The test facility for the ITER TF model coil-Reference-Cited by-同舟云学术

The test facility for the ITER TF model coil

Published:1998-09 Issue:1-4 Volume:41 Page:213-221
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Komarek P,Salpietro E

Publisher

Elsevier BV

Subject

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

Reference5 articles.

1. The IEA large coil task;S Beard;Fusion Eng. Des.,1988

2. The POLO coil: a prototype tokamak poloidal field coil, design features and test results;Darweschsad;IEEE Trans. Magn.,1996

3. M. Darweschsad, G. Dittrich, A. Grunhagen, S. Fink, et. al., Operation of the upgraded TOSKA facility and test results of the EU-LCT coil cooled with forced flow helium II at supercritical pressure, Proc. 19th Symp. Fusion Technol. (SOFT 19), Lisboa, 16–20 September 1996.

4. J. Sapper, et al., The Wendelstein 7-X Stellarator, technical design and engineering, Proc. 19th Symp. Fusion Technol. (19th SOFT), Lisboa, 16–20 September 1996.

5. Superconducting model coil for the Stellarator W 7-X under test;Jungst;IEEE Trans. Magn.,1996

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4. Power dissipation and energy transfer during testing of the ITER toroidal field model coil;Fusion Engineering and Design;2005-11

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