Contents
Thermal Engineering

Vol. 53, No. 1, 2006

Improvement of the Projects of Reactor Installations

Yu. G. Dragunov, S. B. Ryzhov, and V. A. Mokhov p. 1  abstract

Experimental Substantiation of the Workability of Heat Exchangers Used
in a Passive Heat Removal System in a Tropical Environment

P. A. Tupikov, Yu. G. Dragunov, V. S. Popadchuk, S. A. Kharchenko, Yu. A. Bezrukov, and I. L. Kharina p. 10  abstract

The SVBR-75/100 Reactor Installation. An Assessment of the Possibility
of Using It in Projects for Refurbishing Power Units of Nuclear Power
Stations Equipped with VVER Reactors

Yu. G. Dragunov, V. S. Stepanov, N. N. Klimov, S. N. Bolvanchikov, M. L. Kulikov,
A. V. Zrodnikov, G. I. Toshinskii, I. I. Kopytov, V. N. Krushel’nitskii, and V. Z. Kuklin p. 14  abstract

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

G. V. Karetnikov, Yu. A. Bezrukov, A. S. Bogdanov, A. M. Trushin,
V. P. Onshin, and A. V. Smirnov p. 19  abstract

Investigation of Thermohydraulic Processes in Steam Generators
for Nuclear Power Stations Equipped with VVER Reactors

N. B. Trunov p. 26  abstract

Consideration of Field Experience in Developing New Projects of Steam Generators
for Nuclear Power Stations Equipped with VVER Reactors

N. B. Trunov, V. V. Denisov, S. A. Kharchenko, and B. I. Lukasevich p. 37  abstract

Experience with Introduction and Development of the KORSAR Computer Code
for Substantiating the Safety of NPSs with Type VVER Reactors

Yu. G. Dragunov, M. A. Bykov, V. A. Vasilenko, and Yu. A. Migrov p. 43  abstract

Improvement of the TRAP-97 Computational System.
Taking into Consideration Spatial Effects in the Reactor

M. A. Bykov, S. I. Zaitsev, Yu. V. Belyaev, G. V. Alekhin, A. P. Egorov, and V. I. Gusev p. 48  abstract

The Development of the TRAP-97 Software System. A Sensitivity Analysis

M. A. Bykov, S. I. Zaitsev, G. V. Alekhin, S. A. Kurbaev, A. P. Egorov, and V. I. Gusev p. 53  abstract

Development of Mathematical Models for Substantiating the Safety
of Nuclear Power Stations and an Analysis of the Dynamics
of Accidents Associated with Intercircuit Leaks in the Steam Generators
of Reactor Installations with Lead–Bismuth Coolant

A. V. Dedul’ and I. S. Kras’ko p. 62  abstract

Burnout during Upward Flow of Steam–Water Mixture through Vertical Tubes with Spiral Inserts

V. I. Kisina and A. I. Leont’ev p. 65  abstract

Simulating the Distribution of Soluble Impurities during Boiling
in the Equipment of Thermal and Nuclear Power Stations

G. R. Dzhakhan Farnia and V. I. Gorburov p. 71  abstract

Heat Transfer during Natural Circulation and Laminary Flow
of Liquid through Vertical and Inclined Tubes

D. O. Fetisov and O. O. Mil’man p. 76  abstract

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