Preliminary design of lithium lead test blanket module for the Chinese Experimental Advanced Superconducting Tokamak-Reference-Cited by-同舟云学术

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Preliminary design of lithium lead test blanket module for the Chinese Experimental Advanced Superconducting Tokamak

Published:2007-10 Issue:15-24 Volume:82 Page:2347-2352
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Liu Songlin,Bai Yunqing,Zheng Shanliang,Chen Hongli,Wang Weihua,Long Pengcheng,Wu Yican

Publisher

Elsevier BV

Subject

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

Reference17 articles.

1. Blanket system selection for ARIES ST;Sze;Fusion Eng. Des.,2000

2. The European power plant conceptual study: Helium-cooled lithium–lead reactor concept;Sardain;Fusion Eng. Des.,2006

3. Conceptual design of the dual-coolant blanket in the frame of the EU power plant conceptual study;Norajitra;Fusion Eng. Des.,2003

4. HCLL TBM for ITER-design studies;Rampal;Fusion Eng. Des.,2005

5. Design approach for the main ITER test blanket modules for the EU helium cooled lithium-lead blankets;Rampal;Fusion Eng. Des.,2006

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2. Preliminary study of HDA coating on CLAM steel followed by high temperature oxidation;Journal of Nuclear Materials;2013-11

3. Corrosion behavior of CLAM steel in static and flowing LiPb at 480°C and 550°C;Fusion Engineering and Design;2011-10

4. Overview of liquid lithium lead breeder blanket program in China;Fusion Engineering and Design;2011-10

5. Effects of an ultrasonically excited TIG arc on CLAM steel weld joints;The International Journal of Advanced Manufacturing Technology;2011-09-08

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