• DocumentCode
    3172899
  • Title

    Safety characteristics of options for plasma-facing components for ITER and beyond

  • Author

    Piet, S.J. ; McCarthy, K.A. ; Holland, D.F. ; Longhurst, G.R. ; Merrill, B.J.

  • Author_Institution
    EG&G Idaho Inc., Idaho Falls, ID, USA
  • fYear
    1991
  • fDate
    30 Sep-3 Oct 1991
  • Firstpage
    444
  • Abstract
    Plasma-facing components (PFC) likely dominate the safety hazards of the International Thermonuclear Experimental Reactor (ITER) and post-ITER machines. To gain regulatory approval and for fusion energy to fulfill its ultimate attractive safety and environmental potential, safety must be considered when selecting among PFC options. Current PFC safety information is summarized. PFC safety issues fall into seven areas: disruption tolerance, disruption severity, tritium inventory and permeation, accidental energy release, activation/toxin hazards, cooling disturbances, and system issues. PFC options include current ITER mainline options (Be or W coating, C tiles), variants on current ITER options, and liquid metal divertors. No PFC option that the authors have examined is free of critical safety concerns. There are also innovative ideas that may improve any PFC´s performance: superpermeable vacuum ducts, helium self-pumping, and gaseous divertors. Recommendations and a future strategy are presented
  • Keywords
    accidents; fusion reactor materials; fusion reactor safety; fusion reactor theory and design; Be; C tiles; He; ITER; International Thermonuclear Experimental Reactor; PFC; T; W; accidental energy release; activation/toxin hazards; coating; cooling disturbances; critical safety; disruption severity; disruption tolerance; environmental potential; fusion energy; gaseous divertors; liquid metal divertors; permeation; plasma-facing components; post-ITER machines; regulatory approval; safety hazards; self-pumping; superpermeable vacuum ducts; system issues; Coolants; Hazardous materials; Hazards; Inductors; Laboratories; Plasma diagnostics; Plasma materials processing; Plasma properties; Power engineering and energy; Product safety;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1991. Proceedings., 14th IEEE/NPSS Symposium on
  • Conference_Location
    San Diego, CA
  • Print_ISBN
    0-7803-0132-3
  • Type

    conf

  • DOI
    10.1109/FUSION.1991.218884
  • Filename
    218884