• DocumentCode
    1604071
  • Title

    Numerical analysis of two-phase flow and heat transfer of fuel particles and liquid metal for waste transmutation blanket

  • Author

    Wang Weihua ; Liu Guangmeng ; Huang Shenghong ; Yang Bin ; Yang Jinhong ; Chu Delin ; Deng Haifei

  • Author_Institution
    New Star Inst. of Appl. Technol., Hefei, China
  • fYear
    2013
  • Firstpage
    1
  • Lastpage
    5
  • Abstract
    Development of fusion driven sub-critical reactor is a practical approach to the transmutation of long-lived nuclear waste, the production of nuclear fuel and the multiplication of energy. The waste transmutation blanket is regarded as one of the most attractive options for this system and various designs are proposed and investigated. The fuel particles which have been suspended inside the liquid metal lead lithium in the breeder zones are liquid-solid two-phase flows. The Eulerian model and the discrete phase model have been developed, taking into account high power density, fuel particle distribution, variability of viscosity, and velocity slippage between phases. The momentum equations and energy equations are modified to describe the unique characteristics of the two-phase flows. The velocity profile, temperature distribution and particle tracks are calculated. The correlation among the variants of particle size, power density and fuel particle´s thermal conductivity has been established as a reference to the fuel particle design and the safety analysis of fuel particle circulation. The results demonstrate that the newly-developed approaches to numerical simulation can benefit the thermal-hydraulic analyses of the liquid breeder blanket and provide support to improve the design of fuel particles in the dual-cooled waste transmutation blanket.
  • Keywords
    fission reactor fuel reprocessing; fusion reactor blankets; heat transfer; numerical analysis; radioactive waste processing; thermal conductivity; two-phase flow; Eulerian model; discrete phase model; dual-cooled waste transmutation blanket; energy equations; fuel particle circulation safety analysis; fuel particle design; fuel particle heat transfer; fuel particle thermal conductivity; fusion driven subcritical reactor; liquid breeder blanket thermal-hydraulic analyses; liquid metal lead lithium; liquid-solid two-phase flow numerical analysis; long-lived nuclear waste transmutation blanket; momentum equations; particle size variants; particle tracks; power density; velocity slippage; viscosity variability; Density measurement; Fuels; Heat transfer; Liquids; Lithium; Mathematical model; Power system measurements; Eulerian model; sub-critical reactor; two-phase flow; waste transmutation blanket;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
  • Conference_Location
    San Francisco, CA
  • Print_ISBN
    978-1-4799-0169-2
  • Type

    conf

  • DOI
    10.1109/SOFE.2013.6635315
  • Filename
    6635315