• DocumentCode
    1948437
  • Title

    Laser welding of plasma facing units for ITER divertor Dome manufacturing

  • Author

    Mazaev, S. ; Gurieva, T. ; Lapin, A. ; Makhankov, A. ; Mirgorodsky, V. ; Natochev, S. ; Nomokonova, O. ; Vlasov, I. ; Ignatov, A.

  • Author_Institution
    Efremov Inst., St. Petersburg, Russia
  • fYear
    2011
  • fDate
    26-30 June 2011
  • Firstpage
    1
  • Lastpage
    5
  • Abstract
    The ITER divertor is a modular structure consisting of 54 cassettes. Each cassette consists of the cassette body, inner and outer vertical targets and Dome. The Russian Federation is responsible for manufacturing and delivery of 60 Domes for ITER. Each Dome consists of the steel support structure with 34 plasma-facing units of Umbrella, Inner Particle Reflector Plate and Outer Particle Reflector Plate (OPRP). The steel support structure includes three manifolds. Each plasma-facing unit part from 316L(N)-IG steel is supposed to be welded by laser beam welding. During laser beam welding of stainless steels more than 3 mm in thicknesses numerous metallic droplets appeared close to the weld area. The plasma-facing units are part of the divertor cooling system. Thus, droplets from root weld side might detach, appear in the cooling system and contaminate the cooling pumps. In the common practice of laser and e-beam welding both surfaces are machined. The main problem with of laser welding used for manufacture of the Dome are ITER requirement of full penetration and at the same time inaccessibility of weld root for machining after welding. The attempts to select different welding regimes, to use the transversal beam scanning or removable catchers from different materials did not keep droplets from appearing on the weld root. One of the most successful attempts was to use ESAB OK10.69 flux. The flux is placed on the root side of the weld, catches all droplets during the welding process and facilitates weld forming. The LS-15 fiber laser with Motoman HP50 robot in FlexLase laser cell was used for welding at full power up to 15 kW. An industrial videoscope was used for visual examinations of the weld root inside the closed volume of the mock-up. At first, samples and closed-like boxes structure with wall thicknesses about 7 mm were welded during development of welding technology. Then, laser beam welding was applied for manufacturing of the plasma-facing units of mock-up of D- - ome OPRP. The laser welding conditions and parameters for mock ups welded with ESAB OK10.69 flux are described. The visual and radiography examinations results of welded mock-ups are presented. These examinations allow for control of weld root and full-penetration weld of closed mock-ups without their cutting. The examinations have demonstrated a good quality of weld.
  • Keywords
    Tokamak devices; fibre lasers; fusion reactor design; fusion reactor divertors; laser beam welding; plasma materials processing; plasma toroidal confinement; plasma welding; plasma-wall interactions; stainless steel; Dome OPRP mock-up; Dome manufacturing process; ESAB OK10.69 flux; FlexLase laser cell; ITER divertor; LS-15 fiber laser; Motoman HP50 robot; closed-like box structure; divertor cooling system; electron-beam welding; full-penetration weld; industrial videoscope; inner particle reflector plate; laser beam welding technology; laser welding condition; metallic droplet analysis; modular structure; outer particle reflector plate; plasma-facing unit; radiography method; stainless steel; steel support structure; transversal beam scanning analysis; weld root control; Indium phosphide; Lasers; Welding; Dome; ITER; divertor; flux; laser; welding;
  • 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.2011.6052257
  • Filename
    6052257