Tritium retention to the first wall of JT-60U-Reference-Cited by-同舟云学术

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Tritium retention to the first wall of JT-60U

Published:2013-06 Issue:5 Volume:88 Page:295-298
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Adachi Ayumu,Yoshida Masafumi,Takeishi Toshiharu,Tanabe Tetsuo,Hayashi Takao,Nakano Tomohide,Fukumoto Masakatsu,Yagyuu Jyunichi,Miyo Yasuhiko,Masaki Kei,Itami Kiyoshi

Publisher

Elsevier BV

Subject

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

Reference8 articles.

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

2. Hydrogen and deuterium in graphite limiters from TFTR, PDX and PLT

3. Characterization of in-vessel hydrogen isotope retention of JT-60U

4. Hydrogen Retention in and Release from Carbon Materials

5. Tritium distribution in JT-60U W-shaped divertor

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