• DocumentCode
    1351643
  • Title

    Operational Radioactivity Evaluation of ITER Diagnostic Neutron Activation System

  • Author

    Cheon, M.S. ; Seon, C.R. ; Pak, S. ; Lee, H.G. ; Bertalot, L. ; Forrest, R.A.

  • Author_Institution
    Nat. Fusion Res. Inst., Daejeon, South Korea
  • Volume
    38
  • Issue
    3
  • fYear
    2010
  • fDate
    3/1/2010 12:00:00 AM
  • Firstpage
    274
  • Lastpage
    277
  • Abstract
    At the International Thermonuclear Experimental Reactor (ITER), a neutron activation system is foreseen to measure neutron fluence on the first wall and to evaluate total fusion power from ITER plasma. This system utilizes the method of counting gamma radiation from the metal sample irradiated by the neutron flux at the irradiation end located near the plasma. Evaluation of the operational radioactivity of the sample, which has been induced during ITER operation, is necessary in order to determine sample material, mass, and the appropriate irradiation time. Neutronic calculations are performed to evaluate operational activity of the sample. Activation of the sample is calculated according to the irradiation time for various sample materials such as Si, Al, Ti, Fe, Nb, and Cu and by assuming that the samples are irradiated at the midplane inboard region where the neutron flux is one of the strongest.
  • Keywords
    Tokamak devices; neutron activation analysis; plasma diagnostics; plasma toroidal confinement; ITER plasma; International Thermonuclear Experimental Reactor; gamma radiation; irradiation time; neutron activation system; neutron fluence; neutron flux; neutronic calculations; operational radioactivity evaluation; total fusion power; Alite; ITER; MCNP; neutron activation; operational activity;
  • fLanguage
    English
  • Journal_Title
    Plasma Science, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    0093-3813
  • Type

    jour

  • DOI
    10.1109/TPS.2009.2036917
  • Filename
    5350731