原子能科学技术2016，Vol.50Issue(8)：1422-1427,6.DOI:10.7538/yzk.2016.50.08.1422
AP1000核电厂主给水管道断裂事故瞬态特性分析
Transient Characteristics of Main Feedwater Line Rupture Accident for AP1000 Nuclear Power Plant
摘要
Abstract
The AP1000 is the typical “third generation”passive nuclear power plant in the world at present.The primary system of AP1000 nuclear power plant was modeled using RELAP5/MOD3.3 code,and the transient thermal-hydraulic characteristics and the response characteristics of passive system were analyzed under the accident sequence of main feedwater line rupture accident.The results show that during the accident,the primary loop pressure,secondary loop pressure and primary loop temperature are fluc-tuant.The RCS pressure maximum value is 17.13 MPa,less than 91% of the design pressure.The pressure of the main steam system is also less than 91% of the designed value,which satisfies acceptance criteria.关键词
RELAP5/MOD3.3 程序/AP1000/主给水管道断裂事故/非能动核电厂Key words
RELAP5/MOD3.3 code/AP1000/main feedwater line rupture accident/passive nuclear power plant分类
能源科技引用本文复制引用
贾祥,安婕铷,靖剑平..AP1000核电厂主给水管道断裂事故瞬态特性分析[J].原子能科学技术,2016,50(8):1422-1427,6.基金项目
大型先进压水堆及高温气冷堆核电站国家科技重大专项资助项目(2011ZX06002-010,2013ZX06002001) （2011ZX06002-010,2013ZX06002001）
