1. The Moscow Power Institute’s Chair of Nuclear Power Stations turns fifty

   Announcement Pages: 673 - 674

2. 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
   • E. S. Mukhtarov

   OriginalPaper Pages: 675 - 681

3. 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
   • N. B. Trunov

   OriginalPaper Pages: 682 - 687

4. 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
   • M. Mansuri

   OriginalPaper Pages: 688 - 693

5. Thermohydraulic factors causing the growth of dynamic stresses and cracks in the heads of pressurized-vessel reactors

   • K. N. Proskuryakov

   OriginalPaper Pages: 694 - 698

6. 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
   • Yu. B. Vorob’ev

   OriginalPaper Pages: 699 - 705

7. 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
   • S. L. Solov’ev

   OriginalPaper Pages: 706 - 713

8. 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
   • A. V. Smirnov

   OriginalPaper Pages: 714 - 722

9. 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. V. Shishov

   OriginalPaper Pages: 723 - 728

10. Optimizing the process for chemically decontaminating the multiple forced circulation circuit of power units built around RBMK reactors

    • V. M. Krasnoperov
    • I. S. Orlenkov
    • A. M. Aleshin

    OriginalPaper Pages: 729 - 732

11. Raising the operational reliability of the steam generator of a BN-600 power unit in starting regimes

    • P. P. Govorov

    OriginalPaper Pages: 733 - 736

12. A system for monitoring the reliability of pump equipment during the operation of nuclear power stations

    • A. M. Bakhmet’ev
    • M. I. Davidenko
    • A. S. Smirnov

    OriginalPaper Pages: 737 - 742

13. 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
    • I. I. Kopytov

    OriginalPaper Pages: 743 - 748

14. Simulating spatial effects during condensation of steam in a model containment using the KUPOL-3D computer code

    • N. M. Vitushkina
    • A. A. Luk’yanov
    • N. N. Shan’gin

    OriginalPaper Pages: 749 - 754

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

    OriginalPaper Pages: 755 - 759