• DocumentCode
    2882940
  • Title

    The Monte Carlo simulation of a 1MW neutral beam injector on RFX-mod

  • Author

    Pilan, N. ; Agostinetti, P. ; Grando, L. ; Kiyama, S. ; Rizzolo, A. ; Sakakita, H. ; Tollin, M. ; Valisa, M.

  • Author_Institution
    Consorzio RFX, Associazione EURATOM-ENEA per la Fusione, Padova, Italy
  • fYear
    2011
  • fDate
    26-30 June 2011
  • Firstpage
    1
  • Lastpage
    1
  • Abstract
    Summary form only given. The MW level TPE-RX Neutral Beam Injector is planned to be installed on the RFX-mod Reverse Field Pinch (RFP) experiment. The main purpose is to study the behavior of the fast ions, which in the helical equilibrium of the RFP have been seen to feature very long confinement times. Despite the many differences in several aspects, the use of a NBI on RFX has to face similar problems as the ITER NBI on ITER in both cases for instance, the stray poloidal magnetic field generated by the machine, has an impact on the transmission of the neutral beam heating power. To properly integrate the TPE-RX injector on RFX-mod, a 3D Monte Carlo simulation of the injector has been carried out. The code simulates the charged and neutral particle trajectories from the acceleration grids of the beam source up to the RFP plasma. The simulation includes the interactions between the accelerated beam and the background gas, particularly in the neutralization stage, and the effect of the magnetic field produced by RFX and by the Residual Ion Dump. The simulation has allowed to estimate the neutralizer and Residual Ion Dump (RID) efficiency and specifications, the geometry of the beam duct between the injector and RFX-mod and the necessary degree of magnetic screening.
  • Keywords
    Monte Carlo methods; magnetic shielding; plasma beam injection heating; plasma simulation; reversed field pinch; 3D Monte Carlo simulation; ITER NBI; RFX-mod; TPE-RX neutral beam injector; acceleration grids; beam duct; charged particle trajectories; helical equilibrium; long confinement times; magnetic screening; neutral beam heating power transmission; neutral particle trajectories; neutralization; power 1 MW; residual ion dump; reverse field pinch; stray poloidal magnetic field; Magnetic fields; Monte Carlo methods; Three dimensional displays;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Plasma Science (ICOPS), 2011 Abstracts IEEE International Conference on
  • Conference_Location
    Chicago, IL
  • ISSN
    0730-9244
  • Print_ISBN
    978-1-61284-330-8
  • Electronic_ISBN
    0730-9244
  • Type

    conf

  • DOI
    10.1109/PLASMA.2011.5993167
  • Filename
    5993167