严重塑性变形对受低能氦离子辐照的钨表面改性的影响

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Yashan Guo , Ning Guo , Ao Zhang , Kemin Xue , Ping Li
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引用次数: 0

摘要

系统研究了多晶 W 在 823 K ∼ He 等离子体暴露(∼ 50 eV)后表面形貌的取向依赖性。研究结果表明,在 823 K ∼ He 等离子体暴露(∼ 50 eV)后,W 晶体形成了五种不同的起伏形态,起伏的边缘方向与〈100〉取向平行。建立了晶体取向、起伏高度和起伏间隔之间的关系,并引入了间隔系数。起伏间隔和起伏间隔系数逐渐增大,直到倾斜角增大到 36°。经过剧烈塑性变形(SPD)后,起伏高度从原始 W 的 5.7 nm 增加到 SPD 后 W 的 11.9 nm,SPD 后晶粒的表面粗糙度也显著增加。减少带有{100}平面的晶粒和抑制不稳定纳米结构的形成有助于减缓 W 的体积损失和提高其抗辐照性能。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Effect of severe plastic deformation on surface modification of tungsten exposed to low energy helium ion irradiation
The orientation dependence of the surface morphology for polycrystalline W after the He plasma exposure (∼ 50 eV) at ∼ 823 K was systematically investigated. Five different types of undulating morphologies were formed and the edge direction of the undulations was parallel to the 〈100〉 orientation. The relationship among crystal orientation, undulating height and undulating interval was established and the interval coefficient was introduced. The interval and the interval coefficient gradually increase until the tilting angle increases to 36 °. After severe plastic deformation (SPD), the undulating height increased from 5.7 nm for the as-received W to 11.9 nm for the SPDed W and the surface roughness of the SPDed grains increased significantly. Reducing the grains with the {100} plane and inhibiting the formation of unstable nanostructures are helpful to slow down the volume loss of W and improve its irradiation resistance.
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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