Liquid lithium self-cooled breeding blanket design for ITER-Reference-Cited by-同舟云学术

Liquid lithium self-cooled breeding blanket design for ITER

Published:1998-09 Issue: Volume:39-40 Page:669-674
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Kirillov I.R,Danilov I.V,Sidorenkov S.I,Strebkov Yu.S,Mattas R.F,Gohar Y,Hua T.Q,Smith D.L

Publisher

Elsevier BV

Subject

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

Reference16 articles.

1. ITER blanket designs;Gohar;Fusion Eng. Des.,1995

2. I.R. Kirillov, S.I. Sidorenkov, D.L. Smith, T.Q. Hua (Eds.), Development of ITER Li/V advanced blanket option, RF/US Joint Final Report, ITER/RF-US/96/BL, December 1996.

3. Overview of the Russian DEMO plant study;Sokolov;Fusion Eng. Des.,1995

4. F. Najmabadi, R.W. Conn, ARIES Team, The ARES-II and ARES-IV second stability Tokamak reactors, Fusion Technol. 21 (1992) 1721–1728.

5. M.S. Tillack and the ARIES team, STARLITE engineering overview, Proceedings of the 19th Symposium on Fusion Technology, Lisboa, Portugal, 1996, p. 546.

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