Search Results - "NOVOSEL'SKII, O. YU"

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  1. 1
    Investigation of the Heat-Insulation Properties of the Steam-Water Gap in the Downcomer Pipes of a Steam Generator

    Investigation of the Heat-Insulation Properties of the Steam-Water Gap in the Downcomer Pipes of a Steam Generator by Semchenkov, A. A., Novosel’skii, O. Yu, Lemekhov, Yu. V., Khizhnyak, A. G., Shpanskii, S. V., Shishov, V. P.

    Published in Atomic energy (New York, N.Y.) (01-03-2014)
    “…The results of an experimental investigation of heat transfer through a gap filled with a steam–water mixture are presented. It is shown that heat transfer…”
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  2. 2
    Investigation of the development of the 1986 accident at the Chernobyl nuclear power plant

    Investigation of the development of the 1986 accident at the Chernobyl nuclear power plant by Cherkashov, YuM, Novosel'skii, OYu, Checherov, K P

    Published in Atomic energy (New York, N.Y.) (01-04-2006)
    “…Important results obtained from investigations of the diverse processes that occurred during the accident in the No. 4 unit of the Chernobyl nuclear power…”
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  3. 3
    Increasing the nominal safety of the no. 5 unit of the Kursk nuclear power plant

    Increasing the nominal safety of the no. 5 unit of the Kursk nuclear power plant by Potapov, A A, Panin, V M, Ukharov, S G, Novosel'skii, OYu

    Published in Atomic energy (New York, N.Y.) (01-04-2006)
    “…The main technical measures for increasing the nominal safety of the No. 5 unit of the Kursk nuclear power plant are presented: optimization of the…”
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  4. 4
    Comprehensive analysis of mechanical and thermohydraulic processes in the graphite masonry of channel rectors during an accidental rupture of a fuel channel

    Comprehensive analysis of mechanical and thermohydraulic processes in the graphite masonry of channel rectors during an accidental rupture of a fuel channel by SOLOV'EV, S. L, GABARAEV, B. A, NOVOSEL'SKII, O. Yu, FILINOV, V. N, PARAFILO, L. M, KRYUCHKOV, D. V

    Published in Atomic energy (New York, N.Y.) (01-02-2003)
    “…A methodology and preliminary results of a computational analysis of the processes occurring in the graphite masonry in RBMK channel reactors during the…”
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  5. 5
    Criteria for the fracture of RBMK fuel-channel tubes when accidental overheating occurs

    Criteria for the fracture of RBMK fuel-channel tubes when accidental overheating occurs by NOVOSEL'SKII, O. YU, FILINOV, V. N

    Published in Atomic energy (New York, N.Y.) (01-04-1997)
    “…(ProQuest: Abstract omitted; see image)[PUBLICATION ABSTRACT]…”
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  6. 6
    Determining the onset of flow crisis in a multipurpose valve using a 3D thermohydraulic code

    Determining the onset of flow crisis in a multipurpose valve using a 3D thermohydraulic code by Novosel’skii, O. Yu, Skibin, A. P., Solov’ev, S. L., Shishov, A. V.

    Published in Thermal engineering (01-11-2007)
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  7. 7
    The application of computational fluid dynamics for determining the hydraulic characteristics of pipelines at nuclear power stations

    The application of computational fluid dynamics for determining the hydraulic characteristics of pipelines at nuclear power stations by NOVOSEL'SKII, O. Yu, PETROV, V. E, SKIBIN, A. P, SOLOV'EV, S. L, SHISHOV, A. V

    Published in Thermal engineering (01-09-2006)
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  8. 8
    Investigation of the development of the 1986 accident at the chernobyl nuclear power plant

    Investigation of the development of the 1986 accident at the chernobyl nuclear power plant by CHERKASHOV, Yu. M, NOVOSEL'SKII, O. Yu, CHECHEROV, K. P

    Published in Atomic energy (New York, N.Y.) (2006)
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  9. 9
    Determining the onset of flow crisis in a multipurpose valve using a 3D thermohydraulic code

    Determining the onset of flow crisis in a multipurpose valve using a 3D thermohydraulic code by NOVOSEL'SKII, O. Yu, SKIBIN, A. P, SOLOV'EV, S. L, SHISHOV, A. V

    Published in Thermal engineering (2007)
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  10. 10
    Separation system of a new-generation boiling-water vessel reactor

    Separation system of a new-generation boiling-water vessel reactor by Karasev, V. B., Novosel’skii, O. Yu, Shishov, A. V.

