摘要
在大型先进非能动核电厂安全审评过程中,我国核安全监管机构利用非能动堆芯冷却系统整体试验(ad⁃vanced core-cooling mechanism experiment,ACME)开展了全厂断电(station blackout,SBO)整体效应试验,为评估缩比非能动余热排出换热器(passive residual heat removal heat exchanger,PRHR HX)对原型性能的再现能力,本文分析了缩比PRHR HX的流动换热特性,利用多级双向模化分析方法开展了PRHR HX支路自然循环现象的模化分析,研究了SBO试验PRHR HX的失真特性。结果表明:以热阱数为主要模化准则的缩比PRHR HX具有良好的换热性能,事故期间可有效载出堆芯衰变热,实现与堆芯衰变功率的匹配;ACME缩比PRHR换热器以可接受的失真再现了原型的换热能力、通流能力和流动阻力特性;事故瞬态过程中,PRHR自然循环过程的特征时间和模化准则数均呈现动态变化,导致缩比PRHR HX的模化失真也具有显著的动态特性。
During the safety review of advanced passive nuclear power plants,China’s nuclear safety regulatory agencies typically conduct station blackout(SBO)integral effect tests based on the advanced core-cooling mecha⁃nism experiment(ACME).In this study,we evaluated the reproducibility of the scaled passive residual heat remov⁃al heat exchanger(PRHR HX)on design performance of the prototype.Then,we investigated the flow and heat transfer characteristics of PRHR HX based on the ACME SBO test.We also conducted the scaling analysis of PRHR HX,which mainly focused on the natural circulation(NC)phenomena occurring between the PRHR HX and decaying core via the hierarchical two-tiered scaling(H2TS)method.Moreover,we examined the scaling distor⁃tions in simulating NC phenomena.The results revealed excellent heat transfer performance of the scaled-down PRHR HX,which was designed according to the heat sink number similarity criterion.Therefore,the decay heat can be transported effectively and continuously during the transient,matching the decay power of the reactor core.The prototype’s heat transfer characteristic,flow capacity,and friction force characteristic in PRHR NC were repre⁃sented with acceptable scaling distortions in PRHR HX.In the transient process,the characteristic time and scal⁃ing numbers representing the natural circulation process of PRHR all showed dynamic changes,which in turn,led to the scaling distortion of the scaled PRHR HX with significant dynamic characteristics.
作者
刘宇生
许超
谭思超
靖剑平
庄少欣
王楠
LIU Yusheng;XU Chao;TAN Sichao;JING Jianping;ZHUANG Shaoxin;WANG Nan(Heilongjiang Provincial Key Laboratory of Nuclear Power System&Equipment,Harbin Engineeving University,Harbin 150001,China;Nuclear and Radiation Safety Center,MEE,Beijing 100082,China;State Nuclear Power Technology R&D Center Co.,Ltd.,Beijing 102209,China)
出处
《哈尔滨工程大学学报》
EI
CAS
CSCD
北大核心
2023年第10期1689-1695,共7页
Journal of Harbin Engineering University
基金
国家科技重大专项(2015ZX06002007).
关键词
全厂断电
试验模拟
比例分析
自然循环
非能动堆芯冷却系统整体试验
比例失真
动态特性
非能动余热排出
station blackout
experimental simulation
scaling analysis
natural circulation
advanced core-cooling mechanism experiment facility
scaling distortion
dynamic characteristics
passive residual heat removal
