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作 者:张盼 赵传奇 王业辉 胡文超 潘昕怿 ZHANG Pan;ZHAO Chuanqi;WANG Yehui;HU Wenchao;PAN Xinyi(Nuclear and Radiation Safety Center,Beijing 100082,China)
机构地区:[1]生态环境部核与辐射安全中心,北京100082
出 处:《核科学与工程》2022年第1期122-128,共7页Nuclear Science and Engineering
基 金:国家科技重点研发计划“核电厂RISMC设计、分析与运行管理的理论方法研究”(2018YFB1900305)项目资助。
摘 要:福岛核事故发生以后,全厂断电事故成为了关注的热点。为了研究核电厂在全厂断电事故后的系统响应,文章采用系统分析程序针对非能动核电厂的系统、设备建立系统级模型,并开展计算分析。获得了主回路系统、安全系统关键参数的瞬态响应,得出如下结论:全厂断电事故后,非能动核电厂依靠蒸汽发生器(Steam Generator,SG)和非能动余热排出系统(Passive Residual Heat Removal system,PRHR)能够及时带出堆芯衰变热;PRHR启动的早晚影响SG二次侧冷却剂进行堆芯余热的带出,但对反应堆冷却能力的影响并不大;堆芯补水箱(Core Makeup Tanks,CMT)向主回路注入冷却剂的质量和速率对主回路温度、压力、稳压器液位的影响很大,可考虑调节CMT注入管线的阻力,使CMT注入流量在合理的水平,防止稳压器发生满溢。After the Fukushima nuclear accident,the station blackout accident became a focus of attention.In order to study the system response of the nuclear power plant after the station blackout accident,a system-level model for the system and equipment of a passive nuclear power plant is established by using a system analysis code,and the calculation and analysis are carried out.The transient response of key parameters of the primary circuit system and the safety system is obtained,and the conclusions are as follow:After the station blackout accident,the passive nuclear power plant relies on the steam generator(SG)and the passive residual heat removal system(PRHR)can bring out the core decay heat in time.The PRHR start sooner or later affects the SG secondary side coolant to carry out the residual heat of the core,but it has little effect on the cooling capacity of the reactor core.The mass and flow rate of the coolant from CMT inject into the primary circuit have a great influence on the temperature,pressure and pressurizer water level.It can be considered to adjust the resistance of the CMT injection pipeline,so that the CMT injection flow rate is at a reasonable level to prevent the pressurizer from overflowing.
分 类 号:TL99[核科学技术—核技术及应用]
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