[en] The possibility for calculational study on physical processes in the IGR pulse uranium-graphite reactor core through the PRIZMA.D program with application of the correlation results in multivariant calculations is shown by example of one of the experiments. It is shown that the methodology, whereby the correlation results are obtained in one calculational task for multiple configurations, makes it possible to forecast reliably small experimental effects, starting with the percent fractions. The multivariant calculation for the task under consideration proved to be by 90 times more efficient as compared to the series of independent calculations

[en] Computer code PRIZMA based on Monte Carlo simulation was used for solving problems of medical physics. Our results were compared with the results of other authors in series of test calculations. The calculations of the spatial distribution of absorbed dose under tomographical examination were carried out. We numerically obtained the dependence of absorbed dose on scanning parameters: distance to the slice plane, slice thickness, penetration depth into a phantom etc. 5 refs., 6 figs., 2 tabs

[en] The experimental results of measuring the temperature in the IGR reactor laying are analyzed; it is shown, that the temperature measurement is impossible at the start moment due to the thermo-pairs heating and during 1 min after the start due to the system time lag. The three-dimensional program TEMPO on calculation of the reactor laying temperature field is developed. It is shown, that the above program forecasts the temperature field with the 10% error, which is sufficient at the present stage of works. The results of the laying temperature field calculations are presented

[en] Reactor-laser pumping process is studied theoretically. Problems of determining the value of U fission fragment energy input into the laser medium, contributed energy spatial distribution and pumping capacity time profile are solved. Calculational model of uranium nuclei fission fragment distribution, realized within the frames of the PRISMA program complex on the basis of the Monte Carlo method is described. The PRISMA program calculation results for active medium pumping capacity are presented with an account of delay process from the reactor

[en] Results of calculating energy and angular characteristics of (E_e>100 eV) electrons emitted from aluminium plate under oblique incidence of photons with (Θ₀=0-85) energy from 1 keV up to 7 MeV obtained by the Monte Carlo method (PRIZMA program) in three-dimensional geometry, are presented. Electron flux density was the basic determined value describing spectral and angular distributions of emitted electrons. Forward and backward electron output is of practical interest

[en] Calculation technique for particle transport in systems which include regular finite lattices with great amount of elements is suggested. Concept of mobile unit is introduced for efficient description of geometry of regions which contain lattices. Using mobile unit and introduction of coordinate system connected with lattice it is possible to formulate unified approach when types considering lattices of different and to realize it in unified universal geometric module. Using the suggested technique it is possible to conduct calculations of complex systems practically without any restrictions for cell number in the system. Calculation example for multiplication factor and neutron lifetime in critical periodical lattice of uranium rods in aqueous medium is given. 5 refs.; 1 fig.; 1 tab

[en] The results of measurement of the emission spectrum from a lead sphere (R=5 cm) with a central DT neutron sources are presented. The comparison with the results of the experiments carried out in USA and Japan and with Monte Carlo calculations performed using neutron constants BAS is given. 2 refs.; 1 fig

[en] Numerical calculation of the efficiency of xenon ionization chambers used for X-ray medical computer tomographs is conducted using Monte-Carlo method. The considered detector represents xenon ionization chamber with complete collection of carriers. Calculation of sensitivity of such a detector is boiled down to calculation of energy release in the sensitive volume of detector filled with a gas. Besides contribution of electrons producted in the inlet aperture substance and electrons of this detector into energy release is estimated and contribution of electrons producted in the neighbour detector elements is determined, as well. Calculation is made for 40, 60, 80, 100, 120 and 140 keV energy photons. Analysis of calculation results has shown, that electrons producted in gas layer contribute mainly into energy release. Effect of neighbouring detectors is maximum 1.7%. Contribution from electrons formed in electrode and inlet aperture constitutes 2.5-8%

[en] Possibilities of the PRIZMA code, intended for Monte Carlo calculations of radiation transport are considered. The contribution of the particles, that were in different situations, may be calculated by means of a developed method of tagged particles. A particle is marked by different types of a mark and the obtained results are fixed in dependence on the mark types. Possibilities of using the tagged particle method and a special method of simulation are shown

[en] Results of the calculations with BAS constant system of the number experiments on ²³⁵U- and ²³⁸U-systems are shown. Fission neutron spectra in SC BAS is defined from experiments, which show that this spectra differs from the Maxwell or Watt function. The calculations of neutron leakage spectra for uranium spheres with central 14 MeV sources are carried out. The good agreement of theoretical and experimental data is obtained