Thermal desorption behavior of deuterium for 6 MeV Fe ion irradiated W with various damage concentrations-Reference-Cited by-同舟云学术

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Thermal desorption behavior of deuterium for 6 MeV Fe ion irradiated W with various damage concentrations

Published:2015-06 Issue: Volume:461 Page:336-340
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Oya Yasuhisa,Li Xiaochun,Sato Misaki,Yuyama Kenta,Zhang Long,Kondo Sosuke,Hinoki Tatsuya,Hatano Yuji,Watanabe Hideo,Yoshida Naoaki,Chikada Takumi

Publisher

Elsevier BV

Subject

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

Reference26 articles.

1. Recent progress in research on tungsten materials for nuclear fusion applications in Europe

2. Tungsten as material for plasma-facing components in fusion devices

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

4. Hydrogen in tungsten as plasma-facing material

5. The effect of displacement damage on deuterium retention in ITER-grade tungsten exposed to low-energy, high-flux pure and helium-seeded deuterium plasmas

Cited by 43 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Characterization of Vacancy Defects Using TEM in Heavy-Ion-Irradiated Tungsten Foils;Metallurgical and Materials Transactions A;2024-06-05

2. Hydrogen Traps in Tungsten: A Review;Physics of Metals and Metallography;2024-03

3. Mechanism of hydrogen isotope exchange for tritium removal in plasma-facing materials: a multi-scale investigation;Nuclear Fusion;2024-02-23

4. Thermal annealing effect on D retention for damaged W-10%Re alloy;Fusion Engineering and Design;2023-11

5. A critical review of experiments on deuterium retention in displacement-damaged tungsten as function of damaging dose;Materials Research Express;2023-10-01

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