AP1000主回路系统热工水力瞬态计算程序RETAC的开发  

Development of Thermal-Hydraulic Transient Analysis Code RETAC for AP1000 Primary Loop

作　　者：王伟伟[1,2] 苏光辉[1,2] 田文喜[1,2] 秋穗正[1,2] 

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,陕西西安710049 [2]西安交通大学核科学与技术系,陕西西安710049

出　　处：《原子能科学技术》2011年第10期1185-1190,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：针对先进压水堆AP1000的具体结构和运行特点,采用FORTRAN程序设计语言,自主开发了用于AP1000主回路系统热工水力瞬态计算的微机型程序RETAC(REactor Transient Analysis Code)。利用程序对AP1000失流事故进行分析,得到了堆芯燃料中心最高温度、最小偏离泡核沸腾比(MDN-BR)、稳压器压力、水位及蒸汽发生器二次侧压力、水位等主要系统参数的瞬态特性。分析结果表明,在失流事故初期阶段,堆芯热通道燃料中心最高温度和MDNBR不超出规定限值,满足安全准则要求。RETAC完全采用模块化编程,便于移植和二次开发,可为后续开发自主知识产权的大功率压水堆安全分析程序提供借鉴。A thermal-hydraulic microcomputer code（RETAC,REactor Transient Analysis Code） for transient analysis of AP1000 primary loop was developed using FORTRAN language.The loss of flow accident（LOFA） was analyzed using RETAC.Transient characteristics of some main system parameters were obtained,including the maximum fuel temperature and MDNBR in the hot channel,pressure and water level in the pressurizer and steam generator secondary side.The results show that at the early stage of the loss of flow accident,the highest fuel central temperature and MDNBR in the hot channel do not exceed specified limits and meet the safety criteria.Modular programming technique was adopted for RETAC and it is convenient for further modification and application.It is expected that the present work is instructive to develop Chinese own independent software for the design and safety analysis of large scale PWR.

关 键 词：AP1000 热工水力 瞬态分析 安全分析软件 RETAC 

分 类 号：TL33[核科学技术—核技术及应用]