Afrikantov Experimental Design Bureau of Mechanical Engineering

Nizhniy Novgorod, Russia

Afrikantov Experimental Design Bureau of Mechanical Engineering

Nizhniy Novgorod, Russia
SEARCH FILTERS
Time filter
Source Type

Kashka M.M.,Atomflot State Enterprise | Pastukhov A.N.,Atomflot State Enterprise | Samoilov O.B.,Afrikantov Experimental Design Bureau of Mechanical Engineering | Kolomiets B.I.,Afrikantov Experimental Design Bureau of Mechanical Engineering | Dovbush S.P.,Afrikantov Experimental Design Bureau of Mechanical Engineering
Atomic Energy | Year: 2017

The tightness of fuel-element cladding is monitored in order to identify fuel assemblies where depressurization has occurred in the course of operation. The condition of the fuel elements in the fuel assemblies of icebreaker cores is determined during refueling of the reactor immediately after a spent assembly is loaded into a dry cell of the storage facility cover in the floating technical service facility by extracting an air sample from its active part into a standard radiation-monitoring measurement system. This method of monitoring cladding tightness does not disrupt the refueling of icebreaker reactors or the refueling cycle time and allows routine evaluation of the condition of the core for representative extraction of spent fuel assemblies for materials studies. © 2017 Springer Science+Business Media New York


Beznosov A.V.,Novgorod State University | Chernysh A.S.,Novgorod State University | Zudin A.D.,Novgorod State University | Bokova T.A.,Novgorod State University | Novinskii E.G.,Afrikantov Experimental Design Bureau of Mechanical Engineering
Atomic Energy | Year: 2017

Heat removal during transient processes in nuclear power installations and bench loops cooled by lead and lead-bismuth coolant is studied. It is shown that low-pressure heat-exchange equipment is effective. The studies were conducted in a non-isothermal loop with circulating of lead coolant at 450–500°C, average speed in the narrow section of the gap in longitudinal flow over the heat-exchange surface 0.1–1.05 m/sec, Peclet number 300–3300, and the oxygen thermodynamic activity in lead 1–10–3. The processes occurring in a non-isothermal liquid-metal loop with an experimental heat-exchange section model the dependence of the heat-exchange characteristics on impurity mass transfer in the loop. © 2017 Springer Science+Business Media New York


Sergeev D.A.,RAS Institute of Applied Physics | Kandaurov A.A.,RAS Institute of Applied Physics | Troitskaya Y.I.,RAS Institute of Applied Physics | Pakholkov V.V.,Afrikantov Experimental Design Bureau of Mechanical Engineering | And 2 more authors.
Instruments and Experimental Techniques | Year: 2017

The use of visualization techniques in the research on thermohydraulic processes using large-scale models of nuclear power plants is discussed. In particular, the original particle-image velocimetry (PIV) measurement system at the TISEI test bench was presented, which is a model of a proposed fast-neutron reactor. Illumination and video-filming systems with the simultaneous use of several lasers and camcorders, as well as image-processing algorithms that make it possible to carry out field measurements with high precision in a complex configuration of the reactor model, reflections and distortions of the laser knife section, and shadowing by obstacles are described. The developed methodology of conversion of the image coordinates and velocity field into the reference system of the reactor model using a virtual 3D simulation made it possible to significantly simplify the experiments. © 2017, Pleiades Publishing, Inc.


Khlybov A.A.,Nizhny Novgorod State Technical University | Pichkov S.N.,Afrikantov Experimental Design Bureau of Mechanical Engineering | Shishulin D.N.,Afrikantov Experimental Design Bureau of Mechanical Engineering
Russian Journal of Nondestructive Testing | Year: 2016

The results of the acoustic monitoring of the damage that accumulated in an austenitic steel sample tube during thermal pulsation are presented. © 2016, Pleiades Publishing, Ltd.


Uglov A.L.,Scientific Research Center for Testing and Evaluating Technical Systems | Khlybov A.A.,Nizhny Novgorod State Technical University | Pichkov S.N.,Afrikantov Experimental Design Bureau of Mechanical Engineering | Shishulin D.N.,Afrikantov Experimental Design Bureau of Mechanical Engineering
Russian Journal of Nondestructive Testing | Year: 2017

Results of testing a technique for evaluating damages on the inner surface of austenitic-steel pipe samples by the spectral acoustic method with the use of an acoustic phased antenna array are provided. It is shown that accumulated damages can be revealed in the surface layer at a level of 10% of exhausting the resource of an article made of 12Kh18N10T steel. © 2017, Pleiades Publishing, Ltd.


