• DocumentCode
    1070809
  • Title

    Review of the ITER Project

  • Author

    Shimomura, Y. ; Spears, W.

  • Author_Institution
    ITER, Gaerching, Germany
  • Volume
    14
  • Issue
    2
  • fYear
    2004
  • fDate
    6/1/2004 12:00:00 AM
  • Firstpage
    1369
  • Lastpage
    1375
  • Abstract
    ITER is planned to be the first fusion experiment operating under reactor-relevant conditions, thereby demonstrating the scientific and technological feasibility of fusion energy. ITER should accomplish this objective by demonstrating extended burn of deuterium-tritium plasmas at a fusion power of > 400 MW, by demonstrating technologies essential to a reactor in an integrated system, and by performing integrated testing of high-heat-flux components and tritium breeding blankets. The ITER tokamak is designed to have flexibility of plasma operations, providing a wide range of opportunities to develop inductively and noninductively driven reactor core plasmas and to study burning plasma physics. The ITER design, safety analysis and cost estimates are supported by a broad physics and analysis basis, and extensive technology R&D. Full-sized or scalable modules of key components have been successfully manufactured and tested. The scientific and technological bases to start ITER construction are established. Technical specifications allowing calls for tender for the supply of items needed for the start-up of the construction phase are under development. Inter-governmental negotiations among Canada, the European Union, Japan, the Republic of Korea, the People´s Republic of China, the Russian Federation and the United States of America to prepare the Joint Implementation Agreement for ITER construction and operation are expected to conclude in 2003. The ITER International Fusion Energy Organization would then be established in 2004 under international law and ITER operation would be able to start in 2014.
  • Keywords
    Tokamak devices; fusion reactor design; fusion reactor safety; project management; research and development management; technological forecasting; technology management; Canada; China; European Union; ITER construction; ITER design; ITER operation; ITER project; ITER tokamak; International Fusion Energy Organization; Japan; Joint Implementation Agreement; Republic of Korea; Russian Federation; United States of America; burning plasma physics; core plasmas; cost estimates; deuterium-tritium plasmas; full-sized modules; fusion energy; fusion experiment; fusion power; high-heat-flux components; inductively driven reactor; integrated system; integrated testing; inter-governmental negotiations; international law; magnetic fusion; noninductively driven reactor; plasma operations; reactor-relevant conditions; safety analysis; scalable modules; scientific feasibility; technical specifications; technological feasibility; tritium breeding blankets; Costs; Fusion reactor design; Inductors; Performance evaluation; Physics; Plasma materials processing; Research and development; Safety; System testing; Tokamaks; ITER; magnetic fusion; tokamak;
  • fLanguage
    English
  • Journal_Title
    Applied Superconductivity, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    1051-8223
  • Type

    jour

  • DOI
    10.1109/TASC.2004.830580
  • Filename
    1325054