• DocumentCode
    1947431
  • Title

    Design feasibility analysis of the robot for EAST tokamak flexible in-vessel inspection

  • Author

    Peng, X. ; Song, Y. ; Yang, Y. ; Qiao, P. ; Ji, X.

  • Author_Institution
    Inst. of Plasma Phys., Hefei, China
  • fYear
    2011
  • fDate
    26-30 June 2011
  • Firstpage
    1
  • Lastpage
    4
  • Abstract
    EAST is a full superconducting tokamak fusion experiment device with `D´ shape vacuum vessel and toroidal coils and actively cooled plasma facing components (PFCs), which aims at studying the scientific and engineering issues under steady state operation. It is difficult but very important to know well the operating state of the components in the vacuum vessel during plasma operation campaign for the help of guiding operation plan and understanding physical phenomena. A robotic system (called flexible in-vessel inspection robot, FIVIR) is proposed to inspect the surface of plasma facing components to know the performance of first wall, such as erosion and desquamation. Because of the geometric requirement and the intensity of ports usage arrangement, two FIVIRs are planned installing toroidal symmetry on EAST. Each FIVIR is a series-wound robot with ten degrees of freedom consisting of main robot and end-effector. The main robot has the primary function that transports the end-effector and associated process tools into the vacuum chamber in the equatorial plane at R=1.94m and back to the storage port, which has the benefit that easy control of the FIVIR and easy position calculation of the end-effector. All the joints in the FIVR are driven by actuators. The workspace of the robot is analyzed to see whether it can reach any point of the plasma facing surface in the distance of 15mm and the range of ±90°along toroidal direction.
  • Keywords
    Tokamak devices; fusion reactor design; fusion reactor materials; plasma toroidal confinement; plasma-wall interactions; D shape vacuum vessel; EAST tokamak; FIVIR; actively cooled plasma facing components; design feasibility analysis; equatorial plane; flexible in-vessel inspection; full superconducting tokamak fusion experiment; plasma facing surface; plasma operation campaign; steady state operation; toroidal coils; toroidal symmetry; vacuum chamber; Humans; Robots; EAST; feasibility analysis; in-vessel inspection; robot;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering (SOFE), 2011 IEEE/NPSS 24th Symposium on
  • Conference_Location
    Chicago, IL
  • ISSN
    1078-8891
  • Print_ISBN
    978-1-4577-0669-1
  • Electronic_ISBN
    1078-8891
  • Type

    conf

  • DOI
    10.1109/SOFE.2011.6052217
  • Filename
    6052217