锆合金原位离子辐照条件下的位错环演化研究

庞华; 李奕鹏; 吕亮亮; 张翔; 赵艳丽; 张吉斌; 彭航; 张宏智; 孙志鹏; 陈杰

doi:10.13832/j.jnpe.2021.06.0248

锆合金原位离子辐照条件下的位错环演化研究

doi: 10.13832/j.jnpe.2021.06.0248

1.
中国核动力研究设计院核反应堆系统设计技术重点实验室，成都，610213
2.
厦门大学能源学院，福建厦门，361102
3.
中国核动力研究设计院核反应堆燃料及材料重点实验室，成都，610213

详细信息

作者简介:
庞　华（1975—），女，研究员级高级工程师，现从事燃料元件设计和研究工作，E-mail: qingwenxiong@foxmail.com

通讯作者:
吕亮亮，E-mail: shinesky@126.com

中图分类号: TL341
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- 被引次数: 0
出版历程
- 收稿日期: 2021-07-12
- 修回日期: 2021-08-18
- 刊出日期: 2021-12-09

Study on the Evolution of Dislocation Loop under Zirconium Alloy In-Situ Ion Irradiation

1.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
2.
College of Energy, Xiamen University, Xiamen, Fujian, 361102, China
3.
Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

摘要

摘要: 位错环演化是核用锆合金辐照组织演化的主要特征之一，对合金辐照后的力学性能（强度、塑性等）有着决定性的影响。目前，锆合金辐照位错环演化的实验研究主要基于离位中子或离子辐照，无法直接观察位错环的演化过程。为了更深入地理解锆合金辐照下的微观组织演化，本工作采用先进的原位离子辐照实验方法，实时观察Zr-2合金位错环的演化过程，揭示不同辐照损伤剂量和温度对演化过程的影响规律，并结合弥散障碍物硬化模型对合金的辐照硬化性能进行了评估，验证了原位离子辐照用于研究锆合金包壳材料辐照后位错环演化和力学性能评价的可行性和先进性。
- 锆合金 /
- 原位辐照 /
- 微观组织演化 /
- 位错环 /
- 力学性能
Abstract: Dislocation loop evolution is one of the major features of the microstructure evolution of nuclear-grade zirconium alloy exposed to irradiation, which determines the mechanical properties (strength, plasticity, etc.) of the alloy after irradiation. To date, experimental researches on the irradiation dislocation loop evolution of zirconium alloy are mainly based on ex-situ neutron or ion irradiation, without a direct observation of the dislocation loop evolution process. To obtain an in-depth understanding of microstructure evolution of zirconium alloy under irradiation, the present work utilizes the advanced in-situ ion irradiation technique for a real-time observation of Zr-2 alloy dislocation loop evolution. As a result, the rule of irradiation dose and temperature dependence of the evolution process has been revealed, and the irradiation hardening effect has been evaluated by applying the dispersed barrier hardening model, the feasibility and advancement of the in-situ ion irradiation technique on studying dislocation loop evolution and mechanical property evaluation of zirconium alloy cladding materials after irradiation is demonstrated.
- Zirconium alloy /
- In-Situ irradiation /
- Microstructure evolution /
- Dislocation loop /
- Mechanical properties

HTML全文

图 1 Zr-2合金在300℃辐照时的<c>型位错环在辐照初期形核和生长的TEM明场像

Figure 1. TEM Bright Field Images Showing Nucleation and Growth of <c> Dislocation Loops in Zr-2 Alloy at the Early Stage of Irradiation at 300℃　　　　

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图 2 Zr-2合金在300℃辐照时的<c>型位错环在辐照中后期生长和合并的TEM明场像

Figure 2. TEM Bright Field Images Showing the Growth and Coalescence of <c> Dislocation Loops in Zr-2 Alloy at the Late Stage of Irradiation at 300℃

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图 3 300℃辐照下<c>型位错环的平均尺寸和数密度与辐照损伤剂量之间的关系

Figure 3. The Relationship between Average Size and Number Density and Irradiation Damage of <c> Dislocation Loops under Irradiation at 300℃

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图 4 不同温度下由位错环导致的硬化随辐照损伤剂量的变化关系　　　　

Figure 4. Relationship between Hardening Caused by Dislocation Loops and Irradiation Damage at Different Temperatures

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