Retention and permeation properties of deuterium in tungsten under irradiation of the D–He mixture plasma-Reference-Cited by-同舟云学术

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Retention and permeation properties of deuterium in tungsten under irradiation of the D–He mixture plasma

Published:2018-11 Issue: Volume:136 Page:545-548
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Hayashi Tatsuya,Takimoto Toshikio,Tonegawa Akira,Matsumura Yoshihito,Sato Kohnosuke,Kawamura Kazutaka

Funder

Joint Project

National Institute for Fusion Science

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference17 articles.

1. ITER tungsten divertor design development and qualification program

2. Deuterium retention in single-crystal tungsten irradiated with 10–500 eV/D+

3. Tritium retention in tungsten exposed to intense fluxes of 100 eV tritons

4. Formation process of tungsten nanostructure by the exposure to helium plasma under fusion relevant plasma conditions

5. Observations of suppressed retention and blistering for tungsten exposed to deuterium–helium mixture plasmas

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1. The mechanism of negative and positive hydrogen ions production on the Ni surface;Vacuum;2020-01

2. Effect of annealing on the microstructure behavior of D+-irradiated W-2vol.%TiC composite prepared by wet-chemical method;Fusion Engineering and Design;2019-11

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