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An Analysis of Correlations for Calculating Critical Heat Fluxes in Substantiating the Safety of a Reactor PlantBEZRUKOV, Yu. A; ASTAKHOV, V. I; BYKOV, M. A et al.Thermal engineering. 2010, Vol 57, Num 5, pp 376-381, issn 0040-6015, 6 p.Article

Investigation of the mixing of coolant flows in a VVER VesselBEZRUKOV, Yu. A; DRAGUNOV, Yu. G; LOGVINOV, S. A et al.Atomic energy (New York, N.Y.). 2004, Vol 96, Num 6, pp 391-398, issn 1063-4258, 8 p.Article

A study of boron dilution in a VVER-1000 reactorsMELIKHOV, V. I; MELIKHOV, O. I; YAKUSH, S. E et al.Thermal engineering. 2002, Vol 49, Num 5, pp 372-376, issn 0040-6015Article

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 reactorKARETNIKOV, G. V; BEZRUKOV, Yu. A; BOGDANOV, A. S et al.Thermal engineering. 2006, Vol 53, Num 1, pp 19-25, issn 0040-6015, 7 p.Article

Experimental substantiation of the workability of heat exchangers used in a passive heat removal system in a tropical environmentTUPIKOV, P. A; DRAGUNOV, Yu. G; POPADCHUK, V. S et al.Thermal engineering. 2006, Vol 53, Num 1, pp 10-13, issn 0040-6015, 4 p.Article

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