• DocumentCode
    1413080
  • Title

    Modeling of Surface Composition Dynamics in the ITER Divertor Region

  • Author

    Nieto-Pérez, Martin ; Ramos, G. ; Allain, Jean Paul

  • Author_Institution
    CICATA Queretaro, Inst. Politec. Nac., Santiago de Queretaro, Mexico
  • Volume
    38
  • Issue
    3
  • fYear
    2010
  • fDate
    3/1/2010 12:00:00 AM
  • Firstpage
    414
  • Lastpage
    418
  • Abstract
    The formation of mixed materials in the ITER divertor region is a critical materials issue that is expected to have a profound effect on the operation of the machine. This is particularly true for the divertor, the component where most of the energy is deposited during ITER operation. The divertor is made up of three tungsten domes and two vertical plates (inboard and outboard) which will be manufactured with composite carbon fiber according to the latest design. In the case of the first wall, the plasma-exposed surface is made out of beryllium; some of this beryllium is eroded from the first wall and finds its way into the divertor region, where it may strike the carbon vertical plates and get implanted or deposited. Having beryllium in the divertor enhances tritium trapping via codeposition, hence reducing the net available fuel for the reactor; on the other hand, there is evidence of carbon chemical erosion suppression. In this paper, the dynamic composition of a carbon surface under simultaneous bombardment by deuterium, tritium, and beryllium ions is studied. Both carbon and beryllium can redeposit on the target once eroded, so the source of ions receives feedback from the eroded material. Simulation results show that both the partial sputtering of Be and C atoms as well as the bombarding energy play an important role in Be accumulation on the vertical target plate, which can reach up to 50% near the surface. The results also show that the contribution of redeposited species may become so large that the DT bombarding flux may drop to 70% of the incident species.
  • Keywords
    Tokamak devices; carbon; fusion reactor divertors; plasma simulation; sputtering; surface composition; C; ITER divertor region; beryllium accumulation; beryllium atom partial sputtering; beryllium ion; carbon atom partial sputtering; carbon surface; carbon vertical plates; deuterium ion; surface composition dynamics; tritium ion; tritium trapping; Beryllium; ITER; carbon; divertor; mixed materials; modeling;
  • fLanguage
    English
  • Journal_Title
    Plasma Science, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    0093-3813
  • Type

    jour

  • DOI
    10.1109/TPS.2009.2039006
  • Filename
    5409590