Cr涂层锆合金包壳腐蚀模型研究  

Investigation on Corrosion Model of Cr-coated Zirconium Alloy Cladding

作　　者：沈勇[1,2] 曾谢虎 段振刚 文青龙[1,2,3] 袁波 何梁[4] 高士鑫 Shen Yong;Zeng Xiehu;Duan Zhengang;Wen Qinglong;Yuan Bo;He Liang;Gao Shixin(School of Energy and Power Engineering,Chongqing University,Chongqing,400044,China;Liangjiang Laboratory for New Energy(Nuclear Energy and Power),Chongqing,400044,China;Key Laboratory of Low-grade Energy Utilization Technologies and Systems,Ministry of Education,Chongqing University,Chongqing,400044,China;Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)

机构地区：[1]重庆大学能源与动力工程学院,重庆400044 [2]两江新能源(核能与动力)实验室,重庆400044 [3]重庆大学低品位能源利用技术及系统教育部重点实验室,重庆400044 [4]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610213

出　　处：《核动力工程》2024年第S01期175-180,共6页Nuclear Power Engineering

基　　金：国家自然科学基金(52201091)。

摘　　要：作为耐事故燃料(ATF)包壳候选材料之一,Cr涂层可显著提高锆合金包壳的抗腐蚀和抗氧化性能,有望延长服役寿期。为评估Cr涂层锆合金包壳腐蚀氧化行为,本文建立了Cr涂层锆合金包壳在压水堆正常运行工况下的腐蚀模型,并基于文献实验数据对模型进行了验证;基于该模型进行了热流密度和质量流速对Cr涂层锆合金包壳的腐蚀影响分析。结果表明腐蚀厚度随热流密度的增加而增加;此外,冷却剂质量流速的增加引起包壳壁温减小,最终导致包壳腐蚀厚度减小。As one of the candidate materials for accident tolerant fuel(ATF)cladding,Cr coating can significantly improve the corrosion resistance and oxidation resistance of zirconium alloy cladding,which is expected to prolong the service life.In order to evaluate the corrosion and oxidation behavior of Cr-coated zirconium alloy cladding,a corrosion model of Cr-coated zirconium alloy cladding under normal operating conditions of PWR was established in this paper,and the model was verified based on the experimental data in the literature.Based on this model,the effects of heat flux and mass flow rate on the corrosion of Cr-coated zirconium alloy cladding were analyzed.The results show that the corrosion thickness increases with the increase of heat flux.In addition,the increase of coolant mass flow rate leads to the decrease of cladding wall temperature,which eventually leads to the decrease of cladding corrosion thickness.

关 键 词：压水堆 耐事故燃料(ATF) Cr涂层锆包壳 腐蚀模型 

分 类 号：TL334[核科学技术—核技术及应用]