不同注水方式下混合粒径碎片床冷却特性实验研究  

Experimental Study on Cooling Characteristics of Mixed Particle Size Debris Bed under Different Water Injection Methods

作　　者：杨生兴 宫厚军[1] 方昱 黎阳[1] 胡钰文 昝元锋 杨祖毛[1] 卓文彬[1] Yang Shengxing;Gong Houjun;Fang Yu;Li Yang;Hu Yuwen;Zan Yuanfeng;Yang Zumao;Zhuo Wenbin(CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology,Nuclear Power Institute of China,Chengdu,610213,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610213

出　　处：《核动力工程》2023年第4期247-252,共6页Nuclear Power Engineering

摘　　要：液态堆芯熔融物与冷却剂相互作用(FCI)后破碎形成颗粒床,对颗粒床实施有效的冷却可以实现熔融物的滞留并终止事故进程。本文基于原型熔融物FCI实验后的碎片粒径分布和孔隙率,构建了带内热源的混合粒径砂石碎片床,对不同碎片床强化排热措施(顶部淹没水池、自然循环驱动底部注水、周向进水)下的干涸特性进行了研究,实验中发现:顶部淹没水池条件下,碎片床的中上部率先出现汽泡壅塞区,随后在碎片床中下部出现缺液干涸区;自然循环驱动底部注水条件下,极大改善了碎片床底部的缺液状态,干涸热流密度(DHF)提升2.5倍以上,干涸区域位于碎片床中上部;周向进水方式下,DHF也提升2.5倍以上。The liquid core melt interacts with the coolant and breaks into a particle bed.Effective cooling of the particle bed can realize the retention of the melt and stop the accident process.In this paper,based on the particle size distribution and porosity of the fragments after the prototype molten FCI experiment,a mixed particle size sand debris bed with internal heat source was constructed,and the dryout characteristics of the debris bed under different enhanced heat removal measures(submerged pool at the top,water injection at the bottom driven by natural circulation,and circumferential water inlet)were studied.The results show that,under the condition of submerged pool at the top,the bubble clogging zone appears first in the middle and upper part of the debris bed,and then the liquid deficiency dryout zone appears in the middle and lower part of the debris bed.Under the condition of water injection at the bottom driven by natural circulation,the fluid deficiency at the bottom of the debris bed was greatly improved,and the dryout heat flux(DHF)increased by more than 2.5 times,the dryout area was located in the middle and upper part of the debris bed.Under the circumferential water inlet,DHF also increased by more than 2.5 times.

关 键 词：严重事故 堆内滞留 碎片床 干涸热流密度(DHF) 

分 类 号：TL334[核科学技术—核技术及应用]