Measurement of hydrogen permeation due to atomic flux using permeation probe in the spherical tokamak QUEST-Reference-Cited by-同舟云学术

Measurement of hydrogen permeation due to atomic flux using permeation probe in the spherical tokamak QUEST

Published:2010-11 Issue:6 Volume:85 Page:950-955
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Sharma Sanjeev K.,Zushi Hideki,Takagi Ikuji,Hisano Yuki,Sakamoto Mizuki,Higashizono Yuta,Shikama Taichi,Morita Sigeru,Tanabe Tetsuo,Yoshida Naoaki,Hanada Kazuaki,Hasegawa Makoto,Mitarai Osamu,Nakamura Kazuo,Idei Hiroshi,Sato Kohnosuke N.,Kawasaki Shoji,Nakashima Hisatoshi,Higashijima Aki,Nakashima Yousuke,Nishino Nobuyuki,Hatano Yuji,Sagara Akira,Nakamura Yukio,Ashikawa Naoko,Maekawa Takashi,Kishimoto Yasuaki,Takase Yuichi

Publisher

Elsevier BV

Subject

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

Reference14 articles.

1. Tritium inventory in ITER plasma-facing materials and tritium removal procedures

2. Gas balance and fuel retention in fusion devices

3. Active particle control experiments and critical particle flux discriminating between the wall pumping and fuelling in the compact plasma wall interaction device CPD spherical tokamak

4. Hydrogen isotope retention and recycling in fusion reactor plasma-facing components

5. Plasma driven permeation of tritium in fusion reactors

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1. Atomic and ionic hydrogen flux probe for quantitative in-situ monitoring of hydrogen recycling;Fusion Engineering and Design;2023-04

2. Spatial distribution of atomic and ion hydrogen flux and its effect on hydrogen recycling in long duration confined and non-confined plasmas;Nuclear Materials and Energy;2017-08

3. Characteristic of a pdCu membrane as atomic hydrogen probe for QUEST;Nuclear Materials and Energy;2016-12

4. Hydrogen flux measurements with permeation probes in spherical tokamak QUEST;Vacuum;2016-07

5. Permeation measurements for investigating atomic hydrogen flux and wall pumping/fuelling dynamics in QUEST;Journal of Nuclear Materials;2012-01