Development and validation of models for fuel rod oxidation and hydrogen pick-up behaviors in pressurized water reactor

BackgroundDuring the long-term operation of a nuclear reactor, the contact between zirconium alloy cladding and cooling water results in oxidation reactions and hydrogen uptake-induced embrittlement behavior, which deteriorates the thermal and mechanical properties of the cladding, posing a threat t...

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Bibliographic Details
Main Authors: CHEN Nan, XIANG Fengrui, HE Yanan, WU Yingwei, ZHANG Jing, SU Guanghui, TIAN Wenxi, QIU Suizheng
Format: Article
Language:zho
Published: Science Press 2024-09-01
Series:He jishu
Subjects:
Online Access:http://www.hjs.sinap.ac.cn/zh/article/doi/10.11889/j.0253-3219.2024.hjs.47.090601/
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