Surface morphology and deuterium retention in tungsten exposed to high flux D plasma at high temperatures-Reference-Cited by-同舟云学术

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Surface morphology and deuterium retention in tungsten exposed to high flux D plasma at high temperatures

Published:2015-02 Issue: Volume:457 Page:213-219
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Jia Y.Z.,De Temmerman G.,Luo G.-N.,Xu H.Y.,Li C.,Fu B.Q.,Liu W.

Funder

National Magnetic Confinement Fusion Science Program of China

Publisher

Elsevier BV

Subject

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

Reference26 articles.

1. Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

2. Blister formation of tungsten due to ion bombardment

3. The influence of displacement damage on deuterium retention in tungsten exposed to plasma

4. Blister formation on tungsten surface under low energy and high flux hydrogen plasma irradiation in NAGDIS-I

5. Influence of blistering on deuterium retention in tungsten irradiated by high flux deuterium 10–100eV plasmas

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1. Microstructural evolution and hardening of W-ZrC, W-1Re-ZrC and W-3Re-ZrC alloys induced by He ions irradiation;Nuclear Materials and Energy;2024-09

2. Blistering and retention behavior of laser powder bed fused tungsten alloys under hydrogen plasma irradiation;Journal of Nuclear Materials;2024-07

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

4. Bimodal structured chromium-tungsten composite as plasma-facing materials: Sinterability, mechanical properties, and deuterium retention assessment;Acta Materialia;2024-01

5. Surface blistering and deuterium retention in chemical vapor deposition tungsten exposed to deuterium plasma;Nuclear Materials and Energy;2023-12

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