LOCA事故工况下锆包壳的高温氧化行为研究进展

赵琬倩; 贾玉振; 裴静远; 李国庆; 吕俊男; 张君松; 廖京京; 彭倩

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

LOCA事故工况下锆包壳的高温氧化行为研究进展

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

中国核动力研究设计院反应堆燃料及材料重点实验室，成都，610213

基金项目: 国家自然科学基金项目（52101104）

详细信息

作者简介:
赵琬倩（1990—），女，博士研究生，现主要从事反应堆燃料及材料相关研究，E-mail: wanqianzhao@126.com

中图分类号: TL334
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出版历程
- 收稿日期: 2022-12-21
- 修回日期: 2023-04-19
- 刊出日期: 2023-06-15

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

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

摘要

摘要: 锆合金是被广泛地用于水冷动力堆反应的包壳材料。锆合金包壳在失水事故（LOCA）极端事故工况下的高温行为成为国内外学者研究和讨论的热点。本文综述了近年来国内外锆合金的高温氧化行为研究进展，详述了氧化动力学特征、氧化失稳现象和氧化转折机理，同时概述了近10 年中国核动力研究设计院（NPIC）的相关研究工作。本文报道的研究进展，尤其是对于转折机理的探讨，可为进一步提高国产化新型锆合金使用性能提供研发指导。
- 锆合金 /
- 包壳 /
- 失水事故（LOCA） /
- 事故工况 /
- 氧化行为 /
- 转折机理
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

HTML全文

图 1 模拟LOCA事故试验温度曲线与XRD测试温度曲线

Figure 1. Temperature Curves of Simulated LOCA Test and XRD Test

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图 2 Hyun-Gil Kim发现氢化物在α-Zr(O)层边界处形成

Figure 2. Hyun-Gil Kim Found Hydride Formed at Boundary of α-Zr(O) Layer

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图 3 “氢致转折”机理图

Figure 3. Schematic Diagram of Transition Caused by Hydrogen　　　　　　

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图 4 t→m相变诱发氧化失稳示意图^[28]

①、②、③—O/M波纹状界面，代表不同反应阶段O/M附近晶粒组织特征不同；surface—氧化膜-腐蚀环境界面；O/M interface—氧化物/金属的内表面

Figure 4. Schematic Diagram of Mechanism of Oxidation Breakaway Induced by t→m Phase Transition

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图 5 锆合金氧化膜/基体力学弯曲模型图^[29]

w—Zr合金基底层的宽度；r—中性轴的初始曲率半径；$ \theta $—简化弯曲弯曲梁的挠度；h₁—Zr合金的基体层的厚度；h₂—氧化膜的厚度；x—锆合金氧化前的中心厚度；O—建立坐标系的圆点

Figure 5. Mechanical Bending Model of Zirconium Alloy Oxidation Film/Matrix

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