Table 1: International project Generation-IV and Russian technology experience

GENERATION-IV

(June 2002)

RUSSIA

 

Thermal systems

Supercritical Water-Cooled Reactor:

  • 1700 MWe.
  • 500° C outlet temperature.
  • Efficiency near 45%.
  • 20 years of R&D, including the reactors with variable neutron spectrum, with up to 1800 MWe capacity.
  • Works stopped at the beginning of the 1990s.

    • Very High-Temperature Reactor:

    • 600 MWe.
    • > 900° C outlet temparature.
    • 1250° С fuel temperatures.
    • Solid graphite block core based on GT-MHR.

  • 30 years of R&D.
  • Existed an operational prototype with outlet temperature of 3000 К.
  • NPP technical projects (ABTU-50, VG-400 with temperature of 950° С).
  • International GT-MHR project is being developed.
  • PBMR development is supported.

    • Molten Salt Reactor:

    • Fuel – liquid Li, Be, Th, U fluorides.
    • 1000 MWe.
    • low pressure (< 0.5 МРа) and high temperature (> 700° С).
  • 30 years of R&D, including fluoride technologies, physics and chemistry of the molten salt fuel, loop and reactor tests, etc.

    • Fast systems

    Sodium-Cooled Reactor with Advanced Recycle Technology:

    • 150 to 500 MWe.
    • Metal fuel with metallurgical recycle or 'pyro'-process.
  • 50 years of R&D, several reactor prototypes.
  • 20 years of operating a BN-350 plant with desalination.
  • In operation: the world’s only commercial NPP with fast BN-600 reactor. Under construction: NPP with BN-800 reactor.
  • Development of BN-1600 reactor was stopped in 1992.
  • Research, development and reactor tests both of the traditional oxide fuel and the 'dense' fuel (metallic, based on carbides and nitrides).
  • Gas-fluoride and chloride technology of the fuel pyro-chemical processing reached the stage of pilot facilities.

    • Fast Lead-Bismuth-Cooled Reactor:

    • 120-400 MWe.
    • 540 to 750° С outlet temperature.
    • 30 years of R&D, existed operational prototypes with total operation time of 80 reactor years.

    Fast Gas-Cooled Reactor:

    • 600 MWth / 288 MWe.
    • He – coolant.
    • 48% efficiency.

  • 20 years of R&D.
  • Works stopped at the beginning of the 1990s.

    • Fast Lead-Cooled Reactor:

    No proposals.

    • 15 years of R&D.
    • Technical design of the demonstration unit is being developed.

    Small systems

    No proposals.

    • 40 years of R&D. Hundreds of existed and presently operating ship facilities with water-cooled reactors.
    • Several NPP prototypes, including an operational one (Bilibino).
    • About 20 NPP designs with water-cooled and lead-bismuth reactors.
    • Construction-ready design of a floating NPP with KLT-40 reactor.
    Nuclear Renaissance: A View From Russia

    Restore Frames  |  Sym Home  |  Programme  |  Back   |  Forward

    © copyright The World Nuclear Association 2002