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  1. No Access

    Article

    Design and Analysis of Solid Blanket Concept for Hybrid Fusion-Fission Facility

    The article discusses the results of conceptual design and analysis for solid blanket of a hybrid fusion-fission facility based on a tokamak-type fusion reactor with magnetic plasma confinement. This blanket i...

    Yu. S. Strebkov, D. A. Afremov, O. P. Arhipov, I. V. Vershinin… in Physics of Atomic Nuclei (2023)

  2. No Access

    Article

    Reactor Pressure Vessel Cooling Scheme: Selection and Validation for Small Nuclear Power Plants

    An analysis of existing and possible designs of high-temperature gas-cooled reactor installations has shed light on the critical elements determining the reactor’s efficiency and reliability; it required deter...

    D. A. Afremov, Yu. G. Dragunov, S. A. Koretskii, V. V. Kudinov… in Atomic Energy (2021)

  3. No Access

    Article

    Verification of a CFD-Class Software Tool as Applied to Modeling the Fuel Assemblies of Liquid Metal Cooled Reactors

    Methodical approaches to verification of a CFD-class code for modeling fluid dynamics and heat transfer processes within the boundaries of a fuel assembly (FA) used in liquid metal cooled reactors are proposed...

    D. A. Afremov, A. A. Dunaitsev, A. G. Zakharov, A. V. Nedaivozov… in Thermal Engineering (2020)

  4. No Access

    Article

    Study into the Distribution of Mass Velocity and Enthalpy of Single-Phase and Two-Phase Flows in the Cross Section of a 19-Rod Bundle in an Electrically Heated Model of an RBMK-1000 Fuel Assembly

    The results of experimental studies into the distribution of mass velocity and enthalpy of single-phase and two-phase flows over the cross section of a 19-rod bundle in an electrically heated model of an RBMK-...

    D. A. Afremov, A. V. Basov, E. A. Boltenko, M. V. Davydov… in Thermal Engineering (2020)

  5. No Access

    Article

    The EUCLID/V1 Integrated Code for Safety Assessment of Liquid Metal Cooled Fast Reactors. Part 2: Validation and Verification

    The article presents information on the validation and verification (V&V) of the first version (V1) of the EUCLID integrated code intended for safety analysis of operating or designed liquid metal (sodium, lea...

    V. M. Alipchenkov, A. V. Boldyrev, D. P. Veprev, Yu. A. Zeigarnik… in Thermal Engineering (2018)

  6. No Access

    Article

    Evaluation of Radioactive Aerosol Precipitation on the Inner Surfaces of Steam-Water Lines in Beyond Design Basis Accidents at NPP with RBMK

    The results of modeling performed with the MELCOR code of the transport and precipitation of fission product aerosols in the steam-water lines of RBMK during beyond design basis accidents are presented. It is ...

    D. A. Afremov, I. V. Zhukov, D. A. Pripachkin, A. K. Budyka in Atomic Energy (2017)

  7. No Access

    Article

    Fourth International Scientific and Technical Conference on Innovative Projects and Technologies of Nuclear Power (MNTK NIKIET-2016)

    Yu. G. Dragunov, B. A. Gabaraev, A. V. Dzhalavyan, A. V. Lopatkin… in Atomic Energy (2017)

  8. No Access

    Article

    Fundamentals, current state of the development of, and prospects for further improvement of the new-generation thermal-hydraulic computational HYDRA-IBRAE/LM code for simulation of fast reactor systems

    The conceptual fundamentals of the development of the new-generation system thermal-hydraulic computational HYDRA-IBRAE/LM code are presented. The code is intended to simulate the thermalhydraulic processes th...

    V. M. Alipchenkov, A. M. Anfimov, D. A. Afremov, V. S. Gorbunov… in Thermal Engineering (2016)

  9. No Access

    Article

    Investigation of Processes in Lead Coolant with Loss-of-Integrity of a Heat-Exchange Tube in a Brest-OD-300 Steam Generator

    The results of an experimental investigation by means of pulse radiography of the outflow of a steam–water mixture below the level of lead melt are presented. The x-ray diffraction patterns of bubble and jet e...

    A. V. Abramov, E. O. Kovalev, P. A. Kolesnikov, R. R. Mukhametov… in Atomic Energy (2016)

  10. No Access

    Article

    Modeling of Cesium and Iodine Transport in the FAL-ISP 1 Experiment

    D. A. Afremov, I. V. Zhukov, Yu. V. Zhuravleva, D. A. Pripachkin in Atomic Energy (2015)

  11. 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)

  12. No Access

    Article

    Verification of relap5/mod3.2 critical heat transfer computational method by experiments performed on the ks facility

    The computational results obtained with the RELAP5/mod3.2 code for critical heat transfer are compared with experimental data obtained on the KS facility for RBMK fuel assembly models. The confidence interval ...

    D. A. Afremov, D. A. Yashnikov in Atomic Energy (2011)

  13. 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)

  14. 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)

  15. 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)

  16. No Access

    Article

    Model of Dispersion of a Droplet of Corium Melt during Its Motion through the Coolant as Applied to the Problem of Steam Explosion

    The phenomenon of steam explosion takes an important place in the analysis of severe accidents in nuclear power generation. The intensity of steam explosion defines the scenario of further course of an acciden...

    D. A. Afremov, S. L. Solov'ev in High Temperature (2001)

  17. No Access

    Article

    Preliminary modeling of the second stage of the chernobyl accident

    R. M. Aksenov, D. A. Afremov, N. V. Solov'ev in Atomic Energy (1996)

  18. No Access

    Article

    Size distribution of particles formed when a drop of molten fuel interacts with coolant

    D. A. Afremov, V. K. Sirotkin in Atomic Energy (1995)