[en] Chernobyl decommission plan which meets IAEA safety recommendations was developed. It is aimed to conservation of NPP equipment for at least 30 years with works on reactor dismantling

[en] Based on the examples of typical fuel cycles of WWER-1000 reactor the approaches and criteria allowing to perform the evaluation of effectiveness are considered. Particular attention is focused on the fact that during the operation of fuel loading the average level of reactor heat power is lower to nominal

[en] In the member countries of the Commonwealth of Independent States there are 14 power blocks operating with VVER-1000 nuclear reactors. Each block is equipped with four steam generators, 35 of which have already broken down without finishing one fourth of their service life. In 17 nuclear power plants in the world, in the period from 1979 to 1993 50 steam generators were likewise replaced, having completed 14 years instead of the guaranteed 30 years, owing to the corrosion damage to a large number of pipes of the heat-transfer surface. In the case of nuclear power plants with VVER-1000 reactors the reason is different-cracks in the output manifolds

[en] The project tasks 'Elaboration of Management System and introduction of Quality Assurance System in NNPC 'Energoatom' have considered. The aims on each tasks packet are given

[en] The base of an optimization for a periodicity of the safety systems control, possessing one or some reserve channels, are developed with the regeneration method

[en] It is revealed that the cause of outlet ('cold') collector failures in the PGV-1000 and PGV-1000M steam generators is the mechanism of material damage in connetors between holes in collector wall, principally new in the practice of steam generator engineering. It is shown that location of the damaged connectors is determined by pipe sheet structural peculiarities damage maximum lays near the wedge area on the one hand, and by specific features of therma-hydraulic process character in steam generator volume (the second maximum lays near the edge end) on the other hand). The connector damage character may be interpreted as that of fatigue type and should be determined by thermal-hydraulic processes in staem generator volume. 7 refs., 3 figs

[en] The article adduces results of the optimum control periodicity account for the system of the reactor emergency cooling by high pressure pumps. Authors showed the control periodicity can be increased in several times with respect to regulations control periodicity

[en] This paper describes the method used at Rivne NPP to provide an analytical justification for their EOIs. In addition, operating experience from many operating PWR plants in the U.S. and around the world was used. The work is being conducted in two phases: the first phase performs all of the reviews and assessments necessary to determine the new analyses required to justify the EOIs, in the second phase, these new analyses are conducted and documented, and the EOI Analytical Justification report will be written

[en] Applicability of aqueous solutions of low-molecular organic aliphatic acid production wastes for deposit removal from steam turbine condenser tube systems at NPPs with WWER-1000 is studies. The results of analysis of the efficiency of different metal acid corrosion inhibitors are summarized. Advisability of their application from technical and ecological viewpoints is proved

[en] The procedure, algorithm and criterions of determination of a burnup of the irradiated nuclear fuel in process of overloading are described. The feature of the procedure, algorithm and criterions consists in the account of initial enrichment and cooling time nuclear fuel after irradiation