严重事故IVR下反应堆压力容器耦合传热数值模拟分析  

Simulation on Coupled Heat Transfer for Reactor Vessel in Severe Accident IVR

作　　者：姚彦贵[1] 施杨[1] 蒋兴[1] 贺寅彪[1] 

机构地区：[1]上海核工程研究设计院,上海200233

出　　处：《原子能科学技术》2014年第8期1473-1478,共6页Atomic Energy Science and Technology

摘　　要：堆芯熔化严重事故下保证反应堆压力容器(RPV)完整性非常重要,高温蠕变失效是堆芯熔化严重事故下反应堆压力容器的主要失效模式。在进行严重事故堆芯熔化物堆内包容(IVR)下RPV结构完整性分析中,RPV内外壁和沿高度方向的温度分布以及剩余壁厚是结构分析的重要输入。本文采用CFD分析方法对RPV堆内熔融物、RPV壁以及外部气液两相流动换热进行热-固-流耦合分析,获得耦合情况下的温度场、流场、各相份额分布以及RPV的剩余壁厚,为RPV在严重事故IVR下的结构完整性分析提供依据。It is very important to remain the integrity of reactor pressure vessel （RPV ） in the core melt severe accident .The high temperature creep failure is the main failure mode for RPV in core melt severe accident .T he altitude distributions of outer and inner wall temperatures are important inputs for structure analysis .In this work ,the CFD method was used to carry out heat-solid-fluid coupled analysis of the corium in RPV , RPV wall and outer gas-water two-phase flow heat transfer . The temperature field , flow field , the fraction distribution of each phase in the coupled situation and the remaining thickness of the pressure vessel wall were obtained ,providing the support for analyzing the RPV structure integrity in severe accident the reactor corium in-vessel retention （IVR） .

关 键 词：耦合传热分析 严重事故 反应堆压力容器 

分 类 号：TL35[核科学技术—核技术及应用]