TEM Examination of M5 Zirconium Alloy Cladding of Spent Fuel Rod

TEM Examination of M5 Zirconium Alloy Cladding of Spent Fuel Rod

The zirconium alloy cladding of PWR fuel rods which undergo high neutron irradiation during service, will cause significant changes in its microstructure, thereby affecting its macroscopic performance. Therefore, the study of neutron irradiation behavior of zirconium alloy cladding is a focus of nuc...

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Bibliographic Details
Main Author:	QIAN Jin, BIAN Wei, GUO Yifan, WANG Xin, LIANG Zhengqiang
Format:	Article
Language:	English
Published:	Editorial Board of Atomic Energy Science and Technology 2024-01-01
Series:	Yuanzineng kexue jishu
Subjects:	post irradiation examination tem pressurized-water reactor zirconium alloy fuel rod neutron irradiation hot cell
Online Access:	https://yznkxjs.xml-journal.net/cn/article/doi/10.7538/yzk.2023.youxian.0112

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