Reliability Analysis of Primary-circuit Coolant System in Pressurized Water Reactor Nuclear Power Plant
REN Lu
JIANG Yutian
WANG Hepeng
DING Xiaoxue
WANG Zihan
DING Jiaqi
ZHANG Xiaohui
ZIANG Zixin
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.
Keywords：pressurized water reactor(PWR)nuclear power plantprimary-circuitreliabilityGO-FLOW
Publication Date：2023-12-30
Online Publishing Date：2025-08-15(First online date of this platform, not the publication date of the document)
Pages：8( 32-39 )