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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.


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.


Ilyakhinskii I.A.,Afrikantov Experimental Design Bureau of Mechanical Engineering | Bugreev A.V.,Afrikantov Experimental Design Bureau of Mechanical Engineering | Ilyakhinskii A.V.,Russian Academy of Sciences | Rodyushkin V.M.,Russian Academy of Sciences
Atomic Energy | Year: 2016

The relation between the structure and acoustic parameters for silicon carbide/graphite composite is shown. The effect of the composition and density of the composite and the size of the structural component of silicon on the propagation velocity and damping of the longitudinal ultrasonic wave at frequency 1, 4, and 5 MHz is determined. The results obtained can serve as a basis for testing the quality of the parts in tribocoupling units. © 2016 Springer Science+Business Media New York


Zverev D.L.,Afrikantov Experimental Design Bureau of Mechanical Engineering | Pakhomov A.N.,Afrikantov Experimental Design Bureau of Mechanical Engineering | Polunichev V.I.,Afrikantov Experimental Design Bureau of Mechanical Engineering | Veshnyakov K.B.,Afrikantov Experimental Design Bureau of Mechanical Engineering | Kabin S.V.,Afrikantov Experimental Design Bureau of Mechanical Engineering
Atomic Energy | Year: 2013

The main technical solutions incorporated in the design of the RITM-200 reactor for a new-generation nuclear icebreaker are presented. Its special feature is an extended service life compared with icebreakers which are currently in service. To secure this quality, the main damaging factors revealed during operation and influencing service life are examined. The following are presented: the results of a systems analysis of the design implementation of the equipment and systems and their heat-engineering characteristics as well as the water-chemistry and gas regime of the first-loop coolant for optimizing the reactor's operating conditions and securing a high safety level and acceptable technical economic indicators. © 2013 Springer Science+Business Media New York.


Sosnin M.A.,Afrikantov Experimental Design Bureau of Mechanical Engineering | Belin A.V.,Afrikantov Experimental Design Bureau of Mechanical Engineering | Sukharev Yu.P.,Afrikantov Experimental Design Bureau of Mechanical Engineering
Atomic Energy | Year: 2013

The experience gained in developing and putting into use the software and hardware in the informationmeasurement and intellectual systems of the hot critical stand at OKBM Afrikantov is described. The structure and composition of the measuring equipment as well as specialized software are described. The problems that can be solved using this system are described. The directions for further development of the informationmeasurement complex of the critical stand are determined. © 2013 Springer Science+Business Media New York. Reference:.


Barinov A.A.,Novgorod State University | Dmitriev S.M.,Novgorod State University | Khrobostov A.E.,Novgorod State University | Samoilov O.B.,Afrikantov Experimental Design Bureau of Mechanical Engineering
Atomic Energy | Year: 2016

Methods of validating the thermomechanical reliability of the core of water-moderated and -cooled reactors that are used in reactor design practice are reviewed. The factors determining the thermomechanical reliability of the core and the particulars of the calculation of its criteria in using deterministic and statistical methods are examined. The advantages and disadvantages of different statistical approaches to taking account of the computational uncertainties are indicated. The particularities of using different methods for validating the thermomechanical reliability and their role in the reactor design process are colligated. © 2016 Springer Science+Business Media New York


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.

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