• DocumentCode
    2930882
  • Title

    Towards diagnostics for a fusion reactor

  • Author

    Costley, A.E.

  • Author_Institution
    Cadarache Centre, ITER Organ., St. Paul-lez-Durance, France
  • fYear
    2009
  • fDate
    7-10 June 2009
  • Firstpage
    1
  • Lastpage
    10
  • Abstract
    The requirements for measurements on modern tokamak fusion plasmas are outlined, and the techniques and systems used to make the measurements, usually referred to as `diagnostics´, are introduced. The basics of three particular diagnostics - magnetics, neutron systems and a laser based optical system - are outlined as examples of modern diagnostic systems, and the implementation of these diagnostics on a current tokamak (JET) are described. The next major step in magnetic confinement fusion is the construction and operation of the International Thermonuclear Experimental Reactor (ITER), which is a joint project of China, Europe, Japan, India, Korea, the Russian Federation, and the United States. Construction has begun in Cadarache, France. It is expected that ITER will operate at the 500 MW level. Because of the harsh environment in the vacuum vessel where many diagnostic components are located, the development of diagnostics for ITER is a major challenge - arguably the most difficult challenge ever undertaken in the field of diagnostics. The main elements in the diagnostic step are outlined using the three chosen techniques as examples. Finally, the step beyond ITER to a demonstration reactor, DEMO, that is expected to produce several GWs of fusion power is considered and the impact on diagnostics outlined. It is shown that the applicability and development steps needed for the individual diagnostics techniques will differ. The challenges for DEMO diagnostics are substantial and a dedicated effort should be made to find and develop new techniques, and especially techniques appropriate to the DEMO environment. It is argued that the limitations and difficulties in diagnostics should be a consideration in the optimization and designs of candidate DEMOs.
  • Keywords
    Tokamak devices; fusion reactor design; plasma diagnostics; plasma toroidal confinement; Cadarache; China; DEMO reactor; Europe; France; ITER; India; International Thermonuclear Experimental Reactor; JET; Japan; Korea; Russian Federation; United States; fusion reactor diagnostics; laser based optical system; magnetic confinement fusion; magnetics; neutron system; tokamak fusion plasma; vacuum vessel; Europe; Fusion reactors; Inductors; Laser fusion; Laser modes; Magnetic confinement; Neutrons; Plasma diagnostics; Plasma measurements; Tokamaks; DEMO; ITER; Plasma measurements; diagnostics;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2009 First International Conference on
  • Conference_Location
    Marseille
  • Print_ISBN
    978-1-4244-5207-1
  • Electronic_ISBN
    978-1-4244-5208-8
  • Type

    conf

  • DOI
    10.1109/ANIMMA.2009.5503733
  • Filename
    5503733