[en] The PRIZMA-D code is intended for solving by the Monte Carlo method of the problems, connected with calculations of nuclear reactors and critical assemblies. Taking into account the effect of the perturbation on the distribution of the source division points is carried out by means of the method of small iterations for the division points. This method is described in the paper. Possibilities of its application are shown by the examples of calculations of some problems. The comparative results are presented

No abstract available

[en] Highlights: • PRIZMA is a Monte Carlo code for solving fixed source and criticality problems. • Particles: neutrons, gammas, electrons, positrons, ions. • Application fields: nuclear and radiation safety; pulsed, thermal and fast reactors. • PRIZMA is a part of package for precision core simulation through reactor campaign. • Special techniques for perturbation analysis. - Abstract: For more than thirty years the code PRIZMA has been used at RFNC-VNIITF for solving radiation transport problems with the Monte Carlo method. The code models the separate and coupled transport of neutrons, photons, electrons, positrons and ions in one-, two-, and three-dimensional geometry. For criticality calculations the code implements the method of generations with a constant number of fission sites in one generation. Now the code is extending its capabilities for nuclear reactor calculations. The paper describes the current status of the code and gives examples of its application to particle transport in nuclear reactors and other physical facilities

[en] For more than thirty years the code PRIZMA has been used at RFNC-VNIITF (Snezhinsk, Russia) for solving radiation transport problems with the Monte Carlo method. The code models the separate and coupled transport of neutrons, photons, electrons, positrons and ions in one-, two-, and three-dimensional geometry. For criticality calculations the code implements the method of generations with a constant number of fission sites in one generation. Now the code is extending its capabilities for nuclear reactor calculations. The paper describes the current status of the code and gives examples of its application to particle transport in nuclear reactors and other physical facilities. (authors)