Contents
Thermal Engineering

Vol. 53, No. 9, 2006

The Moscow Power Institute’s Chair of Nuclear Power Stations Turns Fifty p. 673

A Combined Thermal and Strength Analysis of the Behavior of a VVER-440 Reactor’s Vessel
during an Accident Involving Core Melting

N. G. Rassokhin, V. D. Loktionov, and E. S. Mukhtarov p. 675  abstract

Results from Comprehensive Thermal and Chemical Tests of Steam Generator No. 2
in Unit 1 at the Volgodonsk Nuclear Power Station

V. I. Gorburov, Yu. F. Kutdyusov, I. O. Bud’kov, A. Yu. Petrov, A. G. Zhukov, and N. B. Trunov p. 682  abstract

Assessing the Influence of Uncertain Factors in Analyzing Emergency Processes
at Nuclear Power Stations Equipped with VVER-1000 Reactors

Yu. B. Vorob’ev, V. D. Kuznetsov, and M. Mansuri p. 688  abstract

Thermohydraulic Factors Causing the Growth of Dynamic Stresses and Cracks
in the Heads of Pressurized-Vessel Reactors

K. N. Proskuryakov p. 694  abstract

A Comparison of Procedures for Estimating the Impact of Nondensable Gases on Steam Condensation
Taking into Account the Interaction of Power Engineering Processes in the Primary Circuit
of a Nuclear Power Installation

O. E. Stepanov, A. V. Bulanov, V. E. Karnaukhov, M. L. Lukashenko, and. Yu. B. Vorob’ev p. 699  abstract

The Use of Supercritical Parameters of a Coolant—a Promising Path to Development
of Nuclear Power Plant Water-Cooled Reactors in the 21st Century

B. A. Gabaraev, V. N. Smolin, and S. L. Solov’ev p. 706  abstract

The Application of the BAGIRA Code for a Computational Analysis of Accident
Conditions Involving a Small Leak from the Reactor Coolant Circuit
on the PSB-VVER Test Facility

A. E. Kroshilin, V. E. Kroshilin, and A. V. Smirnov p. 714  abstract

The Application of Computational Fluid Dynamics for Determining the Hydraulic
Characteristics of Pipelines at Nuclear Power Stations

O. Yu. Novosel’skii, V. E. Petrov, A. P. Skibin, S. L. Solov’ev, and A. V. Shishov p. 723  abstract

Optimizing the Process for Chemically Decontaminating the Multiple Forced Circulation
Circuit of Power Units Built around RBMK Reactors

V. M. Krasnoperov, I. S. Orlenkov, B. A. Gusev, and A. M. Aleshin p. 729  abstract

Raising the Operational Reliability of the Steam Generator of a BN-600 Power Unit
in Starting Regimes

P. P. Govorov p. 733  abstract

A System for Monitoring the Reliability of Pump Equipment during the Operation
of Nuclear Power Stations

A. M. Bakhmet’ev, M. I. Davidenko, and A. S. Smirnov p. 737  abstract

Development in a Nuclear Power Station Project of Matters Concerning the Dismantling
of Equipment at the Stage of Power Unit Decommissioning

B. K. Bylkin, A. I. Berela, and I. I. Kopytov p. 743  abstract

Simulating Spatial Effects during Condensation of Steam in a Model Containment
Using the KUPOL-3D Computer Code

N. M. Vitushkina, A. A. Luk’yanov, and N. N. Shan’gin^† p. 749  abstract

A List of Journal Papers on Nuclear Power Engineering Published in 2005 p. 755

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