Thermophysical studies for validating new-generation nuclear-reactor designs von Efanov, A. D., Kalyakin, S. G., Sorokin, A. P.

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EXPERIMENTAL INVESTIGATION OF THE CHARACTERISTICS OF THE THROUGH PART OF A LIQUID-METAL TARGET BASED ON A LEAD-BISMUTH ALLOY von BEZNOSOV, A. V, MELUZOV, A. G, NOVOZHILOVA, O. O, EFANOV, A. D

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Thermohydraulic studies of sodium-cooled reactor facilities von Poplavksii, V. M., Efanov, A. D., Zhukov, A. V., Kalyakin, S. G., Sorokin, A. P., Yuriev, Yu. S.

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Sodium as a coolant for fast reactors von Poplavskii, V. M., Efanov, A. D., Kozlov, F. A., Sorokin, A. P., Korolkov, A. S., Shtynda, Yu. E.

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Heavy Liquid Metal Coolant – Lead–Bismuth and Lead – Technology von Zrodnikov, A. V., Efanov, A. D., Orlov, Yu. I., Martynov, P. N., Troyanov, V. M., Rusanov, A. E.

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Experimental investigations of the thermohydraulic parameters of the flow section of a liquid-metal target with a window for a proton beam from an accelerator von BEZNOSOV, A. V, DAVYDOV, D. V, MELUZOV, A. G, LYAKHOVA, P. I, EFANOV, A. D

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Table for Critical Heat Fluxes in Square-Packed Fuel-Element Assemblies von Bobkov, V. P., Efanov, A. D., Smogalev, I. P., Pomet'ko, R. S.

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Hydrodynamic characteristics of an experimental model of the target in the MK-1 liquid-metal target system von Boronin, A. A., Efanov, A. D., Levchenko, Yu. D., Orlov, Yu. I., Fedotovskii, V. S.

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Lithium in nuclear and thermonuclear power engineering von Loginov, N I, Efanov, A D, Arnoldov, M N, Morozov, V A

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Investigation of thermodynamic properties of sodium-lead system von Efanov, A D, Loginov, N I, Morozov, V A, Morozov, A V, Mikheyev, A S

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Basic Questions Concerning the Thermophysics of Nuclear Power von Gulevich, A V, Efanov, AD, Kirillov, P L, Kozlov, F A

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Experimental investigations of the characteristics of a liquid-metal target based on a lead-bismuth eutectic alloy von BEZNOSOV, A. V, MELUZOV, A. G, DAVYDOV, D. V, PINAEV, S. S, ORLOV, Yu. I, EFANOV, A. D, EFIMOV, E. I, RACHKOV, V. I

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Development of an integrated computer code for simulating processes occurring in the containment shell of nuclear power plants with VVÉR reactors von GABARAEV, B. A, EFANOV, A. D, ZAICHIK, L. I, MELIKHOV, O. I, SOLOV'EV, S. L, SOLOV'EV, A. L

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Thermohydraulic Aspects of Deep Burnup of Nuclear Fuel in Fast Reactors von Efanov, A. D., Sorokin, A. P., Zhukov, A. V., Bogoslovskaya, G. P., Sorokin, G. A.

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Experimental database on fast-reactor thermohydraulics for computational code verification von Efanov, A. D., Sorokin, A. P., Zhukov, A. V., Kuzina, Yu. A., Denisova, N. A., Sorokin, G. A., Fedosova, M. A.

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Thermal-Hydraulics, Physical Chemistry, and Technology at Nuclear Power Stations Equipped with Fast-Neutron Sodium-Cooled Reactors von ALEKSEEV, V. V, EFANOV, A. D, KOZLOV, F. A, SOROKIN, A. P

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The effect of droplet sprinkling on the oxidation kinetics of zirconium cladding in steam von Dzhusov, Yu.P., Efanov, A.D., Kalyakin, S.G., Khoruzhii, O.V., Likhanskii, V.V., Malynkin, V.G., Matweev, L.V., Shumsky, R.V., Stein, Yu.Yu, Volcheck, A.M.

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Thermal Experiments on a Model of a Target for an Accelerator-Driven System von Efanov, A D, Orlov, Yu I, Sorokin, A P, Ivanov, E F, Bogoslovskaya, G P, Li, N

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Ileotyphlitis von Dantsig, I I, Efanov, D A, Levin, N F, Kiselev, A I, Remizov, A S

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Heat transfer during boiling of a liquid metal during emergency cooldown of a fast-neutron reactor von Sorokin, A. P., Efanov, A. D., Ivanov, E. F., Martsinyuk, D. E., Bogoslovskaya, G. P., Rymkevich, K. S., Mal’kov, V. L.

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