, showing strong agreement for thermal neutron flux values and demonstrating the accuracy of the model in capturing core physics, non-uniform power distribution, and the effects of the heavy water reflector on thermal flux. These results establish a robust technical benchmark and a validated modeling approach that can inform preliminary core design considerations for a potential Malaysian MPR, which remains at the conceptual stage with no design decisions finalized. The study confirms that MCNPX 2.7 is a reliable tool for research reactor neutronics analysis and provides essential insights for future design and safety studies.