IPWRs非能动余热排出系统运行特性分析  

Analysis on the thermal-hydraulic characteristics for passive residual heat removal system of IPWRs

作　　者：代守宝 彭敏俊[1] 

机构地区：[1]哈尔滨工程大学核科学与技术学院,黑龙江哈尔滨150001

出　　处：《核科学与工程》2010年第3期244-249,共6页Nuclear Science and Engineering

摘　　要：由于结构紧凑和采用模块化及非能动安全技术,一体化压水堆(IPWRs)特别适合于舰船核动力装置的应用。本文研究对象为基于固有安全一体化动力堆UZrHx和俄罗斯一体化压水堆ABV-6M的运行特点而概念设计的一体化压水堆。堆芯采用弧形板状燃料元件,直流蒸汽发生器形式为套管式,利用3个回路的自然循环排出堆芯余热的非能动余热排出系统以及一套能动的停堆冷却系统。运用RE-LAP5/MOD3.4程序对该反应堆在全船断电事故工况下反应堆停堆,非能动余热排出系统和能动停堆冷却系统分别投入运行进行仿真计算,分析其热工水力动态特性,保证堆芯安全。Due to compact configuration and the inherent safety functions,an integral pressurized water reactors（IPWRs） are suitable for the medium/small size nuclear power plants and marine nuclear power.Fundamental concept and general arrangement of the IPWRs in this paper is based on the same principle of the Inherent Safe UZrHx Power Reactor and the Russian ABV-6M IPWR.Overall design of the IPWR is as follows： the adoption of the arc plate fuels in core,casing once-through steam generator（OTSG）,passive residual heat removal system（PRHRS） with three natural circulation loops and active shutdown cooling system（SCS）.In the case of electricity shutdown accident,the reactor trips and PRHRS come into operation.By means of the RELAP5/MOD3.4 code,the thermal-hydraulic behaviors of the IPWR and its PRHRS safety characteristics are researched.The core decay heat may be safely removed.

关 键 词：一体化压水堆 非能动余热排出系统 RELAP5/MOD3.4 

分 类 号：TL353[核科学技术—核技术及应用]