反应堆冷却剂丧失事故后溶解沉淀过程及其热力学分析  

Dissolution and Precipitation Process after Loss of Coolant Accident(LOCA)in a Reactor and Its Thermodynamic Analysis

作　　者：庄文华 鲍一晨[2] 陈志刚 石秀强[2] 刘晓强[2] 张乐福[1] ZHUANG Wenhua;BAO Yichen;CHEN Zhigang;SHI Xiuqiang;LIU Xiaoqiang;ZHANG Lefu(School of Nuclear Science and Engineering,Shanghai Jiao Tong University,Shanghai 200240,China;Shanghai Nuclear Engineering Research and Design Institute,Shanghai 200233,China)

机构地区：[1]上海交通大学核科学与工程学院,上海200240 [2]上海核工程研究设计院股份有限公司,上海200233

出　　处：《腐蚀与防护》2025年第4期52-59,共8页Corrosion & Protection

基　　金：国家重点研发计划(2018YFE0116200)。

摘　　要：采用自主搭建的试验系统模拟核电厂事故后安全壳地坑化学效应,对事故后安全壳内材料溶解与沉淀行为开展试验研究。研究了七种材料在不同温度(75~145℃)硼酸溶液中(pH4)的溶解释放行为,以及喷淋系统喷出氢氧化钠(pH8,pH12)时不同温度下材料的溶解释放行为,确定了代表性元素Al、Zn、Fe和Ca的溶解浓度与时间、pH和温度之间的关系。采用三种不同沉淀方法研究了冷却剂丧失事故(LOCA)情景下可能会形成的沉淀物。基于试验结果,通过热力学计算阐明了事故后模拟环境中会发生的化学反应。The chemical effects of the containment sump after a nuclear power plant accident were simulated using a self-developed experimental system,and the experimental research on the dissolution and precipitation behavior of materials inside the safety shell after the accident was conducted.The dissolution and release behavior of seven materials in boric acid solutions(pH4)at different temperatures(75-145℃)was studied,as well as the dissolution and release behavior of materials at different temperatures when sodium hydroxide(pH8,pH12)was sprayed from a spray system.The relationship between the dissolution concentrations of representative elements(Al,Zn,Fe,and Ca)and time,pH,and temperature was determined.Three different precipitation methods were used to study the possible formation of precipitates under LOCA scenarios.Based on the experimental results,the chemical reactions that would occur in the simulated environment after the accident were elucidated through thermodynamic calculations.

关 键 词：化学效应 溶解 沉淀 安全壳材料 冷却剂丧失事故(LOCA) 

分 类 号：TG172[金属学及工艺—金属表面处理]