摘要
自然循环能力是衡量钠冷快堆固有安全性的重要指标,堆芯布置、回路设计及工况参数等都会影响堆芯自然循环能力,因此不同堆型的自然循环能力有很大差异。为了保证堆芯事故得到有效缓解,中国实验快堆(CEFR)的设计中通过优化系统布置,重点考虑了堆芯自然循环。本文采用SAS4A程序对CEFR进行系统建模,分析了CEFR在无保护失流(ULOF)工况下的堆芯热工水力参数瞬态特性,验证了CEFR利用自身自然循环和负反馈设计进行事故缓解的能力,本文还对一回路流动阻力和二回路钠装量对堆芯自然循环的影响进行分析。计算结果表明,CEFR具有良好的自然循环特性,在ULOF工况下可以依靠其负反馈停堆,并能够建立起稳定的自然循环从而导出堆芯余热。
Natural circulation ability is an important indicator to measure the inherent safety of sodium cooled fast reactor.Core layout,circuit design and operating parameters will affect the natural circulation capacity of the core,so the natural circulation capacity of different core types is very different.In order to effectively alleviate the core accident,the natural circulation of China Experimental Fast Reactor(CEFR)is considered in the design by optimizing the system layout.In this paper,the SAS4A program is used to model the CEFR system.The transient characteristics of the core thermal hydraulic parameters of CEFR under the condition of Unprotected Loss of Flow(ULOF)are analyzed,and the ability of accident relief using the natural circulation and negative feedback of CEFR is verified.This paper also does research on the influence of primary circuit flow resistance and secondary circuit sodium loading on the natural circulation of the core.The calculation results show that CEFR has strong natural circulation characteristics,and can shutdown rely on its negative feedback under the condition of SBO,and a stable natural circulation is established to remove the core residual heat.
作者
梁继越
张熙司
乔鹏瑞
张东辉
LIANG Jiyue;ZHANG Xisi;QIAO Pengrui;ZHANG Donghui(China Institute of Atomic Energy,Reactor Engineering Technology Research Division,Beijing.102413,China)
出处
《核科学与工程》
CAS
CSCD
北大核心
2019年第6期1040-1046,1052,共8页
Nuclear Science and Engineering
