NEUTRONIC ANALYSIS OF THE CANDLE GAS-COOLED FAST REACTOR (GFR) CORE WITH METALLIC URANIUM (U-10%wtZr) FUEL BASED ON OPENMC
Nurhidayah, Fiber Monado, Menik Ariani, Hadir Kaban

University Sriwijaya

Abstract

This study conducts a neutron analysis of the CANDLE Gas-Cooled Fast Reactor (GFR) core with Uranium Metallic (U-10%wtZr) fuel using the OpenMC software. The analysis aims to understand the reactor core^s neutron flux distribution and fission reaction rates. Results reveal higher neutron fluxes in the starter fuel zone due to increased fission reaction rates, while the fresh fuel region shows lower fluxes. The OpenMC software proves effective in neutron analysis for complex reactor geometries, providing crucial insights for safer and more efficient nuclear reactors. Findings contribute to advancing CANDLE-GFR reactors with Uranium Metallic fuel, facilitating sustainable, clean energy solutions while meeting future energy demands and addressing environmental concerns.

Keywords: U-10%wt Zr, CANDLE, GFR, flux distribution, and fission reaction rates

Topic: Physics and Applied Physics