Contents
Thermal Engineering


Vol. 58, No. 5, 2011


Prospects for Development of Nuclear Power Stations Equipped with VVER Reactors

Yu. M. Semchenkov and V. A. Sidorenko p. 361  abstract

Efficient Ways for Setting Up the Operation of Nuclear Power Stations in Power Systems
in the Base Load Mode

R. Z. Aminov, A. F. Shkret, E. Yu. Burdenkova, and M. V. Garievskii p. 370  abstract

A Comprehensive Approach to Selecting the Water Chemistry of the Secondary
Coolant Circuit in the Projects of Nuclear Power Stations Equipped with VVER-1200 Reactors

V. F. Tyapkov p. 377  abstract

The Problem of Optimizing the Water Chemistry Used in the Primary Coolant Circuit
of a Nuclear Power Station Equipped with VVER Reactors under the Conditions
of Longer Fuel Cycle Campaigns and Increased Capacity of Power Units

R. B. Sharafutdinov and N. L. Kharitonova p. 383  abstract

Development and Introduction of Information Technologies for Supporting
the Management of Maintenance and Repairs at Nuclear Power Stations

V. D. Gurinovich and Yu. A. Yanchenko p. 390  abstract

The Influence of the High-Temperature Coolant Purification System at Nuclear
Power Stations Equipped with VVER-1000 Reactors on the Formation of Dose Burdens

B. A. Gusev and V. M. Krasnoperov p. 396  abstract

Using Mathematical Models of a Power Unit for Testing the Algorithms
of Control Systems for the Kudankulam Nuclear Power Station

A. P. Zhukavin and A. O. Lebedev p. 399  abstract

Field Examination of the Erosion–Corrosion Wear of Pipelines
at Russian Nuclear Power Stations Equipped with VVER Reactors

V. I. Baranenko, V. M. Markochev, and Yu. A. Yanchenko p. 404  abstract

Results from Additional Field Examination of Pipelines Carried Out
at Russian Nuclear Power Stations in Accordance with the Mihama Program

V. N. Lovchev, D. F. Gutsev, G. V. Tomarov, A. A. Shipkov, and N. S. Koreshkova p. 412  abstract

An Experimental Substantiation of the Emergency Cooldown System Project
for the KLT-40S Reactor Installation of a Floating Nuclear Cogeneration Station

B. F. Balunov, A. A. Shcheglov, V. A. Il’in, E. N. Saikova, M. A. Bol’shukhin,
O. A. Bykh, A. M. Khizbullin, and A. N. Sokolov
p. 418  abstract

Formation of a Nuclear Reactor’s Molten Core Bath in a Crucible-Type Corium
Catcher for a Nuclear Power Station Equipped with VVER Reactors

S. V. Beshta, S. A. Vitol’, V. S. Granovskii, E. K. Kalyago, S. V. Kovtunova,
E. V. Krushinov, M. B. Sulatskaya, A. A. Sulatskii, V. B. Khabenskii,
V. I. Al’myashev, and V. V. Gusarov
p. 424  abstract

Form Factor and Its Influence on the Critical Heat Flux in Channels Having
Different Shapes with Heat Release Nonuniformly Distributed over the Length

V. P. Bobkov p. 429  abstract

A Method for Numerically Simulating the Thermal State of a Tube
with Punched Helical-Tape Finning

I. V. Galushchak, V. Ya. Gorbatenko, and A. A. Shevelev p. 435  abstract

A List of Journal Articles Published in 2009–2010 on Nuclear Power Engineering p.440


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