Researching | Chemical interaction layer between uranium oxide fuel pellet and zirconium alloy cladding in pressurized water reactor

NUCLEAR TECHNIQUES, Volume. 46, Issue 9, 090602(2023)

Chemical interaction layer between uranium oxide fuel pellet and zirconium alloy cladding in pressurized water reactor

Huacai WANG^*, Dawei YANG, Huanlin CHENG, Qi TANG, Wei WANG, and Jin QIAN

Author Affiliations

China Institute of Atomic Energy, Beijing 102413, China

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References (22)

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References(22)

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Huacai WANG, Dawei YANG, Huanlin CHENG, Qi TANG, Wei WANG, Jin QIAN. Chemical interaction layer between uranium oxide fuel pellet and zirconium alloy cladding in pressurized water reactor[J]. NUCLEAR TECHNIQUES, 2023, 46(9): 090602

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Paper Information

Category: Research Articles

Received: Feb. 10, 2023

Accepted: --

Published Online: Oct. 8, 2023

The Author Email: WANG Huacai (wanghc1986@163.com)

DOI:10.11889/j.0253-3219.2023.hjs.46.090602

Topics

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