受压热冲击下反应堆压力容器内流动和传热研究综述

Summary of Flow and Heat Transfer in RPV under PTS

在发生反应堆失水事故(LOCA)时,紧急安注导致的受压热冲击(PTS)对反应堆压力容器(RPV)的安全有着重要影响。对于失水事故下反应堆压力容器内流动和传热的研究,发达国家已经进行了很多年,在试验模拟和数值计算方面均取得了很多的成果。随着我国近年来核电技术的进步,对失水事故下RPV的完整性展开了研究工作。本文总结了国内外该方面研究工作,对研究工作中存在的问题和发展的方向进行了探讨。

PTS under loss of coolant accident (LOCA) has great effect on the safety of RPV. Many research works focusing on flow and heat transfer in RPV under PTS have been done in developed coun-tries for many years, and a lot of results have been got both on experiment and numerical simulation. The safety of nuclear power plant is enhanced greatly by these research works. With the developing of nuclear power technology in China, RPV integration under PTS has been studied. The paper summarizes research works at home and abroad in recent years. The problems existed in present work and research direction in the future are discussed.