Coupled Thermomechanical Responses of Zirconium Alloy System Claddings under Neutron Irradiation

Zirconium (Zr) alloy is a promising fuel cladding material used widely in nuclear reactors. Usually, it is in service for a long time under the effects of neutron radiation with high temperature and high pressure, which results in thermomechanical coupling behavior during the service process. Focusi...

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Bibliographic Details
Main Authors: Hui Zhao, Chong Yang, Dongxu Guo, Lu Wu, Jianjun Mao, Rongjian Pan, Jiantao Qin, Baodong Shi
Format: Article
Language:English
Published: MDPI AG 2021-02-01
Series:Applied Sciences
Subjects:
Online Access:https://www.mdpi.com/2076-3417/11/3/1308