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Dive into the research topics where V. V. Makarov is active.

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Featured researches published by V. V. Makarov.


Russian Engineering Research | 2012

Wear dynamics of fragments in the lower part of a fuel assembly with unattached rods

Yu. N. Drozdov; E. P. Osipova; V. N. Puchkov; V. V. Makarov; A. V. Afanas’ev; I. V. Matvienko

The dynamic characteristics and wear of unattached fuel rods in the lower supporting lattice are investigated. The vibrational eigenfrequencies and dynamic rigidity of the fuel rods in different configurations are determined. The vibrational wear at contact between the fuel rods and the spacing elements is studied.


Russian Engineering Research | 2012

Seismic tests of fuel assemblies

Yu. N. Drozdov; M. A. Tananov; E. P. Osipova; T. I. Nazarova; V. V. Makarov; A. V. Afanas’ev; V. V. Abramov

Seismic tests of full-scale mockups of fuel assemblies from the VVER-1000 reactor permit the determination of the transfer characteristics between the stimulus (acceleration of the supports) and the response of the fuel assemblies. No resonant responses of the fuel assemblies to seismic loads are observed.


Russian Engineering Research | 2012

Pile dynamics in coolant flux

Yu. N. Drozdov; M. A. Tananov; E. P. Osipova; V. V. Makarov; A. V. Afanas’ev; I. V. Matvienko

Intrinsic and forced vibrations of a reactor pile in standing water and in coolant flux are investigated. The eigenfrequencies and damping factors of the intrinsic vibrations and the parameters of forced vibrations of the fuel rods are determined. The influence of the auxiliary spacers on fuel-rod vibrations is discussed.


Journal of Machinery Manufacture and Reliability | 2012

Friction of fuel-rod casings and spacers in the pile of VVER reactors

Yu. N. Drozdov; V. V. Makarov; A. V. Afanas’ev; V. N. Puchkov; E. P. Osipova

Frictional tests of fuel-rod casings and spacing cells are conducted in various conditions. The frictional coefficients are determined for different loads. The influence of factors such as vibration, the contact load, the sample speed, the atmosphere, and the temperature is considered.


Journal of Machinery Manufacture and Reliability | 2012

Dynamic characteristics of the mockup of the fuel assembly in coolant flow

Yu. N. Drozdov; V. V. Makarov; A. V. Afanas’ev; I. V. Matvienko; E. P. Osipova; T. I. Nazarova

During exploitation, fuel assemblies are subjected to vibration loads caused by vibrations of intracase devices, pressure pulsations, acoustic waves, and turbulent flow of the coolant. Vibrations of the fuel assembly can be the cause of damage to its details, particularly, fuel elements and spacer lattices, because of their wear. Therefore, one requirement for the project of the fuel assembly of AES-2006 reactor installations is vibration strength and resistance throughout the service life of the fuel assembly in the reactor. The vibration strength and fuel assembly strength are substantiated by computational-experimental methods using the results of the experimental modal analysis of the full-scale mockup for verification.


Journal of Machinery Manufacture and Reliability | 2012

Seismic stability tests for models of fuel assemblies

Yu. N. Drozdov; V. V. Makarov; I. V. Matvienko; A. V. Afanasiev; V. V. Abramov; T. I. Nazarova; V. N. Puchkov; E. P. Osipova

A procedure and results of seismic stability tests of full-scale models for fuel assemblies of the water-water energetic reactor VVER-1000 are presented. In the course of tests, kinematic loading of fuel assembly supports has been carried out in accordance with accelerograms of the motion of fuel assembly supports during an earthquake, which was obtained by computational methods. Based on the results of measurements of the vibrational response of fuel assemblies, transfer characteristics between the response of fuel assemblies and applied action (support acceleration) are determined. The lack of a resonant response of fuel assemblies at seismic loads is found.


Russian Engineering Research | 2011

Resistance to fretting corrosion of fuel rods in a VVER-440 water-moderated reactor in contact with spacers

Yu. N. Drozdov; E. P. Osipova; V. N. Puchkov; V. V. Makarov; A. V. Afanas’ev; A. V. Grishakov

The wear resistance of fuel assemblies in the VVER-440 water-moderated reactor is investigated, with small fuel-rod diameter. The experimental apparatus, the model of the fuel rods, and the similarity conditions are described; the possibility of applying the experimental results to regular fuel rods is noted.


Russian Engineering Research | 2011

Drop strength of the fuel assembly in a nuclear power plant

Yu. N. Drozdov; V. N. Puchkov; E. P. Osipova; T. I. Nazarova; V. V. Makarov; V. V. Abramov; A. V. Afanas’ev

The possible structural deformation of the fuel assembly in a nuclear power plant when dropped during transportation or other operations is considered. The consequences of such damage are studied.


Russian Engineering Research | 2011

Friction and wear of fuel assemblies in water-moderated reactors

Yu. N. Drozdov; V. V. Makarov; A. V. Afanas’ev; I. V. Matvienko; V. N. Puchkov

Static and dynamic processes that involve frictional forces are experimentally studied. The frictional forces affect the stress of the fuel assembly in all stages of the life cycle.


Russian Engineering Research | 2011

Friction of fuel-rod casings and spacing cells in the pile of a water-cooled, water-moderated reactor

Yu. N. Drozdov; E. P. Osipova; T. I. Nazarova; V. V. Makarov; V. V. Abramov; A. V. Afanas’ev; M. V. Puchkov

Fuel-rod casings and spacing cells are subjected to frictional tests, with variation in the technological and operational factors.

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Yu. N. Drozdov

Russian Academy of Sciences

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V. N. Puchkov

Russian Academy of Sciences

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E. P. Osipova

Russian Academy of Sciences

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T. I. Nazarova

Russian Academy of Sciences

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A. V. Beznosov

Nizhny Novgorod State Technical University

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M. A. Antonenkov

Nizhny Novgorod State Technical University

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M. A. Tananov

Russian Academy of Sciences

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