• DocumentCode
    1948620
  • Title

    Design and indigenous development of fabrication of cryopanels for cryopump applications

  • Author

    Gangradey, Ranjana ; Ravi, Prakash ; Udgata, Swamp

  • Author_Institution
    Inst. for Plasma Res. (IPR), Gandhinagar, India
  • fYear
    2011
  • fDate
    26-30 June 2011
  • Firstpage
    1
  • Lastpage
    4
  • Abstract
    Hydro formed cryogenic panels or radiation shield are considered to be one of the most important element in building a reactor of fusion Grade. The panels have several applications e.g. cryopump shields, radiation shield for vacuum vessel to protect TF coils etc. Indigenous fabrication technology to develop such prototype panels to work in the stringent environment of 4K and 80 K cryogens flowing at higher pressures, undergoing a number of thermal cycles with complete leak tightness against Ultra High Vacuum, was taken up addressing all technological barriers. Leak tightness with a pressure of 4 bar was also carried out. Austenitic steel material was taken as the shield plate material to work in fusion tokamak environment. Several joining process available for fabrication were checked for its flexibility cost effectiveness and cleanliness in operation. Various port connections like vertical port, horizontal port, and fish mouth port, inclined port, etc. were tried and definite conclusions were made for successful applications. Hydro-forming with different fluids and different type of die contours were tried and conclusions drawn on area of application and process Panels of different shape and size were designed, CFD conducted to understand its flow behavior, pressure drop, etc. Similarly efforts were taken on design of weld spacing, port size, spot gap for various burst pressure requirements and pressure drop requirements of such panel in operations. Physical prototypes of different shapes and sizes, different bubble geometry, port connections, thickness were made and conclusions drawn on process limitations, quality control points etc. Various tests were conducted at the end of fabrications of such prototypes which includes vacuum leak tests, mechanical and material tests, and thermal cycling after subjecting to cryogenic temperatures. The successful panel is thus shown in details in this paper with all technical details of design, fabrication procedures, testing a- - nd performance. The work has been carried out by the support of Board of Research for Fusion Science and Technologies (BRFST) under, Govt. of India.
  • Keywords
    austenitic steel; computational fluid dynamics; cryopumping; fusion reactor instrumentation; fusion reactor materials; Board-of-Research-for-Fusion Science-and-Technologies; TF coils; austenitic steel material; bubble geometry; computational fluid dynamics; cryogenic temperatures; cryopanels fabrication; cryopump applications; fish mouth port; fusion grade reactor; fusion tokamak environment; hydroformed cryogenic panels; leak tightness; port connections; port size; pressure drop; radiation shield; shield plate material; spot gap; temperature 4 K to 80 K; thermalcycles; ultra high vacuum; vacuum leak tests; vacuum vessel; weld spacing; Computational fluid dynamics; Marine animals; Mouth; Nitrogen; Pumps; Surface treatment; Welding; Radiation shield; cryogenic; cryogenic panels;
  • 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.2011.6052264
  • Filename
    6052264