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

Pang Hua; Li Yipeng; Lyv Liangliang; Zhang Xiang; Zhao Yanli; Zhang Jibin; Peng Hang; Zhang Hongzhi; Sun Zhipeng; Chen Jie

doi:10.13832/j.jnpe.2021.06.0248

Volume 42 Issue 6

Dec. 2021

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Pang Hua, Li Yipeng, Lyv Liangliang, Zhang Xiang, Zhao Yanli, Zhang Jibin, Peng Hang, Zhang Hongzhi, Sun Zhipeng, Chen Jie. Study on the Evolution of Dislocation Loop under Zirconium Alloy In-Situ Ion Irradiation[J]. Nuclear Power Engineering, 2021, 42(6): 248-253. doi: 10.13832/j.jnpe.2021.06.0248

Citation:

Pang Hua, Li Yipeng, Lyv Liangliang, Zhang Xiang, Zhao Yanli, Zhang Jibin, Peng Hang, Zhang Hongzhi, Sun Zhipeng, Chen Jie. Study on the Evolution of Dislocation Loop under Zirconium Alloy In-Situ Ion Irradiation[J]. Nuclear Power Engineering, 2021, 42(6): 248-253. doi: 10.13832/j.jnpe.2021.06.0248

Citation:

Pang Hua, Li Yipeng, Lyv Liangliang, Zhang Xiang, Zhao Yanli, Zhang Jibin, Peng Hang, Zhang Hongzhi, Sun Zhipeng, Chen Jie. Study on the Evolution of Dislocation Loop under Zirconium Alloy In-Situ Ion Irradiation[J]. Nuclear Power Engineering, 2021, 42(6): 248-253. doi: 10.13832/j.jnpe.2021.06.0248

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

doi: 10.13832/j.jnpe.2021.06.0248

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

Received Date: 2021-07-12
Rev Recd Date: 2021-08-18
Publish Date: 2021-12-09

Abstract

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

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References(16)

References

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