重庆理工大学学报2024，Vol.38Issue(17)：227-235,9.DOI:10.3969/j.issn.1674-8425(z).2024.09.028
核反应堆刚凸-包壳微动损伤裂纹行为研究
Study on fretting damage crack behavior of dimple-cladding in nuclear reactor
摘要
Abstract
The fretting behavior between the cladding tube and the rigid convex in the nuclear fuel rod assembly may cause the failure of the assembly,and even threaten the safety of the reactor.This paper takes the dimple-cladding structure in the nuclear fuel rod assembly as the research object to address the crack initiation and propagation under the fretting behavior of rigid-cladding.It employs the finite element simulation method.Our results show the contact area of the cladding tube is consistently under pressure during the circular moving fretting process.The crack is controlled by shear stress in the slip regime,which initiates at the interface between cladding coating and substrate and propagates along the interface,even causing the coating delamination.While in the mix regime and partial slip regime,cracks initiate at the surface or sub-surface of the cladding and propagate to the interior of the cladding,which are controlled by both shear stress and normal stress.Our results show the shear stress is the main cause of the damage of the cladding tube,and plays a primary role in the initiation and propagation of cracks in the fretting behavior of rigid-cladding structures.关键词
刚凸-包壳结构/微动/裂纹萌生/裂纹扩展Key words
rigid-cladding structure/fretting/crack initiation/crack propagation分类
能源科技引用本文复制引用
崔筱婷,王宇星,廖业宏,沈火明,任啟森,刘娟,彭振驯,黄恒..核反应堆刚凸-包壳微动损伤裂纹行为研究[J].重庆理工大学学报,2024,38(17):227-235,9.基金项目
国家自然科学基金青年基金项目(12402113) （12402113）
四川省自然科学基金青年基金项目(2023NSFC1300) （2023NSFC1300）
四川省自然科学基金重点项目(2024NSFC0037) （2024NSFC0037）
