The test facility for the ITER TF model coil

Fusion Engineering and Design

Volumn 41, Issue 1-4, 1998, Pages 213-221

  Komarek, P ^a   Salpietro, E ^b  

^a KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

^b MAX PLANCK INSTITUT FÜR PLASMAPHYSIK   (Germany)

Author keywords

[No Author keywords available]

Indexed keywords

CRYOGENIC EQUIPMENT; ELECTRIC POWER SUPPLIES TO APPARATUS; EXPERIMENTAL REACTORS; PUMPS; REACTOR SHIELDING; REFRIGERATORS; VACUUM TECHNOLOGY;

INTERNATIONAL THERMONUCLEAR EXPERIMENTAL REACTORS (ITER); VACUUM VESSELS;

FUSION REACTORS;

EID: 0032475156     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0920-3796(98)00116-1     Document Type: Article

References (5)

1. D. S Beard, W. Klose, S. Shimamoto, G. Vescey, The IEA large coil task, Fusion Eng. Des. 7 (1988) 1-232.
2. M. Darweschsad, R. Heller, G. Friesinger, M. Irmisch, et al., The POLO coil: a prototype tokamak poloidal field coil, design features and test results, IEEE Trans. Magn. 32 (1996) 2256-2259.
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. K.-P. Jungst, et al., Superconducting model coil for the Stellarator W 7-X under test, IEEE Trans. Magn. 32 (4) (1996) 2296-2298.