Dynamic measurements of the flow and structure oscillations to validate FSI calculations von Bolshukhin, M.A., Budnikov, A.V., Shmelev, E.I., Kulikov, D.A., Loginov, A.V., Pribaturin, N.A., Lobanov, P.D., Meledin, V.G., Suvorov, A.S, Stulenkov, A.V.

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The World’s First Floating NPP: Origination and Direction of Future Development von Belyaev, V. M., Bol’shukhin, M. A., Pakhomov, A. N., Khizbullin, A. M., Lepekhin, A. N., Polunichev, V. I., Veshnyakov, K. B., Sokolov, A. N., Turusov, A. Yu

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Study of the Influence of Operating and Geometric Parameters on the Critical Outflow of Subcooled and Boiling Water through Channels of Different Geometry von Konovalov, I. A., Bol’shukhin, M. A., Khizbullin, A. M., Sokolov, A. N., Barinov, A. A., Loktionov, V. D., Dmitriev, S. M., Zyryanova, T. K.

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Experimental study of a passive system for lowering damaging pressure levels in the protective shell of the KLT-40S reactor facility von Bakhmetiev, A. M., Bolshukhin, M. A., Khizbullin, A. M., Kamnev, M. A.

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Integration of the Computational Validation Process for Reactor Equipment into a Single Information Space to Create Digital Doppelgangers of Nuclear Energy Facilities von Belokrylov, P. Yu, Bol’shukhin, M. A., Komissarov, K. V., Petrunin, V. V., Poverennov, E. Yu

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Supercomputer Twin of a Nuclear Energy Installation: Developmental Approaches and Application Experience von Bol’shukhin, M. A., Bolnov, V. A., Budnikov, A. V., Ereev, M. N., Zotova, M. V., Zotov, I. S., Lepekhin, A. N., Panov, V. A., Petrunin, V. V., Rogozhkin, S. A., Romanov, R. I., Fomichev, V. I.

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Key Results of Computational and Experimental Studies of Passive Systems of Emergency Heat Removal von Bakhmet’ev, A. M., Bol’shukhin, M. A., Kamnev, M. A., Khizbullin, A. M., Sokolov, A. N.

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Computational and Experimental Studies of Mixing of a Light Gas in the ERCOSAM–SAMARA Projects von Bakhmet’ev, A. M., Bol’shukhin, M. A., Kamnev, M. A., Khizbullin, A. M., Tyurikov, O. V.

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Developing SupercomputerTwins Of NuclearPowerPlants ForVarious Applications With The Use Of Russian 3D Numerical Analysis Codes von Bolnov, V A, Bolshukhin, M A, Budnikov, A V, Dmitriev, S M, Zotova, M V, Zotov, I S, Petrunin, V V, Sveshnikov, D N, Romanov, R I

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Experimental validation of the cooling loop for a passive system for removing heat from the AES-2006 protective envelope design for the Leningradskaya nuclear power plant site von Bakhmet’ev, A. M., Bol’shukhin, M. A., Vakhrushev, V. V., Khizbullin, A. M., Makarov, O. V., Bezlepkin, V. V., Semashko, S. E., Ivkov, I. M.

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A method of quantitative analysis of rapid thermal processes through vessel walls under nonisothermal liquid flow von Bolshukhin, M. A., Znamenskaya, I. A., Fomichev, V. I.

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An experimental substantiation of the emergency cooldown system project for the KLT-40S reactor installation of a floating nuclear cogeneration station von Balunov, B. F., Shcheglov, A. A., Il’in, V. A., Saikova, E. N., Bol’shukhin, M. A., Bykh, O. A., Khizbullin, A. M., Sokolov, A. N.

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Thermographic study of turbulent water pulsations in nonisothermal mixing von Bol’shukhin, M. A., Znamenskaya, I. A., Sveshnikov, D. N., Fomichev, V. I.

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Methodology for Lifetime Assessment of Reactor Plant Equipment and Systems Based on Damaged Medium Mechanics von Mitenkov, F. M., Bol’shukhin, M. A., Kozin, A. V., Korotkikh, Yu. G., Panov, V. A., Pakhomov, V. A., Kaplienko, A. V.

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Experimental studies of heat transfer during steam condensation on a vertical multirow on-line bundle of slightly inclined coil tubes with and without noncondensable gas in the bun... von Tarasov, G. I., Bol’shukhin, M. A., Sinitsyn, A. N., Vasyatkin, A. G., Kustov, S. V.

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Simulation of Fatigue Processes in the Structural Materials of Reactor Vessels Over a 102 – 1012 Cycle Durability Range von Bol’shukhin, M. A., Ereev, M. N., Kozin, A. V., Panov, V. A., Kaplienko, A. V.

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MODELING DAMAGE ACCUMULATION PROCESSES RESULTINGFROM THERMAL PULSATION von Bolshukhin, M. A., Lebedev, V. V., Kozin, A. V., Korotkikh, Yu. G., Panov, V. A., Pakhomov, V. A.

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Simulation of Fatigue Processes in the Structural Materials of Reactor Vessels Over a 10 super(2) - 10 super(12) Cycle Durability Range von Bol'shukhin, MA, Ereev, M N, Kozin, A V, Panov, V A, Kaplienko, A V

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A TECHNOLOGY OF OPERATIONAL MONITORING OF NNPEQUIPMENT AND SYSTEMS von Mitenkov, F. M., Bolshukhin, M. A., Kozin, A. V., Korotkikh, Yu. G., Panov, V. A., Pakhomov, V. A., Pichkov, S. N.

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Fuelling floating reactors von Samoilov, O B, Kuul, V S, Morozov, O A, Alexeev, V I, Bolshukhin, M A

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