The RADTRAD and MicroShield analysis methodology for the LOCA during the long-term shutdown period of Chinshan BWR/4 nuclear power plant

Abstract The Chinshan Nuclear Power Plant is a BWR/4 plant and is in the long-term shutdown period with the fuels still residing in the reactor core. This study presents the methodology for immersion dose analysis of loss of coolant accident (LOCA) with the above conditions and assuming some of the safety systems, facilities and radiation shielding fail. The RADTRAD and MicroShield codes are used in the methodology. This methodology can be used to calculate whole body dose, thyroid dose, and beta-skin dose received by control room personnel for the condition with full core damaged and calculate direct gamma ray radiation dose of control room personnel for the condition with no fuels damaged. The analysis results show that even failures in the safety systems, facilities or radiation shielding during the LOCA, the whole body dose, thyroid dose, and beta-skin dose are well below the acceptance limits specified in the Standard Review Plan.