Skip to main content

39 Result(s)

within V. M. Poplavskii Remove this filter

previous disabled Page of 2
and

  1. No Access

    Article

    Research on the Thermophysics of Next-Generation Nuclear Reactors

    The results of scientific research on the thermophysics of next-generation nuclear reactors conducted at the Leipunskii Institute of Physics and Power Engineering are presented: integrated experimental and com...

    A. P. Sorokin, V. M. Poplavskii, F. A. Kozlov, Yu. A. Kuzina, A. A. Kamaev… in Atomic Energy (2017)

  2. No Access

    Article

    Experimental and Computational Investigation of the Emission of Radioactive Products from Irradiated Fuel of Fast Sodium-Cooled Reactor

    The key experimental and computational studies of the emission of long-lived radioactive fission products and actinides from uranium dioxide irradiated in BN-600 into sodium and the gas phase in the range 150–...

    S. V. Zabrodskaya, L. I. Moseev, V. M. Poplavskii, S. I. Porollo… in Atomic Energy (2017)

  3. No Access

    Article

    Experimental studies of heat exchange for sodium boiling in the fuel assembly model: Safety substantiation of a promising fast reactor

    Numerical simulation of the ULOF-type accident development in a fast reactor with sodium coolant performed using the COREMELT code indicates that sodium boiling in the active core takes place. The boiling is a...

    R. R. Khafizov, V. M. Poplavskii, V. I. Rachkov, A. P. Sorokin… in Thermal Engineering (2017)

  4. No Access

    Article

    High-Priority R&D Problems of Advanced Fast Sodium Reactors

    The transition to new design and circuitry requires careful validation of the efficacy of the new solutions. For the sodium-water BN-1200 macro-modular steam generator, the damage is determined by the failure ...

    V. M. Poplavskii, Yu. E. Bagdasarov in Atomic Energy (2016)

  5. No Access

    Article

    Experimental Investigations of Heat Transfer Upon Sodium Boiling in a Model Fuel Assembly for Safety Validation of an Advanced Fast Reactor

    A structural concept using a sodium cavity located above the core of a reactor is proposed as a means of preventing accidents resulting in the destruction of core elements. The experimental investigations of h...

    R. R. Khafizov, V. I. Rachkov, V. M. Poplavskii, A. P. Sorokin… in Atomic Energy (2016)

  6. No Access

    Article

    Sodium Fires and Fast Reactor Safety

    Fifteen experiments with instantaneous opening of apertures of different size from pipes without thermal insulation and nine experiments with instantaneous opening of apertures beneath thermal insulation are a...

    Yu. E. Bagdasarov, A. V. Vinogradov, A. V. Drobyshev, A. A. Kamaev… in Atomic Energy (2015)

  7. No Access

    Article

    Computational and Experimental Validation of the Planned Emergency Heat-Removal System for BN-1200

    The results of computational and experimental validation of the design of the emergency heat-removal system for BN-1200 are presented. The results of experimental studies performed on a water model of the V-20...

    D. G. Zaryugin, V. M. Poplavskii, V. I. Rachkov, A. P. Sorokin… in Atomic Energy (2014)

  8. No Access

    Article

    Fuel for advanced sodium-cooled fast reactors: current status and plans

    Different fuel compositions have been irradiated in the BR-10, BOR-60, BN-350, and BN-600 reactors and investigated: PuO2, UC, UN, UPuN, UO2, UPuO2, metallic doped and undoped alloys, and fuel compositions with i...

    V. M. Poplavskii, L. M. Zabudko, I. A. Shkabura, M. V. Skupov… in Atomic Energy (2010)

  9. No Access

    Article

    Sodium as a coolant for fast reactors

    The results of a comparative analysis and choice of sodium as the coolant for fast reactors are presented. The facilities developed for removing impurities present in the sodium coolant and monitoring their co...

    V. M. Poplavskii, A. D. Efanov, F. A. Kozlov, A. P. Sorokin… in Atomic Energy (2010)

  10. No Access

    Article

    Concept of an advanced power-generating unit with a BN-1200 sodium-cooled fast reactor

    The status of work on the development of a 1200 MW sodium-cooled reactor facility for serial construction is presented. The general characteristics of the facility and the power-generating unit as well as the ...

