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Volumn 49, Issue 50, 2000, Pages 709-717

Helium-cooled refractory alloys first wall and blanket evaluation

Author keywords

[No Author keywords available]

Indexed keywords

COOLING SYSTEMS; HELIUM; RADIOACTIVE WASTES; REFRACTORY ALLOYS; TOKAMAK DEVICES; TRITIUM;

EID: 0034315053     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0920-3796(00)00176-9     Document Type: Article
Times cited : (19)

References (17)
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    • M. Abdou et al., The APEX program, International Symposium on Fusion Technology, Rome, September 1999 (in press).
  • 2
    • 85120233204 scopus 로고    scopus 로고
    • F. Najmabadi, K.R. Schultz, R. Krakowski, et al., The ARIES-I tokamak reactor study, Final report, UCLA-PPG-1323, 1991.
  • 3
    • 85120195648 scopus 로고    scopus 로고
    • M.S. Tillack, M.A. Abdou, Z. Garbis, et al., Helium-cooled divertor for ITER: a study of cooling options, requirements and limits, ITER Report published by UCLA as UCLA-FNT-67 UCLA-ENG-93-22, April 1993.
  • 4
    • 85120184292 scopus 로고    scopus 로고
    • C. Baxi, C. Wong, Review of helium cooling for fusion reactor applications, International Symposium on Fusion Technology, Rome, September 1999 (in press).
  • 5
    • 85120195070 scopus 로고    scopus 로고
    • M.T. North, J.H. Rosenfeld, Test results from a helium gas-cooled porous metal heat exchanger, in: Ali M. Khomsary (Ed.) SPIE International, Society for Optical Engineering, November 1996, High Heat Flux Engineering III, vol. 2855, 1996, ISBN 0-8194-2243-6 Denver, Colorado.
  • 6
    • 85120215812 scopus 로고    scopus 로고
    • D.L. Youchison, J.M. McDonald, Thermal performance and flow instabilities in a multi-channel, helium-cooled, porous metal divertor module, International Symposium on Fusion Technology, Rome, September 1999 (in press).
  • 7
    • 0030180617 scopus 로고    scopus 로고
    • High heat flux testing of helium-cooled heat exchangers for fusion applications
    • D.L. Youchison M.G. Izenson C.B. Baxi J.H. Rosenfeld High heat flux testing of helium-cooled heat exchangers for fusion applications Fusion Technol. 29 4 1996 559 570
    • (1996) Fusion Technol. , vol.29 , Issue.4 , pp. 559-570
    • Youchison, D.L.1    Izenson, M.G.2    Baxi, C.B.3    Rosenfeld, J.H.4
  • 8
    • 0001398667 scopus 로고
    • Refactory ceramic foams: a novel, new high temperature structure
    • J. Sherman R.H. Tuffias R.B. Kaplan Refactory ceramic foams: a novel, new high temperature structure Ceramic Bull. 70 1991 1025
    • (1991) Ceramic Bull. , vol.70 , pp. 1025
    • Sherman, J.1    Tuffias, R.H.2    Kaplan, R.B.3
  • 9
    • 85120233546 scopus 로고    scopus 로고
    • Nuclear Regulatory Commission, 10CFR part 61, Licensing Requirements for Land Disposal of Radioactive Waste, Federal Register, FR 47, 57446, 1982.
  • 10
    • 0000245482 scopus 로고
    • Long term radioactive waste from fusion reactors
    • S. Fetter E. Cheng F. Mann Long term radioactive waste from fusion reactors Fusion Eng. Des. 13 1990 239 246
    • (1990) Fusion Eng. Des. , vol.13 , pp. 239-246
    • Fetter, S.1    Cheng, E.2    Mann, F.3
  • 11
    • 85120233305 scopus 로고    scopus 로고
    • D.K. Sze, R.F. Mattas, J. Anderson, R. Haange, H. Yoshida, O. Kveton, Tritium recovery based on cold trap, ISFNT-3, Los Angles, CA, June, 1994.
  • 12
    • 85120212330 scopus 로고    scopus 로고
    • E. Veleckis, V.A. Maroni, Thermodynamic properties of solutions in hydrogen isotopes in metals and laooys of interest to fusion reactor technology, Proceeding of the International Conference on Radiation Effects and Tritium Technology for Fusion Reactors, Gatlingburg, TN, October 1975.
  • 13
    • 85120235914 scopus 로고    scopus 로고
    • S. Willms, LANL, private communication.
  • 14
    • 85120188965 scopus 로고    scopus 로고
    • McCarthy et al., Safety issues due to mobilized activation products in selected APEX designs, International Symposium on Fusion Technology, Rome, September 1999 (in press).
  • 15
    • 85120195230 scopus 로고    scopus 로고
    • C.P.C. Wong, R.D. Stambaugh, Tokamak reactor designs as a function of aspect ratio, International Symposium on Fusion Technology, Rome, September 1999 (in press).
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    • ARIES-RS tokamak power plant design, special issue
    • M.S. Tillack ARIES-RS tokamak power plant design, special issue Fusion Eng. Des. 38 1997 1 218
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  • 17
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    • R.L. Miller. Design point determination for the commercial spherical tokamak, ARIES-ST, Proceedings of the 17th IEEE Symposium on Fusion Engineering, San Diego, CA 1997, p. 1031.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.