Conceptual design on interface between ITER and tritium extraction system of Chinese helium-cooled solid breeder test blanket module-Reference-Cited by-同舟云学术

Conceptual design on interface between ITER and tritium extraction system of Chinese helium-cooled solid breeder test blanket module

Published:2010-12 Issue:10-12 Volume:85 Page:2213-2216
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Zhang Long,Luo Tianyong,Feng Kaiming

Publisher

Elsevier BV

Subject

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

Reference12 articles.

1. K. Feng, G. Zhang, Z. Chen, T. Yuan, X. Wang, J. Yang, et al., Design Description Document for the Chinese Helium Cooled Solid Breeder (CN HCSB) Test Blanket Module (Version IV), SWIP, 2007.

2. Tritium safety consideration in the design of tritium systems for China HCSB and DFLL TBMs;Chen;Fusion Eng. Des.,2008

3. The ITER tritium systems;Glugla;Fusion Eng. Des.,2007

4. Chemical form of released tritium from solid breeder materials under the various purge gas conditions;Kinjyo;Fusion Eng. Des.,2007

5. Use of magnesium for recovering hydrogen isotopes from tritiated water;Willms,1994

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