Temperature dependence of surface morphology and deuterium retention in polycrystalline ITER-grade tungsten exposed to low-energy, high-flux D plasma-Reference-Cited by-同舟云学术

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Temperature dependence of surface morphology and deuterium retention in polycrystalline ITER-grade tungsten exposed to low-energy, high-flux D plasma

Published:2012-01 Issue:1-3 Volume:420 Page:519-524
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Alimov V.Kh.,Tyburska-Püschel B.,Lindig S.,Hatano Y.,Balden M.,Roth J.,Isobe K.,Matsuyama M.,Yamanishi T.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference21 articles.

1. Key ITER plasma edge and plasma–material interaction issues

2. Design study of fusion DEMO plant at JAERI

3. Recent Advances on Hydrogen Retention in ITER’s Plasma-Facing Materials: Beryllium, Carbon, and Tungsten

4. The effect of ion damage on deuterium trapping in tungsten

5. Blister formation and deuterium retention on tungsten exposed to low energy and high flux deuterium plasma

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1. Surface blistering and D desorption in high-energy-rate forging W, W-Y2O3, W-TiC exposed to deuterium plasma;Journal of Nuclear Materials;2024-08

2. Molecular dynamics investigation of dislocation-hydrogen/helium interactions in tungsten;Journal of Nuclear Materials;2024-04

3. Initial microstructure and temperature dependence of irradiation defects evolution in tungsten;Journal of Nuclear Materials;2024-04

4. Defect production in tungsten under sub-threshold energy irradiation: role of hydrogen and surface effects;Nuclear Fusion;2024-03-15

5. The effect of High-Temperature Pre-Damage on Vacancy-Type defects and deuterium retention in tungsten;Nuclear Materials and Energy;2024-03

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