[en] The formats represent a generalization and extension of the English formats ''Parker, K., the Aldermaston Nuclear Data Library as at May 1963''. (AWRE 0-70/63, September 1963). An important feature of the formats proposed here is the introduction of a special classification of the information according to the type of representation. This makes the system of nuclear data storage more flexible and allows the capabilities of modern computers to be more fully utilized. This complete format description of the SOKRATOR library (Soviet Library of Evaluated Nuclear Data) is a translation from Russian original and its supplement. The document will help the user of SOKRATOR files to understand the physics definitions and coding conventions for the various types of numerical data

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[en] The approximations of the nonstationary diffusion equation, taking into account the type of the solution, characteristic to the pulse neutron experiments, are considered. In some simple cases the asymptotic stability and method convergence are proved. A short description of the numerical solution program of the two-dimensional multigroup diffusion equations of instantaneous neutrons is presented

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[en] In detail algorithms and programs are described for calculating angular and energy distributions of products of a wide variety of nuclear reactions within the framework of the statistical model. The program provides for a possibility to account for up to nine competitive fission channels. Corrections for the fluctuation of level widths are introduced within the framework of the Mohldauer formalism. Parameters of optical potentials required for the penetrability coefficient calculations can be selected either automatically according to optical potential versions or be set by input data. The program is written in FORTRAN and is designed for use both in the BESM-6 computer and in the EC-1030 computer. The total program capacity is about of 60 K of words

[en] Investigated is the possibility of using the optical model and the Hauser-Feshbach formalism for describing neutron elastic and inelastic scattering in the 2-14 MeV range in the case of a fixed parameter set. The calculations are compared with the data of the BNL 400 library. Calculated is the ratio of the differential cross section to the Reserford one in the 16 MeV proton elastic scattering on sup(58,60,62,64)Ni, ⁹⁰Zr, ¹²⁰Sn, ²⁰⁸Pb nuclei. Calculations made in the framework of the optical model with an account of the elastic scattering processes going through a compound nucleus are compared with the calculations in the framework of the optical model alone. The conclusion is drawn, that the neutron elastic scattering processes in the energy range from 1 to 14 MeV can be described in the framework of a single fixed parameter set using the Hauser-Feshbach formalism. The inelastic scattering at low energies is well described in terms of a statistic model while at higher energies other more consequent approaches should be used

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[en] The problems of numerical optimization of parameters of neutron transport in hydrogen and oxygen are considered. Additivity of optimization effect in calculations of passing of neutrons of division spectrum in the spherical layer of water of large optical depth is investigated. Analysis of quality of functional calculations of neutron flux in the water by REMPI programm, realized ''yield+P₁'' approximated model is carried out. The ''Yield+P₁'' approximated model, realized in the REMPI programm, well describes the space-energy distribution of the neutrons in the wide range of the depths of the water layer. The parameters of the ''Yield+P₁'' approximated model, characterizing interaction of the neutrons with hydrogen and oxygen nucleus, are mutually adjusted and optimal in the known extent

[en] Described is the algorithm for solution of the problem relating to kinetics of the deformed-stressed state of the fuel element, which is based on the finite difference method. The nonlinear relationship between the stresses and deformations is reduced to the system of the transcendental equations for the functions describing this relationship. To improve stability of the differential circuitry and convergence of the range method during solution of the finite difference equations, there is introduced a regularization parameter. Considered are cylindrical axially-symmetrical rod-type (solid and hollow) and annular fuel elements with thin-walled jackets. The calculations are performed with due account for the plastic deformation, creep deformation, fuel and jacket swelling, coolant pressure, and irregularity of the temperature field. The calculation results are cited