1. Improvement of the projects of reactor installations

   • Yu. G. Dragunov
   • S. B. Ryzhov
   • V. A. Mokhov

   OriginalPaper Pages: 1 - 9

2. 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
   • I. L. Kharina

   OriginalPaper Pages: 10 - 13

3. 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
   • V. Z. Kuklin

   OriginalPaper Pages: 14 - 18

4. 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. V. Smirnov

   OriginalPaper Pages: 19 - 25

5. Investigation of thermohydraulic processes in steam generators for nuclear power stations equipped with VVER reactors

   • N. B. Trunov

   OriginalPaper Pages: 26 - 36

6. 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
   • B. I. Lukasevich

   OriginalPaper Pages: 37 - 42

7. 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
   • Yu. A. Migrov

   OriginalPaper Pages: 43 - 47

8. Improvement of the TRAP-97 computational system. Taking into consideration spatial effects in the reactor

   • M. A. Bykov
   • S. I. Zaitsev
   • V. I. Gusev

   OriginalPaper Pages: 48 - 52

9. The development of the TRAP-97 software system. A sensitivity analysis

   • M. A. Bykov
   • S. I. Zaitsev
   • V. I. Gusev

   OriginalPaper Pages: 53 - 61

10. 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’
    • I. S. Kras’ko

    OriginalPaper Pages: 62 - 64

11. Burnout during upward flow of steam-water mixture through vertical tubes with spiral inserts

    • V. I. Kisina
    • A. I. Leont’ev

    OriginalPaper Pages: 65 - 70

12. Simulating the distribution of soluble impurities during boiling in the equipment of thermal and nuclear power stations

    • G. R. Dzhakhan Farnia
    • V. I. Gorburov

    OriginalPaper Pages: 71 - 75

13. Heat transfer during natural circulation and laminary flow of liquid through vertical and inclined tubes

    • D. O. Fetisov
    • O. O. Mil’man

    OriginalPaper Pages: 76 - 79