An overview of US ITER test blanket module program-Reference-Cited by-同舟云学术

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An overview of US ITER test blanket module program

Published:2006-02 Issue:1-7 Volume:81 Page:433-441
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Ying A.,Abdou M.,Wong C.,Malang S.,Morley N.,Sawan M.,Merrill B.,Sze D.K.,Kurtz R.,Willms S.,Ulrickson M.,Zinkle S.

Publisher

Elsevier BV

Subject

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

Reference14 articles.

1. Technical issues and requirements of experiments and facilities for fusion nuclear technology;Abdou;Nucl. Fusion,1987

2. The helium cooled lithium lead blanket test proposal in ITER and requirements on test blanket modules instrumentation;Li Puma;Fusion Eng. Des.,2005

3. US plans and strategy for ITER blanket testing;Abdou;Fusion Sci. Technol.,2005

4. The EU advanced dual coolant blanket concept;Norajitra;Fusion Eng. Des.,2002

5. High performance PbLi blanket;Tillack,1997

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