• DocumentCode
    1605923
  • Title

    ITER neutral beam Vacuum Vessel design

  • Author

    Delmas, E. ; Agarici, G. ; Boilson, D. ; Chareyre, J. ; Choi, C.-H. ; Chuilon, B. ; Dalla Palma, Mauro ; Dremel, M. ; El Ouazzani, A. ; Geli, F. ; Graceffa, J. ; Hemsworth, R. ; Jones, P.R. ; Mackay, P. ; Marcuzzi, D. ; Rigato, W. ; Roux, K. ; Shah, Devav

  • Author_Institution
    ITER Organ., St. Paul-lez-Durance, France
  • fYear
    2013
  • Firstpage
    1
  • Lastpage
    6
  • Abstract
    The Vacuum vessel of the ITER Heating Neutral Beam injector is a key component of the neutral beam system. It supports the injector components and is also an extension of the ITER Vacuum Vessel. This paper presents the status of the design of the vessel. In the first part of this paper we present the main design requirements. Besides the pressure and thermal loads, the various interfaces with other components are important constraints for the design. Some have specific requirements concerning displacement, or require specific features for their maintenance. Indeed all maintenance involving opening of the vessel needs to be performed using remote handling systems. The second part aims at presenting the present design of the NB vessel. Various concepts were studied before coming to the present design. Structures were optimised to satisfy the chosen design code (RCC-MR) under the various loading scenarios applied to the vessel, both for normal and accidental cases. In addition, the vessel incorporates two sets of long lip seals which tolerate limited displacements. Limiting the displacement is a real challenge considering the size of the flange and the forces involved. An innovative solution has been developed to improve the mechanical connection between the lids and the vessel walls in order to fulfil the requirements. The vessel displacement is also important for the alignment of the Beam Line Components with respect to the neutral beam and for the cryopumps interfaces. The geometry of the vessel was optimised to reduce the electric field stresses and to increase the voltage holding of the Beam Source, which is at 1 MV potential.
  • Keywords
    Tokamak devices; fusion reactor design; plasma heating by laser; plasma toroidal confinement; plasma-wall interactions; ITER heating neutral beam injector; ITER neutral beam vacuum vessel design; beam line components; chosen design code; electric field stresses; main design requirements; neutral beam system; remote handling systems; vessel geometry; vessel walls; Coolants; Flanges; Maintenance engineering; Niobium; Seals; Stress; Welding; HNB; ITER; Neutral Beam; design; vessel;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
  • Conference_Location
    San Francisco, CA
  • Print_ISBN
    978-1-4799-0169-2
  • Type

    conf

  • DOI
    10.1109/SOFE.2013.6635380
  • Filename
    6635380