• DocumentCode
    2017393
  • Title

    Solid breeder blanket option for the ITER conceptual design

  • Author

    Gohar, Y. ; Attaya, H. ; Billone, M.C. ; Finn, P. ; Majumdar, S. ; Turner, L.R. ; Baker, C.C. ; Nelson, B.E. ; Raffray, R.

  • Author_Institution
    Argonne Nat. Lab., IL, USA
  • fYear
    1989
  • fDate
    2-6 Oct 1989
  • Firstpage
    53
  • Abstract
    A solid-breeder, water-cooled blanket option based on a multilayer configuration was developed for the ITER (International Thermonuclear Experimental Reactor). The blanket uses beryllium for neutron multiplication and lithium oxide for tritium breeding. The material forms are sintered products for both materials with 0.8 density factor. The lithium-6 enrichment is 90%. The blanket can accommodate a factor of two change in the neutron wall loading without violating the different design guidelines. The design philosophy adopted for the blanket is to produce the necessary tritium required for the ITER operation and to operate at power reactor conditions as much as possible. At the same time, the reliability and the safety aspects of the blanket are enhanced by using a low-pressure coolant and separating the tritium purge lines from the coolant system. The blanket modules are made by hot vacuum forming and diffusion bonding a double-wall structure with integral cooling channels. The different aspects of the blanket design including tritium breeding, nuclear heat deposition, activation analyses, thermal-hydraulics, tritium inventory, structural analyses, and water-coolant conditions are summarized
  • Keywords
    Tokamak devices; fusion reactor materials; Be; ITER; International Thermonuclear Experimental Reactor; Li; T inventory; activation analyses; diffusion bonding; double-wall structure; hot vacuum forming; low-pressure coolant; multilayer configuration; neutron multiplication; neutron wall loading; nuclear heat deposition; power reactor conditions; solid-breeder; structural analyses; thermal-hydraulics; tritium breeding; water-cooled blanket; Activation analysis; Coolants; Guidelines; Inductors; Lithium compounds; Neutrons; Nonhomogeneous media; Power system reliability; Safety; Solids;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
  • Conference_Location
    Knoxville, TN
  • Type

    conf

  • DOI
    10.1109/FUSION.1989.102170
  • Filename
    102170