Surface blistering and D desorption in high-energy-rate forging W, W-Y2O3, W-TiC exposed to deuterium plasma-Reference-Cited by-同舟云学术

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Surface blistering and D desorption in high-energy-rate forging W, W-Y2O3, W-TiC exposed to deuterium plasma

Published:2024-08 Issue: Volume:596 Page:155079
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Xie X.F.,Xie Z.M.^ORCID,Wang H.^ORCID,Wu S.S.,Luo J.R.,Zhang X.X.,Wang P.,Liu R.,Fang Q.F.,Liu C.S.,Wu X.B.^ORCID

Funder

National Natural Science Foundation of China

Publisher

Elsevier BV

Reference37 articles.

1. Use of tungsten material for the ITER divertor;Hirai;Nucl. Mater. Eng.,2016

2. ITER tungsten divertor design development and qualification program;Hirai;Fusion Eng. Des.,2013

3. Tungsten as first wall material in fusion devices;Kaufmann;Fusion Eng. Des.,2007

4. Blistering behavior and deuterium retention in tungsten vanadium alloys exposed to deuterium plasma in the linear plasma device STEP;Wang;J. Nucl. Mater.,2018

5. Deuterium retention in tungsten and tungsten alloys exposed to pure and impurities seeding deuterium plasma;Zhang;Nucl. Mater. Eng.,2020

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