[en] Analytic estimations of neutron pulse parameters in the coupled reactor system fast reactor - thermal subcritical block are obtained. The modeling calculations of pulse energy characteristics in a laser system pumped using the two zone pulse reactor (BARS) are performed. The comparison with results of direct simulation data are made

[en] A model of multisectional reactor facility dynamics, based on coupled reactor kinetic equations, is proposed. Effective algorithms for investigation of hard systems of differential equations realized in the form of the POKER programm complex for IBM PC/AT personal computer are developed. The complex is designed for simulating nonstationary processes in multisectional reactor facilities with regard to temperature feedback under various laws of changing the external reactivity and external neutron source intensity. 12 refs.; 3 figs

[en] The main results of the complex research and development carried out in 2013 by the Nuclear Reactors Physics Institute are presented. The bulk of studies was carried out in the framework of the Federal Target Program “Nuclear Power Technologies of New Generation in 2010-2015 and until 2020”. The calculation and experimental substantiation of projects BN-1200 with sodium coolant, BREST-OD-300 lead-cooled, multi-purpose research reactor MFRR, SVBR-100 lead-cooled and other projects are included in the scope of investigations. The results of the work obtained in the following areas of activity of experts: design validation of NPP with reactor installations WWER-1000 (NPP-2006), physics and technology of space NPU, efficient nuclear-optical energy converters of pulse action are discussed. The collection contains materials on substantiation of conceptual innovation projects of NPP, technical and economic studies of the nuclear fuel cycle. The problem of further studies are formulated and discussed

[en] The collection includes abstracts of reports of scientific and technical conference Thermophysics-2012 which has taken place on October 24-26, 2012 in Obninsk. In abstracts the following questions are considered: experimental and calculating and theoretical studies of thermal hydraulics of liquid-metal cooled fast reactors to justify their characteristics and safety; physico-chemical processes in the systems with liquid-metal coolants (LMC); physico-chemical characteristics and thermophysical properties of LMC; development of models, computational methods and calculational codes for simulating processes of of hydrodynamics, heat and mass transfer, including impurities mass transfer in the systems with LMC; methods and means for control of composition and condition of LMC in fast reactor circuits on impurities and purification from them; apparatuses, equipment and technological processes at the work with LMC taking into account the ecology, including fast reactors decommissioning; measuring techniques, sensors and devices for experimental studies of heat and mass transfer in the systems with LMC

[en] The information is given on characteristics and possibilities of experimental thermophysical facilities of SSC RF - IPPE, which is used for research and applied investigations in the field of hydrodynamics, heat transfer, physical chemistry and technology of coolants. These facilities also can be used for justification of parameters and safety of nuclear power installations with coolants of different types and purposes (water, gases, alkali and heavy metals), for testing sensors, devices, apparatus and reactor equipment under conditions near to the reactor ones

[en] The fast reactor core space kinetics model with moderating multiplying neutron reflector is formulated. The several particular cases of this model, which permit to calculate the space-time characteristics of the neutron flux are considered. The parameters of the reactor kinetics model were calculated using the Monte Carlo method by means of the MMKFK computer program. The mathematical simulation of fast processes with impulse neutron generation in the reactor system with multiplying reflector is made in two- and multizone approximations. The neutron impulse parameters calculated are compared with analogous characteristics, which were calculated using the model of coupled reactors. 19 refs.; 8 figs.; 4 tabs

[en] The results of the thr Nuclear Reactors Physics Institute for the year 2013 are discussed. The main areas of new generation research units with the fast reactor BN-1200 with sodium coolant are presented. Development of materials, safety studies, neutron-physical and thermal-hydraulic characteristics of the power unit BREST-OD-300 of the new generation is an important direction in the activities of the Institute. Issues of increasing the effectiveness of existing and future nuclear power plants are solved, study of nuclear and radiation safety at the NPP Beloyarsk and Bilibino is considered. The recommendations on the physics and technology of space NPU are elaborated. The concepts for innovative projects - WWER-SCP, molten salt reactor; high-temperature sodium technologies are presented. The Institute focuses on innovative exchange, best practice and knowledge preservation

[en] In the book there are reports concerning the status and problems of investigations in the field of hydrodynamics, heat transfer and safety in justification of fast reactors with different liquid metal coolants (LMC); thermophysical properties of LMC and processes in them; investigations of mass transfer and development of sodium and heavy LMC technologies; development of measuring techniques, sensors, devices, equipment and processes for operation with LMC; development and verification of thermohydraulic codes and numerical simulation of thermohydraulic processes; research in justification of new innovation reactor technologies (molten-salt, high-temperature sodium, thermonuclear, space nuclear power reactors)

No abstract available

[en] The review of theoretical approaches to the neutron kinetics analysis in the coupled-type reactor systems is presented. The methods based on application of the integral parameters and integral equation of the neutrons transfer with the excluded energy and angular variables are consequently elucidated. Special attention is paid to the particular reactor facility of the reactor-subcritical assembly type