Vasil'ev A.Y.,RAS Institute of Continuous Media Mechanics | Kolesnichenko I.V.,RAS Institute of Continuous Media Mechanics | Mamykin A.D.,RAS Institute of Continuous Media Mechanics | Frick P.G.,RAS Institute of Continuous Media Mechanics | And 3 more authors.
Technical Physics | Year: 2015

Turbulent free convection of liquid sodium in a straight thermally insulated tube with a length equal to 20 diameters and with end heat exchangers ensuring a fixed temperature drop is investigated experimentally. The experiments are performed for a fixed Rayleigh number Ra = 2.4 × 106 and various angles of inclination of the tube relative to the vertical. A strong dependence of the power transferred along the tube on the angle of inclination is revealed: the Nusselt number in the angular range under investigation changes by an order of magnitude with a maximum at the angle of 65° with the vertical. The characteristics of large-scale circulation and turbulent temperature pulsations show that convective heat transfer is mainly determined by the velocity of large-scale circulation of sodium. Turbulent pulsations are maximal for small angles of inclination (α = 20°–30°) and reduce the heat flux along the channel, although in the limit of small angles (vertical tube), there is no large-scale circulation, and the convective heat flux, which is an order of magnitude larger than the molecular heat flux, is ensured only by small scale (turbulent) flow. © 2015, Pleiades Publishing, Ltd.


Kodochigov N.G.,Afrikantov Experimental Design Bureau of Mechanical Engineering | Sorokin S.E.,Afrikantov Experimental Design Bureau of Mechanical Engineering | Sukharev Y.P.,Afrikantov Experimental Design Bureau of Mechanical Engineering
Atomic Energy | Year: 2015

This article is devoted to the pressing issue of achieving fuel security by realizing in fast reactors the best breeding of new fissile materials from the initial isotopes and using the accumulated fissile isotopes in the same reactor irrespective of the rates at which the spent nuclear fuel is reprocessed in the external fuel cycle. Two fast-reactor concepts based on the same principle are validated by computational means. In the first one, the fissile isotope is replenished with the breeding isotope by moving the neutron flux or energy release along the initially formed composition, consisting of a seed zone and a breeding zone (traveling wave of fission concept); in the second one, the motion of the neutron flux is replaced by the movement of the fuel composition, comprised of fissile and breeding materials (standing wave of fission concept). © 2015, Springer Science+Business Media New York.


Knyazev A.V.,Novgorod State University | Chernorukov N.G.,Novgorod State University | Ladenkov I.V.,Novgorod State University | Ershova A.V.,Afrikantov Experimental Design Bureau of Mechanical Engineering
Russian Journal of Inorganic Chemistry | Year: 2011

Compounds formed in the M 2 I O-Cr 2O 3-TiO 2. system were synthesized by solid-state reactions. These compounds crystallize in hollandite- and spinel-type structures. The features of themal decomposition of the compounds with the compositions M 2 I Cr 2Ti 6O 16(M I = Na, K, Cs) and LiCrTiO 4 were revealed, and their thermal expansion coefficients were determined with the use of high-temperature X-ray diffraction analysis. © 2011 Pleiades Publishing, Ltd.


Patent
Open Joint Stock Company Tvel, Open Joint Stock Company Novosibirsk Chemical Concentrates Plant and Afrikantov Experimental Design Bureau of Mechanical Engineering | Date: 2015-08-26

The present disclosure provides for designs of fuel assemblies and may be used in pressurized water reactors. In some embodiments, a nuclear reactor fuel assembly may comprise a bundle of fuel rods, guide channels, two nozzles, one of which has a bearing plate with openings, elements for the detachable connection of the nozzles to the guide channels, a detachable connection locking device and a locking device fasteners, the elements for the detachable connection of the nozzles to the guide channels have a cross-section size greater than the size of the openings in the nozzle bearing plate. The present disclosure may provide greater ease in loading and unloading, reduce the time required for the mounting and removal of the nozzles during manufacture of the fuel assembly, and reduce the length of the reactor refueling process.


Patent
Open Joint Stock Company Tvel, Open Joint Stock Company Novosibirsk Chemical Concentrates Plant and Afrikantov Experimental Design Bureau of Mechanical Engineering | Date: 2013-10-14

The present disclosure provides for designs of fuel assemblies and may be used in pressurized water reactors. In some embodiments, a nuclear reactor fuel assembly may comprise a bundle of fuel rods, guide channels, two nozzles, one of which has a bearing plate with openings, elements for the detachable connection of the nozzles to the guide channels, a detachable connection locking device and a locking device fasteners, the elements for the detachable connection of the nozzles to the guide channels have a cross-section size greater than the size of the openings in the nozzle bearing plate. The present disclosure may provide greater ease in loading and unloading, reduce the time required for the mounting and removal of the nozzles during manufacture of the fuel assembly, and reduce the length of the reactor refueling process.

Loading Afrikantov Experimental Design Bureau of Mechanical Engineering collaborators
Loading Afrikantov Experimental Design Bureau of Mechanical Engineering collaborators