[en] Modules permitting to conduct multigroup diffusion finite-difference calculation of integrals in the perturbation theory and reactivity in the nodes of the calculation grid for two-dimensional xy and RZ-geometry are described. Direct calculations are compared with the calculations by the perturbation theory. The modules are written in the Algol-GDR language for the BESM-6 computer and connected in the NF-6 complex for calculation of the main neutron-physical pertormance of nuclear reactors. The calculations are carried out for the BOR-60 reactor

[en] Described are the method and programs for multigroup diffusion finite-difference calculations of neutron flux density and neutron worth in nuclear reactors for two-dimensional XY and RZ geometry are described. The finite difference equations within the range of one group (at a given fission source) are solved by the iterative method of variable direction. The acceleration by the two-layer Chebyshev extrapolation is used in iterations according to the fission source. The results of investigations of efficiency of acceleration algorithms used while solving physically dissimilar problems are presented. The programs are involved as modules into the NF-6 complex for calculation of the main nuclear reactor neutron-physical characteristics. Programs are written in the ALGOL-GDR language for the BESM-6 computer and allow to carry out the calculation for an.y number of groups, for which there is constant software

[en] Conception of power nuclear reactor with steam coolant is considered. Use of heat of water-steam phase transformation decreases sufficiently coolant mass flow rate and provides high-effective heat removal at small heating (∼10-50deg C), steam temperature at reactor outlet of 360-400deg C and 10-16MPa pressure. Designs of steam cooled reactor conception are based on the experiennce of designing and operation of WWER (the use of WWER reactor vessels and fast (fuel elements and fuel assemblies reactors. NPP layout is dual-circuit, but single-circuit one is also possible. Preliminary economic analysis shows that specific capital outlays for construction of considered reactors are comparable with those for WWER reactors. The conclusion about the necessity for further studies is made

[en] The concept on designing the global energy system, meeting the modern safety requirements and able to utilize radioactive wastes (White Earth) is presented

[en] The mathematical description of set of 17 automodelling dynamic processes and phenomena in various continuum is submitted, beginning from a liquid and finishing the technocratic continuum. Dynamic processes in physical, ecological, economic and social systems are described by similar laws of dynamic evolution and statistical distributions. Examples of use of these universal laws for the decision of sets prognostic problems are given

[en] Error evaluations of calculations of the effective neutron multiplication factors (Ksub(eff)), conversion ratio (CR) and core conversion ratio (CCR) of fast power reactors have been performed. The evaluations are based on the cross section error covariant matrix composed by an analysis of the latest experimental data on differential neutron cross sections containing in the BNAB-78 library. The sensitivity coefficients ksub(eff), CR and CCR to the group cross sections were calculated using the TVK-2D two-dimensional code on the basis of the generalized perturbation theory. Thus obtained error evaluations of ksub(eff) and the conversion ratios approximately 2.5 % and approximately 3.5 % (at the 67 % c.l.) respectively have proved more optimistic than those 3-5 % and 5-8 % respectively reported earlier elsewhere. A substantial role of uncertainties in the available data on ²⁴¹Pu and inelastic scattering cross sections in the errors calculated has been identified. Recommendations to improve the accuracy of the calculations of fast reactor characteristics are given

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[en] This paper describes the improvement of the potential of the safety for the projects of lead-cooled fast breeder reactors which are in progress in the Russian Federation. The calculations of the accidents and the responses to perturbations of the steady state are performed. The improvement of the core behavior by optimization of the feedback coefficients and by insertion of passive system is realized using the description of the safety potential for these new projects

[en] One of really possible concept of a nuclear power plant with the modular fast liquid metal cooled reactor is suggested. It is characterized by high level of safety due to inherent safety and high potential of fuel breeding due to interassembly heterogeneous arrangement of the reactor core

[en] The concept of a reactor plant with a modular liquid-metal cooled fast reactor is considered. The proposed concept realizable at the present-day level of reactor technology development is characterized by a high-degree of safety provided by self-protection and increased fuel breeding based on the intra-assembly heterogeneous arrangement of the reactor core. 10 refs.; 2 tabs