中国物理B ›› 2020, Vol. 29 ›› Issue (10): 105202-.doi: 10.1088/1674-1056/ab9c09

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Yang-Yi-Peng Song(宋阳一鹏)1, Wen-Bin Qiu(邱文彬)1, Long-Qing Chen(陈龙庆)1, Xiao-Liang Yang(杨晓亮)1, Hao Deng(邓浩)1, Chang-Song Liu(刘长松)2, Kun Zhang(张坤)1,†(), Jun Tang(唐军)1,‡()   

  • 收稿日期:2020-02-24 修回日期:2020-05-28 接受日期:2020-06-12 出版日期:2020-10-05 发布日期:2020-10-05
  • 通讯作者: Kun Zhang(张坤), Jun Tang(唐军)

Hardening effect of multi-energyW2+-ion irradiation on tungsten–potassium alloy

Yang-Yi-Peng Song(宋阳一鹏)1, Wen-Bin Qiu(邱文彬)1, Long-Qing Chen(陈龙庆)1, Xiao-Liang Yang(杨晓亮)1, Hao Deng(邓浩)1, Chang-Song Liu(刘长松)2, Kun Zhang(张坤)1,†, and Jun Tang(唐军)1,‡   

  1. 1 Key Laboratory of Radiation Physics and Technology of Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, China
    2 Key Laboratory of Materials Physics, Institute of Solid State Physics, Chinese Academy of Sciences, Hefei 230031, China
  • Received:2020-02-24 Revised:2020-05-28 Accepted:2020-06-12 Online:2020-10-05 Published:2020-10-05
  • Contact: Corresponding author. E-mail: kzhang@scu.edu.cn Corresponding author. E-mail: tangjun@scu.edu.cn
  • About author:
    †Corresponding author. E-mail: kzhang@scu.edu.cn
    ‡Corresponding author. E-mail: tangjun@scu.edu.cn
    * Project supported by the National Natural Science Foundation of China (Grant Nos. 11975160 and 11775149). One of the authors, Kun Zhang, was supported by the Fundamental Research Funds for the Central Universities, China.

Abstract:

Tungsten is one of the most promising plasma-facing materials (PFMs) to be used in the nuclear fusion reactor as divertor material in the future. In this work, W2+-ions bombardment is used to simulate the neutron irradiation damage to commercial pure tungsten (W) and rolled tungsten–potassium (W–K). The 7 MeV of 3 × 1015 W2+-ions/cm2, 3 MeV of 4.5 × 1014 W2+, and 2 MeV of 3 × 1014 W2+-ions/cm2 are applied at 923 K in sequence to produce a uniform region of 100 nm–400 nm beneath the sample surface with the maximum damage value of 11.5 dpa. Nanoindentation is used to inspect the changes in hardness and elastic modulus after self-ion irradiation. Irradiation hardening occurred in both materials. The irradiation hardening of rolled W–K is affected by two factors: one is the absorption of vacancies and interstitial atoms by potassium bubbles, and the other is the interaction between potassium bubbles and dislocations. Under the condition of 11.5 dpa, the capability of defect absorption can reach a threshold. As a result, dislocations finally dominate the hardening of rolled W–K. Specific features of dislocation loops in W–K are further observed by transmission electron microscopy (TEM) to explain the hardening effect. This work might provide valuable enlightenment for W–K alloy as a promising plasma facing material candidate.

Key words: plasma facing material, tungsten-potassium alloy, ion-irradiation hardening, nanoindentation

中图分类号:  (Power exhaust; divertors)

  • 52.55.Rk
61.80.Jh (Ion radiation effects) 28.52.Fa (Materials)