22 Result(s)

Article

Effects of reactor irradiation on cyclic strength in zirconium alloys

V. M. Filatov, V. I. Barsanov, S. V. Evropin, S. A. Averin… in Soviet Atomic Energy (1983)

Article

Creation and Development of Computational Methods for Estimating the Strength of Equipment and Pipes Used in Radiochemical Production Processes at the Industrial Association Mayak

The Industrial Association Mayak chose for computations to substantiate the safety of equipment used in radiochemical production processes domestic computer codes, which are as good as the foreign codes but al...

S. I. Rovnyi, A. I. Berezyuk, M. V. Pronichev, S. E. Serov, S. V. Evropin… in Atomic Energy (2001)

Article

Management of the Service Life of a Nuclear Power Plant

Nuclear power plant service life management is the modern technology for providing efficient operation of nuclear power plants at an established safety level irrespective of the initial set service life. Conse...

S. E. Bugaenko, A. I. Arzhaev, S. V. Evropin, V. A. Savchenko in Atomic Energy (2002)

Article

Validation of lifetime extension of power-generating units with RBMK reactors

A list of measures for extending the lifetime of power-generating units with RBMK reactors is presented. The normative approaches and criteria are indicated, an assessment of the technical possibility of lifet...

B. A. Gabaraev, Yu. M. Cherkashov, A. A. Petrov, S. V. Evropin… in Atomic Energy (2006)

Article

Control of the safe operating period of equipment and pipelines in reactor facilities which are in operation or under construction

The basic assumptions for ensuring safe operation of the components of nuclear facilities, based on controlling service lifetime characteristics, are presented. It is shown up for the Du300 RBMK-1000 pipes, wh...

S. V. Evropin, B. P. Strelkov in Atomic Energy (2007)

Article

Low-cycle deformation of the structures in a nuclear power plant and methods for calculating them

It is proposed that the fatigue strength of structures in nuclear power plants with a quite long service life be analyzed in two stages: first, the type and location of the process and the effect of basic fact...

N. A. Makhutov, M. M. Gadenin, O. F. Chernyavskii, A. O. Chernyavskii… in Atomic Energy (2009)

Article

Practical aspects of the development of a code of rules for assuring the serviceability of the elements of nuclear power facilities

The 2009 edition of the Federal Law On Technical Regulation, indicating the particulars of technical regulation, makes it possible to implement more fully the provisions of the Federal Law On the Use of Atomic...

S. V. Evropin in Atomic Energy (2011)

Article

Development of software means and normative documentation on the flow-accelerated corrosion of pipelines of nuclear power plants

Software tools (ST) and normative documentation (ND) on the flow-accelerated corrosion (FAC) of pipelines of foreign and domestic nuclear power plants are analyzed.

V. I. Baranenko, A. A. Prosvirnov, S. V. Evropin, A. A. Aref’ev… in Thermal Engineering (2012)

Article

Diagram of fatigue limit states with high asymmetry

Hardening of structural elements and plasticity loss are observed for reactor elements which operate for a long time. In some cases, this results in a change of the asymmetry of multi-cycle loading of structur...

S. V. Evropin, V. M. Filatov in Atomic Energy (2013)

Article

Service-life analysis of nuclear reactor elements under high-frequency random loading

Service life extension for working equipment and nominal service life extension (to 60 or more years) for nuclear reactors under construction make it even more urgent to evaluate the effect of the high-frequen...

S. V. Evropin, V. M. Filatov in Atomic Energy (2013)

Article

High-Temperature Heat-Treatment of the Welded Joints of Du300 Austenitic Pipelines at 900°C

The high-temperature heat treatment of the welded joints of Du300 austenitic pipelines on straight sections and lead-aways, welded joints of Du300 pipelines to pipe connections for equipment and fittings and w...

A. N. Romanov, S. V. Evropin, A. G. Derzhavin, A. V. Tutukin… in Atomic Energy (2014)

Article

Specific features of elastoplastic deformation and fracture of steels at complicated thermomechanical stress paths

Regularities of cyclic elastoplastic deformation and fracture are studied on the basis of the damage accumulation parameter at increased and high temperatures considering the effect of cyclic changes in the ma...

N. A. Makhutov, M. M. Gadenin, S. V. Evropin, O. F. Chernyavskii… in Inorganic Materials (2014)

Article

Stress–Strain Kinetics in Calculations of High-Temperature Strength and Longevity of Reactor Structures

The plastic properties of materials must be used more fully as working temperatures and temperature gradients increase. The results of tests performed on refractory chromium-nickel alloys with co...

Yu. G. Dragunov, S. V. Evropin, M. M. Gadenin, N. A. Makhutov… in Atomic Energy (2016)

Article

Fourth International Scientific and Technical Conference on Innovative Projects and Technologies of Nuclear Power (MNTK NIKIET-2016)

Yu. G. Dragunov, B. A. Gabaraev, A. V. Dzhalavyan, A. V. Lopatkin… in Atomic Energy (2017)

Article

Numerical Study of the Dynamic Strength of RBMK-1000 Stack with Fuel Channel Rupture

The strength of the stack in a RBMK-1000 reactor facility with a rupture of a fuel channel is studied. Local models of unirradiated and irradiated stack, comprising an assembly consisting of 81 columns, and a ...

A. A. Ryabov, V. I. Romanov, S. S. Kukanov, K. V. Tsiberev, S. V. Evropin… in Atomic Energy (2018)

Article

Experimental Validation of the Earthquake Resistance of a Full-Scale Model of RBMK-1000 Graphite Stack with Post-Repair Characteristics

In providing justification for the operational safety of RBMK-1000 power units with graphite stack distortion, earthquake resistance tests were performed on a full-scale model of RBMK graphite stack under seis...

S. V. Evropin, I. M. Baranov, V. S. Novikov, A. V. Malyshev… in Atomic Energy (2018)

Article

Computational and Experimental Validation of the Serviceability of RBMK Core Elements Under Graphite Stack Distortion Conditions

Computational and experimental validation of the serviceability of zirconium channels in the reactor core according to strength criteria was conducted in order to ensure safe operation of the RBMK reactor faci...

S. V. Evropin, A. P. Rakhmanov, E. V. Churakova, I. M. Baranov, S. M. Usov in Atomic Energy (2018)

Article

Development of New Construction Materials for Innovative Reactor Installation Designs

Different stages of the development of new construction materials at NIKIET for innovative designs of reactor installations are analyzed. Justification is given for the use of large-sized intermediate products...

A. B. Korostelev, S. V. Evropin, A. G. Derzhavin, I. V. Vershinin… in Atomic Energy (2021)

Article

Form Change and Cracking of RBMK-1000 Graphite Stack Blocks Under Restrained Deformation

The results of modeling the form change and cracking of graphite blocks under exposure to heat and radiation at the stage of their secondary swelling within the scope of scientific and technical support for th...

A. V. Slobodchikov, S. V. Evropin, A. P. Rakhmanov, A. N. Yurin… in Atomic Energy (2021)

Article

Influence of the Edge Effect in Pipeline–Nozzle Welds During “Leak Before Break” Validation

An appraisal was made of the influence of the edge effect, which is induced when branch-pipes are welded to the nozzles of a multiple forced circulation loop of power units with RBMK-1000, on the stress-strain...

S. V. Evropin, A. N. Yurin, A. A. Chalyi in Atomic Energy (2022)