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Volumn 65, Issue 2, 2003, Pages 303-322

The toroidal field coil design for ARIES-ST

Author keywords

ARIES ST; Embrittlement; Toroidal field

Indexed keywords

CURRENT DENSITY; ELECTRIC INSULATION; ENERGY EFFICIENCY; FUSION REACTORS; MAINTENANCE; STRUCTURAL DESIGN;

EID: 0037318805     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0920-3796(02)00308-3     Document Type: Article
Times cited : (15)

References (13)
  • 1
    • 0030262099 scopus 로고    scopus 로고
    • Evaluation of copper alloys for fusion reactor divertor and first wall components
    • Fabritsiev S.A., Zinkle S.J., Singh B.N. Evaluation of copper alloys for fusion reactor divertor and first wall components. J. Nucl. Mater. 1996.
    • (1996) J. Nucl. Mater.
    • Fabritsiev, S.A.1    Zinkle, S.J.2    Singh, B.N.3
  • 2
    • 0037323138 scopus 로고    scopus 로고
    • ARIES-ST nuclear analysis and shield design
    • ARIES Team, in press
    • L. El-Guebaly, ARIES Team, ARIES-ST Nuclear Analysis and Shield Design, Fusion Eng. Des., in press.
    • Fusion Eng. Des.
    • El-Guebaly, L.1
  • 8
    • 0013250593 scopus 로고
    • Mechanical design of a high-beta TFCX tokamak with a demountable TF coil
    • Varese, Italy, September
    • F. Puhn, et al., Mechanical Design of a High-Beta TFCX Tokamak with a Demountable TF Coil, in: Proceedings of 13th Symposium on Fusion Technology (SOFT), Varese, Italy, September, 1984.
    • (1984) Proceedings of 13th Symposium on Fusion Technology (SOFT)
    • Puhn, F.1
  • 10
    • 0013250695 scopus 로고    scopus 로고
    • Culham Laboratorties, United Kingdom, private communication, 1999.
    • G. Voss, Culham Laboratorties, United Kingdom, private communication, 1999.
    • Voss, G.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.