Research Progress on High Temperature Oxidation Behavior of Zirconium Cladding under LOCA Condition

Zhao Wanqian; Jia Yuzhen; Pei Jingyuan; Li Guoqing; Lyu Junnan; Zhang Junsong; Liao Jingjing; Peng Qian

doi:10.13832/j.jnpe.2023.S1.0119

Volume 44 Issue S1

Jun. 2023

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Article Navigation > Nuclear Power Engineering > 2023 > 44(S1): 119-124

Zhao Wanqian, Jia Yuzhen, Pei Jingyuan, Li Guoqing, Lyu Junnan, Zhang Junsong, Liao Jingjing, Peng Qian. Research Progress on High Temperature Oxidation Behavior of Zirconium Cladding under LOCA Condition[J]. Nuclear Power Engineering, 2023, 44(S1): 119-124. doi: 10.13832/j.jnpe.2023.S1.0119

Citation:

Zhao Wanqian, Jia Yuzhen, Pei Jingyuan, Li Guoqing, Lyu Junnan, Zhang Junsong, Liao Jingjing, Peng Qian. Research Progress on High Temperature Oxidation Behavior of Zirconium Cladding under LOCA Condition[J]. Nuclear Power Engineering, 2023, 44(S1): 119-124. doi: 10.13832/j.jnpe.2023.S1.0119

Citation:

Zhao Wanqian, Jia Yuzhen, Pei Jingyuan, Li Guoqing, Lyu Junnan, Zhang Junsong, Liao Jingjing, Peng Qian. Research Progress on High Temperature Oxidation Behavior of Zirconium Cladding under LOCA Condition[J]. Nuclear Power Engineering, 2023, 44(S1): 119-124. doi: 10.13832/j.jnpe.2023.S1.0119

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Research Progress on High Temperature Oxidation Behavior of Zirconium Cladding under LOCA Condition

doi: 10.13832/j.jnpe.2023.S1.0119

Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610213, China

Received Date: 2022-12-21
Rev Recd Date: 2023-04-19
Publish Date: 2023-06-15

Abstract

Abstract

Zirconium alloy is a cladding material widely used in water-cooled power reactor. The high temperature behavior of zirconium alloy cladding under the extreme accident condition of loss of coolant accident (LOCA) has become a hot topic of research and being discussed at home and abroad. This paper summarizes the worldwide current research progress on high temperature oxidation behavior of zirconium alloy. The oxidation kinetics characteristics, breakaway oxidation behavior, and the oxidation transition mechanism are described in detail. Meanwhile, the research work of Nuclear Power Institute of China for nearly recent ten years has also been overviewed. The research progress reported in this paper, especially the discussion on the oxidation transition mechanism, will provide a theoretical guidance for developing domestic new zirconium alloys in the further.
- Zirconium alloy,
- Cladding,
- Loss of coolant accident (LOCA),
- Accident conditions,
- Oxidation behavior,
- Transition mechanism

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References(29)

References

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