    V. I. Rachkov, V. M. Poplavskii, A. M. Tsibulya, Yu. E. Bagdasarov… in Atomic Energy (2010)

  11. No Access

    Article

    Operating experience and prospects for future development of sodium-cooled fast reactors

    The main stages of the development of sodium-cooled fast reactors in Russia are described. The statistical information on the deviations from the normal regime of functioning that occur in BOR-60 and BN-600 op...

    O. M. Saraev, N. N. Oshkanov, A. V. Zrodnikov, V. M. Poplavskii… in Atomic Energy (2010)

  12. No Access

    Article

    Investigation of the influence of the sodium void effect of reactivity on the technical-economic performance and safety of an advanced fast reactor

    Measures to decrease the sodium void effect of reactivity and the influence of this effect on the technical-economic performance and the safety of BN-1200 are analyzed. Three variants of the core structure dif...

    V. M. Poplavskii, V. I. Matveev, V. A. Eliseev, I. A. Kuznetsov… in Atomic Energy (2010)

  13. No Access

    Article

    Core and fuel cycle for an advanced sodium-cooled fast reactor

    The development of BN-1200 is based on the greatest possible use of tested and scientifically validated and developed technical solutions implemented in BN-350, -600, and the BN-800 design as well as new techn...

    V. M. Poplavskii, A. M. Tsibulya, Yu. S. Khomyakov, V. I. Matveev… in Atomic Energy (2010)

  14. No Access

    Article

    BN-800 design validation and construction status

    Information is presented on the BN-800 design, the second design following BN-600, power-generating unit with a fast reactor. The main stages of the development of the design begun in the 1980s, modified in th...

    O. M. Saraev, Yu. V. Noskov, D. L. Zverev, B. A. Vasil’ev, V. Yu. Sedakov… in Atomic Energy (2010)

  15. No Access

    Article

    30 Years of experience in operating the BN-600 sodium-cooled fast reactor

    Experience in operating the BN-600 sodium-cooled fast reactor during its nominal service life as well as its service life extension period, an additional 15 years, is described. Information is presented on the...

    N. N. Oshkanov, O. M. Saraev, M. V. Bakanov, P. P. Govorov, O. A. Potapov… in Atomic Energy (2010)

  16. No Access

    Article

    Physical characteristics and problems of develo** a sodium-cooled fast reactor as a source of high-potential thermal energy for hydrogen production and other high-temperature technologies

    Hydrogen as an energy carrier will play a considerable role in the future structure of energy production when nuclear reactors will replace fossil fuels. Investigations performed in recent years have shown tha...

    V. M. Poplavskii, A. N. Zabud’ko, É. E. Petrov, M. K. Ovcharenko… in Atomic Energy (2009)

  17. No Access

    Article

    Performance-based reliability assessment of electromagnetic pumps

    The main factors influencing the overhaul period of induction magnetic pumps are examined and analyzed. It is established on the basis of an analysis of the special features of the manufacturing and operation ...

    I. V. Vitkovskii, I. R. Kirillov, P. Yu. Chaika, E. A. Kryuchkov… in Atomic Energy (2007)

  18. No Access

    Article

    Simulation of Tritium Mass Transfer in a Three-Loop Sodium-Cooled Nuclear Power System

    The simulation of the mass transfer of tritium in the technological media of sodium-cooled fast reactors is studied. The computational model of tritium mass transfer for a three-loop nuclear power system is ba...

    F. A. Kozlov, V. M. Poplavskii, V. V. Alekseev, A. G. Tsikunov… in Atomic Energy (2005)

  19. No Access

    Article

    BN-800 as a New Stage in the Development of Fast Sodium-Cooled Reactors

    The role of fast reactors in a strategy for develo** nuclear power in Russia because of the inevitable exhaustion of natural uranium deposits in the foreseeable future is discussed. The BN-800 reactor, which...

    V. M. Poplavskii, A. N. Chebeskov, V. I. Matveev in Atomic Energy (2004)

  20. No Access

    Article

    Prospects for the BN-1800 Sodium-Cooled Fast Reactor Satisfying 21st Century Nuclear Power Requirements

    The BN-1800 power-generating unit is designed to meet the requirements of the strategy for develo** atomic energy in Russia in the first half of the 21st century. The development time is the next 15 years an...

    V. M. Poplavskii, A. M. Tsibulya, A. A. Kamaev, Yu. E. Bagdasarov… in Atomic Energy (2004)

previous disabled Page of 2