徐州工程学院学报（自然科学版）2023，Vol.38Issue(4)：32-39,8.
压水堆核电站一回路冷却剂系统可靠性分析
Reliability Analysis of Primary-circuit Coolant System in Pressurized Water Reactor Nuclear Power Plant
摘要
Abstract
During the operation of primary-circuit system in the pressurized water reactor(PWR)nuclear power plant,the failure of the main pump,regulator and other equipment with time will bring problems related to system stability.According to the operating characteristics of the primary-circuit coolant,a reliability study is conducted on the primary coolant system of a PWR nuclear power plant,focusing on such related equipment as the primary pump,pressurizer,steam generator,and valves.The GO-FLOW method,which is suitable for handling time-related correlations,is used to establish a model of the coolant system.Subsequently,a reliability analysis is performed on the primary coolant system of the PWR nuclear power plant.The research results provide a research basis for the reliable operation of the primary coolant system of PWR nuclear power plants,which is of certain guiding significance for the safe operation of nuclear power plants.关键词
压水堆核电站/一回路/可靠性/GO-FLOWKey words
pressurized water reactor(PWR)nuclear power plant/primary-circuit/reliability/GO-FLOW分类
信息技术与安全科学引用本文复制引用
任潞,江雨天,王贺鹏,丁降雪,王子函,丁家齐,张晓辉..压水堆核电站一回路冷却剂系统可靠性分析[J].徐州工程学院学报（自然科学版）,2023,38(4):32-39,8.基金项目
国家自然科学基金项目(22108316) （22108316）
宁波市自然科学基金项目(2023J102) （2023J102）
