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
The development of the TRAP-97 software system. A sensitivity analysis M. A. BykovS. I. ZaitsevV. I. Gusev OriginalPaper Pages: 53 - 61
Improvement of the TRAP-97 computational system. Taking into consideration spatial effects in the reactor M. A. BykovS. I. ZaitsevV. I. Gusev OriginalPaper Pages: 48 - 52
Experience with introduction and development of the KORSAR computer code for substantiating the safety of NPSs with type VVER reactors Yu. G. DragunovM. A. BykovYu. A. Migrov OriginalPaper Pages: 43 - 47
Consideration of field experience in developing new projects of steam generators for nuclear power stations equipped with VVER reactors N. B. TrunovV. V. DenisovB. I. Lukasevich OriginalPaper Pages: 37 - 42
Investigation of thermohydraulic processes in steam generators for nuclear power stations equipped with VVER reactors N. B. Trunov OriginalPaper Pages: 26 - 36
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. KaretnikovYu. A. BezrukovA. V. Smirnov OriginalPaper Pages: 19 - 25
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. DragunovV. S. StepanovV. Z. Kuklin OriginalPaper Pages: 14 - 18
Experimental substantiation of the workability of heat exchangers used in a passive heat removal system in a tropical environment P. A. TupikovYu. G. DragunovI. L. Kharina OriginalPaper Pages: 10 - 13
Improvement of the projects of reactor installations Yu. G. DragunovS. B. RyzhovV. A. Mokhov OriginalPaper Pages: 1 - 9
