• DocumentCode
    1949597
  • Title

    Performance tests of an Experimental Loop for Liquid breeder in Korea

  • Author

    Yoon, J.S. ; Kim, S.K. ; Jung, Y.I. ; Lee, D.W. ; Cho, S.Y.

  • Author_Institution
    Korea Atomic Energy Res. Inst., Daejeon, South Korea
  • fYear
    2011
  • fDate
    26-30 June 2011
  • Firstpage
    1
  • Lastpage
    5
  • Abstract
    Korea (KO) has developed a Liquid breeder blanket and participated in the Test Blanket Module (TBM) program within the International Thermonuclear Experimental Reactor (ITER) group with a Helium Cooled Molten Lithium (HCML) concept. Based on this concept, helium (He) and liquid lithium (Li) were used as a coolant and breeder, respectively. Additionally, ferritic martensitic (FM) steel was considered as a structural material. However, according to our strategy for developing a liquid breeder TBM and its more relevant DEMO concept, not only liquid lithium breeders, but also lead-lithium (PbLi) breeders were considered. An Experimental Loop for a Liquid breeder (ELLI) was constructed for the purpose of validating the design and fabrication of our electromagnetic (EM) pump; testing the effects of the magneto-hydro-dynamics (MHD); and investigating the compatibility of PbLi using structural materials such as ferritic martensitic steel. In the ELLI, Pb-15.7Li, where Li is 15.7 at % (called PbLi hereafter), is used as the breeding material, and the EM pump circulates it through the loop. The maximum operating pressure and temperature in the loop are 0.5 MPa and 550 °C, respectively. In this study, performance tests with the EM pump were carried out. During the three separate experiments, the EM pump was operated for 250 h with a speed of 0.16 m/s for corrosion tests. For a material of corrosion test, tubular-type specimens and cylindrical-type specimens were fabricated and installed in three test pots of the loop. After installing the specimens into the loop, the corrosion test was performed while the EM pump was operating with a 0.16 m/s flow rate at 340 °C for 250 h.
  • Keywords
    Tokamak devices; fusion reactor blankets; plasma toroidal confinement; DEMO concept; HCML concept; Helium Cooled Molten Lithium; ITER group; International Thermonuclear Experimental Reactor; Korea; TBM program; breeding material; corrosion test; cylindrical-type specimens; electromagnetic pump; ferritic martensitic steel; lead-lithium breeders; liquid breeder blanket; liquid lithium breeders; magneto-hydro-dynamics effects; structural material; test blanket module; tubular-type specimens; Ad hoc networks; Corrosion; Heat pumps; Mobile computing; Corrosion; EM pump; ITER; Liquid breeder; TBM;
  • 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.2011.6052305
  • Filename
    6052305