摘要
设计实验台架研究某型船用核动力装置主泵卡轴特性,利用热工水力程序RELAP5完成了反应堆系统仿真模型的建立及验证。模拟了反应堆系统单台主泵卡轴事故进程,得到了反应堆温度、环路流量等重要参数的变化规律。结果表明:主泵卡轴特性参数对反应堆流量影响较大,事故环路流量大幅下降直至出现倒流现象,影响堆芯冷却与安全;采用多环路设计时,功率运行过程中单台主泵的卡轴事故对反应堆安全造成的风险较小;主泵运行速率对事故进程有一定的影响。
An experiment bench was designed to obtain the shaft seizure characteristics for reactor coolant pump of a certain type of marine nuclear power plant.Using the thermal-hydraulic program RELAP5,a simulation model of reactor system was established and verified.The investigation of shaft seizure accident for single coolant pump was carried out and change rules of important parameters such as reactor temperature,loop flow rate were acquired.The results indicate that shaft seizure characteristic parameters of coolant pump affect the reactor flow characteristics greatly.The flow rate of accident loop declines sharply until the appearance of reverse flow phenomenon,which affects the core cooling and safety.Shaft seizure accident for single coolant pump under power operating condition poses small risk on reactor safety while the multi-loop design is applied.The operation rate of coolant pump has certain influence on the accident process.
作者
李伟通
于雷
李攀
谢明亮
张连红
LI Weitong;YU Lei;LI Pan;XIE Mingliang;ZHANG Lianhong(College of Nuclear Science and Technology,Naval University of Engineering,Wuhan 430033,China;92609 Department of PLA,Beijing 100077,China;China Nuclear Power Operating Technology Corporation Ltd.,Wuhan 430223,China;The No.92730 th Troop of PLA,Sanya 572016,China)
出处
《兵器装备工程学报》
CAS
北大核心
2020年第10期48-52,共5页
Journal of Ordnance Equipment Engineering
基金
国家自然科学基金项目(11502298)
核反应堆系统设计技术国家重点实验室基金项目(HDY-2015004)。
关键词
泵特性实验
主泵模型
卡轴事故
安全分析
pump performance experiment
coolant pump model
shaft seizure accident
safety analysis