Neutronics analysis of UN-PuN fuel for 300MW pressurized water reactor using SRAC-COREBN code

Nuclear Power Plants (NPP) is one of alternative energy that can be used to replace fossil energy. NPP a clean doesn't emit CO2 as residue from the power plant. Pressurized Water Reactor (PWR) most widely commercial reactor date. This usually uses UO2 fuel with enrich U-235 and produce plutonium waste nuclear. In this study, natural uranium addition spent PWR, calling it Uranium-Plutonium Nitride (UN-PuN) fuel. Plutonium PWR (U-fueled) consists Pu-238, Pu-239, Pu-240, Pu-241 Pu-242, which Pu-239 are fissile material. The aim using reduce amount nuclear prevent use weapon. neptunium protactinium also carried out in Neptunium minor actinide materials have high toxicity, so add Np-237 very useful world. And also, Pa-231 aims decrease keff value both Beginning Life (BOL) End (EOL) reactor. research calculates neutronic calculations for SRAC2006 COREBN Code Japanese Evaluated Data Library 4.0 (JENDL-4.0) data library. code calculation method based on interpolation macroscopic cross-section finite-difference diffusion theory. optimum design reached maximum k-eff 1.017077 density was 58.47 W/cc. results obtained excess reactivity 1.68 % smaller than previous study produces an 11.94 %. So has potential applied