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  1. No Access

    Article

    PUChOK BM-DF Code Verification Based on Experimental Study of the Heat-Exchange Crisis Accompanying Deformation of the Channel Tube of an RBMK Fuel Assembly

    The model of a heat-exchange crisis used in the PUChOK BM-DF code, intended for calculating by means of elementary cells the local thermohydraulic parameters of water and a steam–water mixture during stationar...

    D. A. Afremov, A. I. Emel’yanov, A. V. Kudryavtsev, Yu. V. Mironov… in Atomic Energy (2015)

  2. No Access

    Article

    Library of thermophysical electronic databases

    A library of electronic databases for thermophysical data is developed using Microsoft Access. This library includes 13 databases containing experimental data. Existing experimental data and their reduction to...

    Yu. V. Zhuravleva, G. S. Mingaleeva, Yu. V. Mironov, K. A. Mokrousov… in Atomic Energy (2007)

  3. No Access

    Article

    Basic Problems of Experimental Studies of Accident and Transient Regimes of an RBMK Reactor on an Integrated Thermohydraulic Stand

    A full-scale thermohydraulic stand for RBMK safety (FSS RBMK) is under construction at the Energy Scientific-Research Center. The purpose of the stand is to perform local and integrated experiments. The experi...

    N. A. Brus, Yu. V. Mironov, D. A. Afremov, A. F. Finyakin, D. A. Mikhailov in Atomic Energy (2005)

  4. No Access

    Article

    Analysis of the Uncertainty of Calculations of Loss-of-Coolant Accidents for the No. 1 Unit of the Kursk Nuclear Power Plant

    A method is developed for performing statistical analysis of the uncertainty of the hermophysical calculations. This method makes it possible to construct with a prescribed reliability the confidence interval ...

    D. A. Afremov, Yu. V. Zhuravleva, Yu. V. Mironov, V. S. Nazarov… in Atomic Energy (2005)

  5. No Access

    Article

    Verification of the thermohydraulic models used in improved-assessment codes for the RELAP5 and KORSAR two-phase flow models

    A methodology for finding the confidence intervals for the optimal values of the coefficients in the closure relations used in improved-estimate thermohydraulic codes is developed. When a coefficient used in a...

    Yu. V. Mironov, V. E. Radkevich, Yu. V. Zhuravleva, A. V. Kuzin… in Atomic Energy (2004)

  6. No Access

    Article

    A Procedure for Performing a Statistical Analysis of the Uncertainties in Thermohydraulic Calculations

    A methodology is developed for performing statistical analysis of the uncertainties in thermohydraulic calculations on the basis of the idea of the GRS method. The coefficients, which are to be varied, in the ...

    D. A. Afremov, Yu. V. Zhuravleva, Yu. V. Mironov, V. E. Radkevich in Atomic Energy (2002)

  7. No Access

    Article

    Role of separate factors in the development of the chernobyl accident

    E. O. Adamov, A. E. Domoradov, Yu. V. Mironov, Yu. M. Nikitin… in Atomic Energy (1993)

  8. No Access

    Article

    An analysis of the dynamics of the RBMK-1000 reactor for rupture of the pressurized collector at low power

    Yu. V. Mironov, Yu. M. Nikitin, T. I. Fomicheva, E. A. Domoradov in Atomic Energy (1993)

  9. No Access

    Article

    Pressure behavior in the RBMK reator space

    B. A. Gabaraev, Yu. V. Mironov, O. Yu. Novosel'skii, S. L. Simonov… in Soviet Atomic Energy (1990)

  10. No Access

    Article

    RBMK channel boiling during loss of coolant flow at low power

    L. L. Kobzar', Yu. V. Mironov, T. I. Fomicheva, A. M. Khudykin in Soviet Atomic Energy (1989)

  11. No Access

    Article

    Testing algorithms for calculating steam-water flow dynamic

    Yu. V. Mironov, Yu. M. Nikitin in Soviet Atomic Energy (1988)

  12. No Access

    Article

    Analysis of transient processes in nuclear-reactor loops

    Yu. V. Mironov, N. S. Razina, T. I. Fomicheva in Soviet Atomic Energy (1986)

  13. No Access

    Article

    Program complexes for calculating cells of local thermohydpaulic parameters in rod clusters by the cell method

    Yu. V. Mironov in Soviet Atomic Energy (1985)

  14. No Access

    Article

    Analysis of the leakage of steam-water flow with rupture of the heat-carrier circulation loop of nuclear reactors

    Yu. V. Mironov, T. I. Fomicheva in Soviet Atomic Energy (1984)

  15. No Access

    Article

    Problems in summarizing experimental data on the heat-transfer crisis in boiling

    Yu. V. Mironov, S. V. Shpanskii in Soviet Atomic Energy (1982)

  16. No Access

    Article

    Heat transfer in gas-cooled assemblies with artificial roughness

    G. S. Mingaleeva, Yu. V. Mironov, N. S. Razina, T. I. Fomicheva in Soviet Atomic Energy (1981)

  17. No Access

    Article

    Thermohydraulic calculation of multirod heat-liberating piles cooled by single-phase heat carrier

    G. S. Mingaleeva, Yu. V. Mironov in Soviet Atomic Energy (1980)

  18. No Access

    Article

    Distribution of the parameters of two-phase flow over the cross section of a channel with a fuel rod bundle

    Yu. V. Mironov, S. V. Shpanskii in Soviet Atomic Energy (1975)