摘要
核燃料组件在服役过程中,定位格架夹持结构与燃料棒之间的微动磨蚀是导致燃料棒包壳破损的第一大因素,约占燃料棒包壳失效的54.8%。本文针对不同夹持结构对锆合金包壳管的切向微动磨蚀行为,开展了高温高压水化学环境下的磨蚀试验研究,对比分析了曲面与平面夹持结构在不同夹持力条件下包壳管磨痕形貌、磨蚀体积、磨蚀深度等关键参数。研究结果表明,曲面夹持结构对燃料棒包壳的磨蚀以磨粒磨损、片层状脱落、“犁沟”效应为主;平面结构以“犁沟”效应、片层状脱落为主,磨粒磨损较少;此外,相同条件下曲面夹持结构的最大磨蚀深度大于平面夹持结构。
During the service of the nuclear fuel assembly,the fretting wear between the grid spacer holding structure and the fuel rod is the first major factor leading to the damage of the fuel rod cladding,accounting for about 54.8%of the fuel rod cladding failure.According to the tangential fretting wear behavior of zirconium alloy cladding tubes with different holding structures,the experimental study on wear under high temperature and high pressure hydrochemical environment is carried out.The key parameters,such as cladding tube wear scar morphology,wear volume and wear depth of curved and planar holding structures under different holding forces are compared and analyzed.The results show that the wear of the curved holding structure on the fuel rod cladding is mainly abrasive wear,lamellar shedding and“ploughing”effect,while the planar structure is dominated by“ploughing”effect and lamellar shedding,and the abrasive wear is less.In addition,under the same conditions,the maximum wear depth of the curved holding structure is larger than that of the planar holding structure.
作者
任全耀
蒲曾坪
焦拥军
郑美银
陈平
韩元吉
刘孟龙
庄文华
郭相龙
张乐福
Ren Quan yao;Pu Zeng ping;Jiao Yongjun;Zheng Meiyin;Chen Ping;Han Yuanji;Liu Menglong;Zhuang Wenhua;Guo Xianglong;Zhang Lefu(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China;Department of Nuclear Science and Engineering,Shanghai Jiaotong University,Shanghai,200240,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2022年第S02期82-87,共6页
Nuclear Power Engineering
基金
国家自然科学基金(U2067221、12105273)
四川省重大科技专项(2019ZDZX0001)
关键词
切向微动磨蚀
夹持结构
锆合金包壳
磨痕
Tangential fretting wear
Holding structure
Zirconium alloy cladding
Wear scar
作者简介
任全耀(1991—),男,博士研究生,现主要从事核燃料组件设计及性能分析方面研究,E-mail:renquanyao@foxmail.com
