Preliminary Study of 300 MWth Pressurized Water Reactor with Carbide Fuel with Addition Neptunium 237 Using Srac-Corebn Code

Abstract

The research on the design of a pressurized water reactor with a power of 300 MWth and using uranium carbide (UC) fuel has been carried out. Neutronic analysis was carried out using the System Reactor Atomic Code (SRAC) program, which was operated on a set of computers with Linux Operating System (OS), SRAC codes, namely PIU and COREBN. PIU is used to calculate the fuel cell level, and COREBN is used to calculate the reactor core level. The reactor is designed to produce critical conditions. The parameters analyzed in this study were fuel enrichment (U-235), reactor core size, multiplication factor, reactor core configuration, and criticality. This study calculates the neutronic calculation of UC fuel with the addition of Neptunium 237 (Np-237), which aims to reduce the value of the effective multiplication factor (k-eff). Neutronic analysis of UC fuel with critical conditions at Fl = 4.5%, F2 = 5%, F3 = 5.5%, fuel fraction = 55% with the addition of neptunium 237 0.5%.