AP1000非能动余热排出系统建模与瞬态数值分析  

Modeling and Transient Numerical Analysis on Passive Residual Heat Removal System in AP1000

作　　者：王伟伟[1] 苏光辉[1] 田文喜[1] 秋穗正[1] 

机构地区：[1]西安交通大学动力工程多相流国家重点实验室,核科学与技术系,陕西西安710049

出　　处：《原子能科学技术》2011年第12期1456-1461,共6页Atomic Energy Science and Technology

基　　金：国家863计划资助项目(2009AA050701);国家自然科学基金资助项目(10905045)

摘　　要：针对AP1000非能动余热排出系统(PRHRS)的具体结构,采用FORTRAN程序设计语言自主开发了瞬态分析程序RETAC-PRHRS(REactor Transient Analysis Code-Passive Residual Heat RemovalSystem)。利用编制的程序对PRHRS误开启事故进行分析,得到了堆芯归一化热功率、流量、最小偏离核态沸腾比(MDNBR)、系统压力、PRHRS流量等主要系统参数的响应特性。分析结果表明,在PRHRS误开启事故发生时,主要系统参数未超出规定限值,不会触发反应堆停堆。并将计算结果与热工水力分析软件,包括西屋公司开发的LOFTRAN及GSE公司开发的Topmeret/THEATRe的计算结果进行对比。对比趋势符合良好,从而证明了AP1000 PRHRS建模的合理性。A transient analysis program RETAC-PRHRS （REactor Transient Analysis Code-Passive Residual Heat Removal System） for PRHRS in AP1000 was developed using FORTRAN language. The inadvertent operation accident of the PRHRS was analyzed and transient characteristics of some main system parameters were obtained, including normalized thermal power, normalized flow rate and MDNBR in the core, system pressure, flow rate in the PRHRS. The results show that the main system parameters do not exceed specified limits and will not cause reactor shut-down. The computed results are further compared with those of thermal-hydraulic analysis codes, including LOFTRAN developed by Westinghouse and Topmeret/THEATRe developed by GSE. The trend shows a good agreement and thus proves the rationality of the modeling on PRHRS in AP1000.

关 键 词：AP1000 非能动余热排出系统 误开启 自然循环 RETAC-PRHRS 

分 类 号：TL33[核科学技术—核技术及应用]