Prospects of the aqueous self-cooled blanket concept for net

M. Snykers, W. F. Bogaerts, A. Bruggeman, M. J. Embrechts, Wolfgang Daenner, D. Steiner

    Research outputpeer-review

    Abstract

    A low-technology Aqueous Self-Cooled Blanket (ASCB) concept has been proposed for the Next European Torus (NET). This concept relies on structural material and cooling water, with small amounts of lithium compounds for tritium production. Following preliminary investigations, LiOH, LiNO3, LiNO2 and Li2SO4 are currently under consideration as tritium breeding materials in solution. The concept may benefit from the proven technologies from the PWRs and from the CANDU tritium extraction systems. It combines good shielding and breeding capabilities. It would serve as a reliable environment for experimenting with several DEMOnstration reactor-relevant blanket modules in NET. Since net tritium breeding is not a design requirement for NET, sufficient tritium breeding can be obtained without the application of external neutron multipliers if enrichment in 6Li is utilized. For a DEMOnstration reactor ASCB-based blanket, neutron multipliers have to be incorporated and temperature and pressure have to be increased. Radiolysis and corrosion aspects are of particular concern and need further investigation.

    Original languageEnglish
    Pages (from-to)213-218
    Number of pages6
    Journalfusion engineering and design
    Volume8
    Issue numberC
    DOIs
    StatePublished - 1989

    ASJC Scopus subject areas

    • Civil and Structural Engineering
    • Nuclear Energy and Engineering
    • General Materials Science
    • Mechanical Engineering

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