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Volumn 46, Issue 2-4, 1999, Pages 129-150

ITER magnet design and R&D

Author keywords

[No Author keywords available]

Indexed keywords

COST EFFECTIVENESS; CRITICAL CURRENTS; DESIGN; ELECTRIC COILS; NEODYMIUM ALLOYS; PLASMAS; RELIABILITY; SUPERCONDUCTING CABLES; SUPERCONDUCTING MAGNETS; TEMPERATURE;

EID: 0033225913     PISSN: 09203796     EISSN: None     Source Type: None    
DOI: 10.1016/S0920-3796(99)00041-1     Document Type: Article
Times cited : (15)

References (20)
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  • 3
    • 85120111640 scopus 로고    scopus 로고
    • B.E. Keen (Ed.), Design, Construction and first operational experience on the Joint European Torus (JET), Fusion Technology, vol. 1, no. 1, 1987.
  • 4
    • 85120100630 scopus 로고    scopus 로고
    • C. Sborchia, et al., Mechanical structures for the ITER magnet system, Proceedings of the Nineteenth Symposium on Fusion Technology, Lisbon, September 1996.
  • 6
    • 85120129079 scopus 로고    scopus 로고
    • N. Mitchell, A. Alekseev, et al., Magnet safety assessment for ITER, in: R. Kurihura, Y. Seki, J.A.E.R.I. (Eds.), Proceedings of Sixth IAEA Technical Committee Meeting on ‘Developments in Fusion Safety’, Naka, Japan, October 1996, pp. 380–388.
  • 7
    • 0007647487 scopus 로고
    • ITER: The first experimental fusion reactor
    • P-H. Rebut ITER: The first experimental fusion reactor Fus. Eng. Des. 30 1995 85 118
    • (1995) Fus. Eng. Des. , vol.30 , pp. 85-118
    • Rebut, P-H.1
  • 8
    • 85120137186 scopus 로고    scopus 로고
    • 3Sn conductors, Fifteenth Magnet Technology Conference, Beijing, China, October 1997, pp. 1163–1166.
  • 9
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    • Superconductors for the NET Coils
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    • (1991) Fus. Eng. Des. , vol.15 , pp. 85-100
    • Mitchell, N.1    Bottura, L.2
  • 10
    • 85120108622 scopus 로고    scopus 로고
    • N. Mitchell, D. Bessette, et al., Conductor development for the ITER magnets, Fifteenth Magnet Technology Conference, Beijing, China, October 1997, pp. 347–352.
  • 11
    • 85120121158 scopus 로고    scopus 로고
    • F. Wong, N. Mitchell, Selection of the toroidal field coil case structural materials, Adv. Cryogenic Eng. (Mat.) 44 (1988).
  • 12
    • 85120098848 scopus 로고    scopus 로고
    • H. Tsuji, T. Ando, et al., ITER Central Solenoid Model Coil Program, R. Jayakumar, D. Gwinn et al., ITER Central Solenoid Manufacturing R&D, Seventeenth IAEA Fusion Energy Conference, Yokohama, Japan, October 1998.
  • 13
    • 85120109004 scopus 로고    scopus 로고
    • E. Salpietro, R. Maix, et al., The ITER toroidal field model coil (TFMC), 20th Symposium on Fusion Technology, Marseille, September 1998.
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    • N. Martovetsky, et al., Development and test of the ITER conductor joints, ANS 13th Topical Meeting on Technology of Fusion Energy, Nashville, June 1998.
  • 15
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    • C. Marinucci, et al., Performance of the quench detection system for ITER, IEEE Trans. Appl. Superconductivity 7 (2) (1997).
  • 17
    • 85120103881 scopus 로고    scopus 로고
    • R. Vieira, M. Sugimoto et al., ITER coils insulation R&D program, 16th IEEE/NPS Symposium on Fusion Engineering, Champaign, IL, 1995.
  • 18
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    • L.F. Moreschi, et al., ITER magnetic system candidates for low friction materials tested under vacuum at cryogenic temperatures, 20th Symposium on Fusion Technology, Marseille, September 1998, pp. 783–786.
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* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.