Development and verification of the TR-BN software for substantiation of normal operation modes of BN reactors von Fadeev, I.D., Dmitrieva, I.V., Osipov, S.L., Rogozhkin, S.A., Shepelev, S.F.

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Computational and experimental studies of the causes of crack network formation in the area of the heat exchanger tube sheet in the BN'600 reactor von Vilenskij, O. Yu, Krylov, A.N., Osipov, S.L., Osetrov, D.L., Rogozhkin, S.A., Margolin, B.Z., Prokoshev, O.Yu, Pozdnyakov, M.L., Gulenko, A.G.

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Study of functional characteristics for safety system check valve using scaled model von Baluyev, D.E., Gusev, D.V., Meshkov, S.I., Nikanorov, O.L., Osipov, S.L., Rogozhkin, S.A., Rukhlin, S.V., Shepelev, S.F.

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Refinement of the Parameters of a Reactor Installation and Thermohydraulic Characteristics of the Main Equipment, Based on Commissioning Results for a Power Unit with BN-800 von Fadeev, I. D., Dmitrieva, I. V., Pakholkov, V. V., Rogozhkin, S. A., Shepelev, S. F.

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Turbulent convective heat transfer in an inclined tube filled with sodium von Vasil’ev, A. Yu, Kolesnichenko, I. V., Mamykin, A. D., Frick, P. G., Khalilov, R. I., Rogozhkin, S. A., Pakholkov, V. V.

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Numerical Modeling of Delayed-Neutron Precursor Transport in a Sodium-Cooled Fast Reactor von Rogozhkin, S. A., Osipov, S. L., Salyaev, A. V., Usynina, S. G., Pokhilko, V. I., Sazonova, M. L.

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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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Experimental investigation of a new method for advanced fast reactor shutdown cooling von Pakholkov, V. V., Kandaurov, A. A., Potseluev, A. I., Rogozhkin, S. A., Sergeev, D. A., Troitskaya, Yu. I., Shepelev, S. F.

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Computational and Experimental Validation of the Planned Emergency Heat-Removal System for BN-1200 von Zaryugin, D. G., Poplavskii, V. M., Rachkov, V. I., Sorokin, A. P., Shvetsov, Yu. E., Rogozhkin, S. A., Shepelev, S. F.

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Scientific and technical communications: computational and experimental studies substantiating setups for localizing fast-reactor melted fuel von Rogozhkin, S.A, Osipov, S.L, Sobolev, V.A, Shepelev, S.F, Kozhaev, A.A, Mavrin, M.S, Ryabov, A.A

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Numerical Modeling of Thermohydraulic Processes in the Upper Chamber of a Fast Reactor von Rogozhkin, S. A., Osipov, S. L., Fadeev, I. D., Shepelev, S. F., Aksenov, A. A., Zhluktov, S. V., Sazonova, M. L., Shmelev, V. V.

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THE DEVELOPMENT OF THE COMPUTATIONAL MODEL OF A FAST-NEUTRON REACTOR WITH A SYSTEM FOR HEAT REMOVAL THROUGH THE FUEL ASSEMBLY INTERWRAPPER SPACE von Anfimov, A.M., Kirilov, I.N., Kuznetsov, D.V., Rogozhkin, S.A.

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Effect of Pulsed Fluxes of Deuterium Ions and Deuterium Plasma on Oxide Dispersion Strengthened Ferritic Steels von Gribkov, V. A., Demina, E. V., Demin, A. S., Maslyaev, S. A., Pimenov, V. N., Prusakova, M. D., Sirotinkin, V. P., Rogozhkin, S. V., Lyamkin, P. V., Padukh, M.

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