Search Results - "Bezrukov, Yu. A."

An investigation of the survivability of fuel-rod claddings during the first stage of the maximum design basis accident at a nuclear power station with a VVER reactor by KARETNIKOV, G. V, BEZRUKOV, Yu. A, BOGDANOV, A. S, TRUSHIN, A. M, ONSHIN, V. P, SMIRNOV, A. V

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Investigation of the mixing of coolant flows in a VVER Vessel by BEZRUKOV, Yu. A, DRAGUNOV, Yu. G, LOGVINOV, S. A, UL'YANOVSKII, V. N

“…The mixing of flows in a flow-through channel of a VVÉR-1000 reactor in the case where a flow with high or low boron concentration and a flow whose temperature…”
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Experimental substantiation of the workability of heat exchangers used in a passive heat removal system in a tropical environment by TUPIKOV, P. A, DRAGUNOV, Yu. G, POPADCHUK, V. S, KHARCHENKO, S. A, BEZRUKOV, Yu. A, KHARINA, I. L

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An analysis of correlations for calculating critical heat fluxes in substantiating the safety of a reactor plant by Bezrukov, Yu. A., Astakhov, V. I., Bykov, M. A., Strebnev, N. A., Lisenkov, E. A.

“…The experimental data and correlations for calculating critical heat flux that are used in substantiating the safety of a VVER-1200 reactor plant are analyzed…”
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The analysis of signal amplitude estimation methods when determining parameters of power quality by Lavrukhin, A. A., Kochekov, A. V., Bezrukov, Yu. A., Denisova, L. A.

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An Analysis of Correlations for Calculating Critical Heat Fluxes in Substantiating the Safety of a Reactor Plant by BEZRUKOV, Yu. A, ASTAKHOV, V. I, BYKOV, M. A, STREBNEV, N. A, LISENKOV, E. A

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