Surface damage evolution during helium plasma irradiation of W-Y2O3 composite materials in different grain orientations

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-06-01 Epub Date: 2025-04-21 DOI:10.1016/j.jnucmat.2025.155840

Zhen Liu , Guo-Qing Wei , Wei Ye , Gang Yao , Yi-Fan Zhang , Lai-Ma Luo , Yu-Cheng Wu

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Abstract

Tungsten (W) is the preferred material for first walls. In this study, a linear plasma device was employed to irradiate two surfaces of a W-Y₂O₃ (WYO) composite rod with low-energy helium plasma, with one surface perpendicular and the other parallel to the rod’s axial direction. The evolution of surface damage on WYO due to plasma irradiation was characterized by scanning electron microscopy, while the effect of grain orientation on irradiation damage resistance was analyzed through electron backscatter diffraction and white light interferometry. Results reveal that under varying irradiation doses, the surface of polycrystalline W exhibits three distinct morphologies: wavy, pyramidal, and step-like structures. A comparison of the two surfaces shows that the extent of irradiation damage is highly dependent on grain orientation. Specifically, grains oriented along the [101] direction demonstrate the strongest resistance to irradiation damage, whereas those with a [111] orientation exhibit the weakest resistance. Further analysis suggests that differences in atomic binding energies on various crystal planes, along with the channeling effect of adjacent planes, may significantly influence the observed surface morphologies.

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不同晶粒取向W-Y2O3复合材料在氦等离子体辐照下的表面损伤演变

钨(W)是第一面墙的首选材料。在本研究中，利用线性等离子体装置对W-Y2O3 （WYO）复合材料棒进行低能氦等离子体辐照，一个表面垂直于棒的轴向，另一个表面平行于棒的轴向。采用扫描电镜对等离子体辐照下WYO表面损伤的演变进行了表征，并通过电子背散射衍射和白光干涉法分析了晶粒取向对辐照损伤抗力的影响。结果表明，在不同的辐照剂量下，多晶钨的表面呈现出三种不同的形态：波浪形、金字塔形和阶梯状结构。两种表面的比较表明，辐照损伤程度与晶粒取向密切相关。具体来说，沿[101]取向的晶粒对辐照损伤的抵抗力最强，而沿[111]取向的晶粒的抵抗力最弱。进一步分析表明，不同晶体平面上原子结合能的差异，以及相邻平面的通道效应，可能会显著影响观察到的表面形貌。

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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.