环形通道内再淹没过程骤冷前沿推进速度实验研究  

Experimental Study on Velocity of Quench Front during Reflooding Process in a Vertical Annual Channel

作　　者：王金宇 王均 昝元峰[1] 黄军[1] Wang Jinyu;Wang Jun;Zan Yuanfeng;Huang Jun(CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology,Nuclear Power Institute of China,Chengdu 610041,China)

机构地区：[1]中国核动力研究设计院中核核反应堆热工水力技术重点实验室,成都610041

出　　处：《核动力工程》2018年第4期63-66,共4页Nuclear Power Engineering

基　　金：中核核反应堆热工水力技术重点实验室运行基金

摘　　要：骤冷前沿推进速度是衡量失水事故中再淹没过程堆芯冷却效率的重要参数之一。本文通过实验研究了竖直环形通道内骤冷前沿的推进特性,获得初始壁温、入口温度、入口质量流速及加热功率对骤冷前沿推进速度的影响。实验结果表明,骤冷前沿推进速度随初始壁温、入口温度和加热功率的增加而减小,随入口质量流速的增加而增加。Velocity of quench front is one of the important parameters which measure the cooling efficiency of the reactor core during the reflooding process after loss of coolant accident. Based on an experimental study of propulsion characteristics of quench front in a vertical annual channel, the effects of initial clad temperature, inlet coolant temperature, inlet mass flow flux, and heating power on the velocity of quench front were investigated. The results show that the velocity of quench front decreases with the increasing of the initial wall temperature, inlet coolant temperature as well as heating power, but increases with the increasing of the inlet mass flow rate.

关 键 词：环形通道 底部再淹没 骤冷前沿推进 

分 类 号：TL33[核科学技术—核技术及应用]