材料科学
钨
辐照
通量
氘
离子
等离子体
钾
分析化学(期刊)
复合材料
冶金
原子物理学
化学
色谱法
物理
有机化学
量子力学
核物理学
作者
Xiaolei Ma,Xiaoxin Zhang,Ting Wang,Yuan Gao,Yue Yuan,Long Cheng,Jipeng Zhu,Linhuan Wei,Shaoting Lang,Changchun Ge,Qingzhi Yan
出处
期刊:Nuclear Fusion
[IOP Publishing]
日期:2022-11-21
卷期号:63 (2): 026013-026013
被引量:1
标识
DOI:10.1088/1741-4326/aca48c
摘要
Abstract A large-size potassium-doped tungsten (KW) plate with a thickness of 15 mm was fabricated via powder metallurgy technology and hot rolling. In order to appraise the irradiation resistance of KW, the surface deuterium (D) blistering and D retention were studied on Fe 11+ pre-damaged (0, 0.05 and 0.5 dpa) KW and pure tungsten (PW), which were exposed to ∼60 eV and ∼5 × 10 21 m −2 s −1 D plasmas at 500 K at a fluence of ∼5.76 × 10 25 m −2 . The results indicate that the KW alloy can better inhibit the generation of vacancy defects after Fe 11+ ion damage compared with PW because K bubbles can restrain the migration of W self-interstitial atoms and the accumulation of vacancies caused during Fe 11+ ion irradiation. The Fe 11+ ion pre-damage can relieve the surface blistering and D retention of PW and KW at the same time, and the KW has a better effect of inhibiting D retention, while it does not show a significant advantage in inhibiting surface blistering compared with PW. In addition, the causes of the discrepancy in total D retention and the surface morphology evolution of PW and KW are discussed in detail.
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