Surface condition effects on tritium permeation through the first wall of a water-cooled ceramic breeder blanket-Reference-Cited by-同舟云学术

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Surface condition effects on tritium permeation through the first wall of a water-cooled ceramic breeder blanket

Published:2016-11 Issue: Volume:109-111 Page:586-589
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Zhou H.-S.,Xu Y.-P.,Liu H.-D.,Liu F.,Li X.-C.,Zhao M.-Z.,Qi Q.,Ding F.,Luo G.-N.

Funder

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

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

Reference22 articles.

1. The effect of surface composition on plasma driven permeation of deuterium through 304 stainless steel;Causey;J. Nucl. Mater.,1984

2. Influence of surface impurities on plasma-driven permeation of deuterium through nickel;Hatano;J. Vac. Sci. Technol. A,1998

3. Hydrogen plasma-driven permeation through a reduced activation ferritic steel alloy F82H;Zhou;Fusion Sci. Technol.,2013

4. Surface effects on plasma-driven tritium permeation through metals;Ogorodnikova;J. Nucl. Mater.,2001

5. Conceptual design of a water cooled breeder blanket for CFETR;Liu;Fusion Eng. Des.,2014

Cited by 2 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. Plasma exposure behavior of re-deposited tungsten on structural materials of fusion reactors;Journal of Nuclear Materials;2017-05

2. Gas-driven permeation of deuterium through tungsten with different microstructures;Fusion Engineering and Design;2016-12

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