Explore the possible advantages of using thorium-based fuel in a pressurized water reactor (PWR) Part 1: Neutronic analysis

• DOI: 10.1016/j.net.2021.07.019
• Publication Date: 2021-07-16T21:55:54Z
• Authors: A. Abdelghafar Ga...; Mohamed Y.M. Mohsen; Naima Amrani
• Keywords: Burnup; Neutron capture; Pressurized water reactor; Prompt neutron

This study discusses the effect of using 232Th instead 238U on neutronic characteristics and main operating parameters pressurized water reactor (PWR). MCNPX version 2.7 was used to compare UO2 with (Th, 235U)O2 233U) O2. Firstly, infinity multiplication factor (Kinf), thermal neutron flux, power distribution have been studied for investigated fuel types. Secondly, Gd2O3 Er2O3 Kinf radial flux has distinguish which them is more suitable than other in reactivity management. Thirdly, illustrate effectiveness decreasing inventory both actinides non-actinides, concentration plutonium (Pu) isotopes minor (MAs) simulated burnup. Besides, due their large absorption cross-section, concentrations 135Xe, 149Sm, 151Sm burnup investigated. Finally, safety such as worth control rods (ρCR), effective delayed fraction βeff, Doppler coefficient (DRC) were calculated determine extent these types achieve acceptable limits.