    Published in Atomic energy (New York, N.Y.) (01-05-1994)
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  11. 11
    Increasing the nominal safety of the no. 5 unit of the kursk nuclear power plant

    Increasing the nominal safety of the no. 5 unit of the kursk nuclear power plant by POTAPOV, A. A, PANIN, V. M, UKHAROV, S. G, NOVOSEL'SKII, O. Yu

    Published in Atomic energy (New York, N.Y.) (2006)
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  12. 12
    Methodological questions concerning investigations of the hydraulic characteristics of the water-leveling pipes of the separator drums in a RBMK reactor

    Methodological questions concerning investigations of the hydraulic characteristics of the water-leveling pipes of the separator drums in a RBMK reactor by Karasev, V. B., Novosel’skii, O. Yu, Smolin, V. N., Shishov, A. V.

    Published in Atomic energy (New York, N.Y.) (01-11-1994)
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  13. 13
    Investigation of the hydraulic characteristics of the water-leveling pipes of RBMK-1000 separator drums

    Investigation of the hydraulic characteristics of the water-leveling pipes of RBMK-1000 separator drums by Esikov, V. I., Karasev, V. B., Novosel’skii, O. Yu, Smolin, V. N., Shishov, A. V., Gal’berg, V. P., Stasenko, V. V., Ustinov, E. D.

    Published in Atomic energy (New York, N.Y.) (01-11-1994)
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  14. 14
    Assessment of the Vulnerability of RBMK Fuel Channels to Loads Produced by the Rupturing of One Channel

    Assessment of the Vulnerability of RBMK Fuel Channels to Loads Produced by the Rupturing of One Channel by Gabaraev, B A, Novosel'skii, O Yu, Filinov, V N, Parafilo, L M

    Published in Atomic energy (New York, N.Y.) (01-08-2000)
    “…The possibilities for a fuel-channel pipe in RBMK, with nominal parameters, to rupture under internal and external loading caused by the rupture of a…”
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  15. 15
    Assessment of the vulnerability of RBMK fuel channels to loads produced by the rupturing of one channel

    Assessment of the vulnerability of RBMK fuel channels to loads produced by the rupturing of one channel by GABARAEV, B. A, NOVOSEL'SKII, O. Yu, FILINOV, V. N, PARAFILO, L. M

    Published in Atomic energy (New York, N.Y.) (2000)
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  16. 16
    Investigation of the behavior of the technological channels of a RBMK reactor under conditions of heating during an accident

    Investigation of the behavior of the technological channels of a RBMK reactor under conditions of heating during an accident by Novosel'skii, O. Yu, Filinov, V. N., Kryuchkov, I. I.

    Published in Atomic energy (New York, N.Y.) (01-03-1995)
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  17. 17
    Effect of nonsimultaneous rupture of the technological channels on the dynamics of pressure in the reactor space of a RBMK unit

    Effect of nonsimultaneous rupture of the technological channels on the dynamics of pressure in the reactor space of a RBMK unit by Gabaraev, B. A., Novosel'skii, O. Yu, Safonov, V. K., Simonov, S. L.

    Published in Atomic energy (New York, N.Y.) (01-05-1993)
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  18. 18
    Testing the VSPLESK program with data of experiments made on a model of an accident localization system

    Testing the VSPLESK program with data of experiments made on a model of an accident localization system by Karasev, V. B., Novosel'skii, O. Yu, Safonov, V. K., Murashko, A. N., Isaev, O. A.

    Published in Atomic energy (New York, N.Y.) (01-01-1993)
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  19. 19
    Hydraulic resistance of channels with permeable walls

    Hydraulic resistance of channels with permeable walls by Kochenov, I. S., Novosel'skii, O. Yu

    Published in Journal of Engineering Physics (01-03-1969)
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  20. 20
    Hydrostatic calculation of a nuclear reactor cooling system

    Hydrostatic calculation of a nuclear reactor cooling system by Kochenov, I. S., Novosel'skii, O. Yu

    Published in Soviet Atomic Energy (01-08-1967)
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