[en] Technology of intensive shock densification of deep (up to 6 m) layers of soft grounds for bases developed at the Kursk NPP experimental site is described. Data on increment in density of different types of densified grounds are given. Recommendations on application of the given method are presented

[en] Specific features of the Kursk-1 reactor reconstruction are considered. These features and difficulties of organization of work under conditions of NPP operation were analyzed, and complex of measures enabling to conduct the reconstruction qualitatively and effectively was suggested

[en] Short communication. 1 tab

[en] The corroded condition of four assembly channels was investigated after various service times. The inner surface of three of them in contact with the aqueous heat carrier was subjected to local nodule corrosion, the depth of which depends upon the neutron fluence. Within the scope of the electrochemical mechanism of the corrosion process an expression for the predicted thickness of the corrosion film of a nodule and an equation for calculation of the error are proposed. The linear regression method also provides close results in prediction for 20 years of service

[en] The process of improvement of safety of NPP's with RBMK-1000 reactors by technical upgrading and modifications is described, including the following issues: main goals of technical upgrading and modifications and their time table; main activities performed within technical upgrading and modification of the NPP units with RBMK-1000 of the first generation; complete scope of work for technical upgrading and modification of Kursk NPP units 1 and 2; the main work performed in technical upgrading and modification of NPP units with RBMK-1000 reactors of the 2nd generation

[en] To provide cooling of spent turbine condenser steam at the Krusk nuclear power plant, water is employed from a reservoir located on the flood plain of the Seim River. Makeup of reservoir losses during operation of the plant is provided by a pumping station installed beside an artificial channel of the river. The reservoir was filled with water from the Seim River in the spring flood period of 1976. The quality of the water in the reservoir and its effect on scaling and deposits in the turbine condensers are discussed. Since it is impossible to completely prevent scaling in the condensers by replacing the water, it is recommended that the condensers be periodically flushed with acid

[en] The paper presents the objectives, organisation, main findings and conclusions of the international review of the Kursk unit 1 safety analysis report (K1IRSR). The K1IRSR was administered by RISKAUDIT IRSN/GRS international and carried out by international experts from 7 western countries plus the Russian Federation, under the supervision of the safety review group (SRG) of the European bank for reconstruction and development (EBRD). The project was financed by the nuclear safety account (NSA) administered by the EBRD. The Russian experts worked under a contract with IBRAE financed by Rosenergoatom. The main conclusions were that the SAR followed a correct approach, broadly in line with Russian and international guidance documents, but needed improvement in structure and content. It established that the safety level of the unit has been increased significantly by the modernisation programme. The important deviations of the unit from current Russian regulations and the IAEA safety issues for RBMK are either fully resolved or are being addressed to the extent possible by compensatory measures to further reduce the risk. The K1IRSR experts have made a number of recommendations for improvement of the K1SAR. The authors agreed to take the recommendations into account in future revision of the K1SAR. (orig.)

[en] Short communication

[en] Highlights: • Modeling of vapor reactivity coefficient measurements on RBMK reactors was made. • Measurement reactor procedure is presented. • Detailed 3-D model of RBMK core and external systems is developed. • The results obtained are very closed to measurement ones. • These results can be used by Russian TSO of regulatory body in other calculations. - Abstract: The model implemented into coupled neutron-thermohydraulic code system ATHLET + QUABOX/CUBBOX for RBMK-1000 vapor reactivity coefficient measurements computer modeling is described. The results of ATHLET + QUABOX/CUBBOX modeling of Kursk NPP unit 1 vapor reactivity coefficient measurements are presented. Reasonable agreement between measurements and modeling results was shown

[en] A classification of the methods for residual lifetime evaluation is made. The main attention is given to the statistical methods. In the present work the controlled parameter is the equipment lifetime. A methodological approach has been developed allowing to estimate the lifetime of the components on the base of the operational experience, tested using the results from calculations of the failure fluence, obtained for the control rods at the Bilibin and Kursk NPP. Calculations are made for a large group of components