钾掺杂和曝光温度对大规模掺钾钨中氘行为的影响

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2023-08-15 DOI:10.1016/j.jnucmat.2023.154481

Xiaolei Ma , Chenlu Ye , Ting Wang , Fan Feng , Wei Lv , Shaoting Lang , Changchun Ge , Qingzhi Yan , Huimin Shao , Xiaoxin Zhang

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引用次数: 0

摘要

为了满足未来核聚变电站工程应用的需要，采用粉末冶金和热轧技术制备了厚度为15 mm的新型大体积掺钾钨(WK)板。采用相同的制备工艺制备了纯钨(PW)作为比较材料。为了研究K掺杂和暴露温度对WK和PW中D保留和起泡形貌的影响，我们在不同温度(423、473、523和573 K)下进行了高通量(~ 1022 m−2 s−1)和低能(~ 50 eV) D等离子体暴露。结果表明:在不同的暴露温度下，PW和WK均存在严重的表面起泡现象，且与WK相比，PW形成的水疱尺寸较大，但数量较少;在所有暴露温度下，PW中的D保留量显著低于WK。此外，与PW相比，WK中D水泡和滞留的演变对暴露温度更为敏感。详细分析讨论了K掺杂和暴露温度对起泡形貌和D保留的影响。

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Effect of potassium doping and exposure temperature on the deuterium behavior in large-scale potassium-doped tungsten

In order to meet the needs of future fusion power plants in engineering application, a newly large-volume potassium-doped tungsten (WK) plate with a thickness of 15 mm was prepared by powder metallurgy and hot rolling technology. Pure tungsten (PW) as a comparison material was prepared using the same preparation process. To figure out the effect of K doping and exposure temperature on D retention and blistering morphology in WK and PW, the high-flux (∼10²² m⁻² s⁻¹) and low energy (∼ 50 eV) D plasma exposure with different temperatures (423, 473, 523 and 573 K) was performed. The results show that there is serious surface blistering in both PW and WK at all exposure temperatures and PW forms D blisters larger in size but smaller in number compared with WK. The D retention in PW is significantly lower than that in WK at all exposure temperatures. Moreover, the evolution of D blisters and retention in WK is more sensitive to exposure temperature compared to PW. The effects of K doping and exposure temperature on blistering morphology and D retention were analyzed and discussed in detail.

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来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.