He nanobubble driven W surface growth during low-energy He ion irradiations
Author:
Funder
National Natural Science Foundation of China
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference35 articles.
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2. Motion of W and He atoms during formation of W fuzz;Doerner;Nucl. Fusion,2018
3. The influence of plasma-surface interaction on the performance of tungsten at the ITER divertor vertical targets;De. Temmerman;Plasma Phys. Control. Fusion,2018
4. Surface morphology of tungsten exposed to helium plasma at temperatures below fuzz formation threshold 1073 K;Sakamoto;Nucl. Fusion,2017
5. The evolution of He nanobubbles in tungsten under fusion-relevant He ion irradiation conditions;Bi;Nucl. Fusion,2019
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1. Temperature dependence of surface microstructure of 316 L stainless steel exposed to low-energy hydrogen ion irradiation;Fusion Engineering and Design;2023-11
2. An improved model for the prediction of He bubbles driven W fuzz growth at different temperatures;Journal of Nuclear Materials;2023-08
3. Initial growth of tungsten fuzz induced by bubble-driven surface stress layer under helium irradiation;Plasma Physics and Controlled Fusion;2023-05-25
4. W nano-fuzz growth by high-flux He ion irradiation with their energy above 300 eV;Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms;2022-06
5. Evaluating surface damage behavior of W-(Y0.9La0.1)2O3 composites during spark plasma sintering process improvement;Journal of Nuclear Materials;2022-01
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