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AbstractAbstract
[en] The method proposed considers a problem for nonmlinear approximation of measured data and uses a counting characteristic to determine the paralytic and non-paralytic dead-time components, obtained as parameters that minimize quadratic functionals of the derivations. An algorithm for local minimum search was implemented in a Fortran-4 code. The results are in satisfactory agreement with the real system behaviour and the literature data
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[en] Results from reactor core calculations with the RELAP4/MODE6 code for the blowdown phase of loss-of-coolant accident (LOCA) in WWER-440 reactors are presented. The core boundary conditions are obtained from a previous primary loop calculation using the same code. An analysis is given of the thermohydraulic parameters in channels with different hot channel factors, and the thermomechanical behaviour of fuel rods is evaluated. A conclusion about reducing the conservatism of the results is drawn
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[en] The system described is based on the NESSEL-4 computer code. It allows the evaluation of the neutron-physical characteristics of the WWER reactor cell in the fast energy region (10.5 MeV - 4.65 KeV). The evaluated data for the YANKEE reactor obtained by the system are compared with the corresponding predictions of the NESSEL-4 code. 2 tabs., 4 refs
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[en] The fuel rod cladding reliability is analysed for WWER-440 reactor's operation conditions with power exceeding the rated values. The effects of the concentration of the corrosion products and of the other admixtures in the heat carrier on the reliability of the fuel rod sheets is assessed. The PRENTO code for maximal unfavourable cross sections along the height of the fuel elements is used. The increase in the concentration of the corrosion products in the heat carrier from 0.05 to 0.2 mg/kg, when the reactor operates with a power exceeding the rated values leads to a substantial decrease in the reliability of the fuel rod sheets. To increase it a diminution in the permissible deviations from the design dimensions and maintaining the corrosion products concentration in the limits of 0-0.05 mg/kg is necessary. 5 figs., 3 refs
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ACTINIDE COMPOUNDS, ALLOYS, CHALCOGENIDES, CHEMICAL REACTIONS, DATA, ENERGY SOURCES, ENRICHED URANIUM REACTORS, EXPANSION, FUELS, INFORMATION, MATERIALS, MECHANICAL PROPERTIES, NUMERICAL DATA, OXIDES, OXYGEN COMPOUNDS, POWER REACTORS, PWR TYPE REACTORS, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, SAFETY, THERMAL REACTORS, URANIUM COMPOUNDS, WATER COOLED REACTORS, WATER MODERATED REACTORS, WWER TYPE REACTORS, ZIRCONIUM ALLOYS
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AbstractAbstract
[en] The attenuation has been studied of the total 14 MeV neutron flux passing through an iron collimator and directly located behind lead slabs with thicknesses 2.5, 5.0, 7.5, 10.0 and 12.5 cm. A comparison is made between the calculated data and results from a benchmark experiment. The experiment is analysed with an one-dimensional model based on ANISN-code and a tree-dimentional model based on MORSE-code (Monte Carlo method). The energy dependences of the cross-sections and neutron fluxes are represented by a 25-group approximation based on the SUPERTOG program and the files ENDL and ENDF/B-4. The mean deviation of MORSE calculated data from experimental ones is 6.4% for ENDL-data and 8.5% for EDDF-data. ANISN-calculated data show practically full coincidence with experimental ones both for ENDL and ENDF
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[en] A method is proposed for modelling the behaviour of the first wall and divertor materials under the action of high-power heat flux in the case of emergency plasma filament disintegration, as well as for modelling the phase transitions in the lithium-containing eutectics of the blanket. The results of the calculations are presented. 4 figs., 8 refs
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[en] The spectrometric characteristics of a sandwich-type 6LiF neuton spectrometer are studied. The semiconductor detectors used are developed by the method of low-energy ion implantation. A layer of 6LiF is laid on one of the two detectors. Measurements for thermal neutron fluxes, reactor spectrum neutrons and 14 MeV neutrons have been carried out. The spectrometer exhibits good spectrometric properties (90 KeV for the maximum of tritium and 260 KeV for the maximum of the total energy), as well as high stability and radiation resistance
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[en] The energy distribution of neutrons slowing-down by elastic scattering in nonabsorbing media is studied. The slowing-down equation is analytically solved. The behaviour of the collision density function and its derivatives of n-th order is investigated. Exact mathematical expressions are derived for the differences Kn(n-1)(α-n) -Kn-1(n-1)(α-n) where n-1 denotes the n-1 derivative
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[en] A considerable amount of literature on heat transfer in case of emergency core cooling of pressurized water reactors is reviewed and a classification of the respective correlations is given. Based on a comparative analysis, recommendations are made concerning the heat transfer correlations for transition and film boiling with inverted annular flow, slug flow and dispersed flow
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[en] The REND code, based on the Warren model modified by Jaschik-Seifritz, has been used to simulate and study the characteristics of prompt neutron detectors with Hf, Er and Co emitters. The dependence of the basic characteristics such as the Compton and photoelectron escape efficiency, the coefficients of self-shielding and neutron flux depression as well as the generalized correction coefficient on the physical and geometric parameters of the detectors is investigated. Simulation data are presented for the variation of the effective electron current and the current produced by the fast and thermal neutron fluxes, with the geometric parameters. The changes in the corresponding sensitivities are also considered
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