Search Results - "Migrov, Yu. A."

The Development of a Method for Validation of the Uncertainties of the Models Used in Thermal-Hydraulic Codes by Gritsai, A. S., Migrov, Yu. A.

“…The article deals with one of the most crucial and, at the same time, problematic stages of implementing the uncertainty analysis of thermal-hydraulic…”
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Computational and Experimental Validation of a Passive Heat Removal System for NPP Containment with VVER-1200 by Bezlepkin, V. V., Zatevakhin, M. A., Krektunov, O. P., Krylov, Yu. V., Maslennikova, O. V., Semashko, S. E., Sharapov, R. A., Efimov, V. K., Migrov, Yu. A.

“…The EUR-required passive system for protection against unanticipated accidents in nuclear reactors has been developed. This system and the computational…”
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KMS Stand: Large-Scale Model of NPP Containment with VVER by Vasilenko, V. A., Migrov, Yu. A., Zasukha, V. K., Efimov, V. K., Bezlepkin, V. V., Semashko, S. E.

“…The main technical characteristics of the KMS stand as a large-scale model for NPP containment with VVER are presented. It is shown that this stand can be used…”
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Value and Place of the KMS Large-Scale Stand in Solving Safety Problems for NPP with VVER by Vasilenko, V. A., Migrov, Yu. A., Zasukha, V. K., Efimov, V. K., Bezlepkin, V. V., Semashko, S. E.

“…Pressing questions concerning experimental modeling of thermohydraulic processes in NPP containment are examined. Domestic and foreign stands are briefly…”
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Certain Problems of Lengthened Cooldown of NPP–VVER Power Units in Accidents with Loss of Primary-Loop Coolant by Migrov, Yu. A., Gudoshnikov, A. N.

“…The influence of certain physical phenomena on the reliability of cooldown of next-generation VVER cores during long-time passive cooldown in accidents with…”
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Verification of the computer code KORSAR taking into account the effect of nondensables on thermal-hydraulic processes by Gudoshnikov, A. N., Migrov, Yu. A.

“…Calculations to verify the Russian computer code KORSAR were carried out for the B4.1 experimental operating conditions, in which nitrogen was supplied to the…”
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Assessment of uncertainties of the models used in thermal–hydraulic computer codes by Gricay, A. S., Migrov, Yu. A.

“…The article deals with matters concerned with the problem of determining the statistical characteristics of variable parameters (the variation range and…”
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Experience with introduction and development of the KORSAR computer code for substantiating the safety of NPSs with type VVER reactors by DRAGUNOV, Yu. G, BYKOV, M. A, VASILENKO, V. A, MIGROV, Yu. A

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Distinctive features of the model of the drift of phases used in computational dynamic reactor programs by Khabenskii, V. B., Migrov, Yu. A., Tokar', O. V.

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Study of heat and mass transfer between a heated channel and an upper mixing chamber by Malkin, S. D., Khabenskii, V. B., Migrov, Yu. A., Efimov, V. K.

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Abstracts of papers deposited at VINITI by Savin, V. K., Korger, M., Miksher, A. M., Volkov, M. A., Gromov, M. A., Mikhailov, V. D., Volzin, V. D., Kirillov, V. A., Kasamanyan, M. A., Kuzin, V. A., Klimenko, A. P., Korolev, V. I., Ostapchuk, N. V., Grosul, T. N., Zelinskii, G. S., Kamyshnik, L. D., Aleinikov, V. I., Davidson, V. E., Eliseev, V. I., Tolstopyat, A. P., Golubkovich, A. V., Rubinshtein, S. V., Saburov, . N., Karpov, S. V., Malkin, A. Ya, Glushkov, I. A., Rozhkov, V. A., Kuznechikov, A. V., Konstantinov, E. N., Grekov, S. P., Kalyusskii, A. E., Arutyunov, B. A., Vlasov, V. V., Gukhman, A. A., Mishchenko, S. V., Tsymarnyi, V. A., Potienko, N. F., Zysin, L. V., Migrov, Yu. A., Tsirel'man, N. M., Vidin, Yu. V., Pshenichnov, Yu. A., Prilutskii, V. A., Khorol'skii, V. M., Mamedov, A. M., Mikhel' son, M. L., Abramov, L. E., Alekseev, V. K., Nasedkin, V. V., Nasedkina, A. P., Kurkin, V. P., Alekseev, V. P., Doroshenko, A. V., Maksimovich, V. N., Plyatsko, G. V., Benyakovskii, M. A.

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Distinctive features of the model of the drift of phases used in computational dynamic reactor programs by KHABENSKII, V. B, MIGROV, YU. A, TOKAR, O. V

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