42 Result(s)

Article

Experimental Investigations of the Onset and Growth of a Heat-Transfer Crisis in a Full-Scale Cross-Sectional Model FA of the RITM-200 Reactor for Small NPP

The results of experimental investigations of a heat-transfer crisis and post-crisis heat-exchange across the full-cross-section of an electrically heated model FA of a cassette-type core are reported. The tes...

S. M. Dmitriev, O. B. Samoilov, A. V. Kupriyanov, A. B. Osin in Atomic Energy (2022)

Article

High-Temperature Behavior of Irradiated Dispersion Fuel Rods with 42KhNM-Alloy Cladding

Thermal testing of shortened fuel rods with 42KhNM chromium–nickel alloy cladding, pre-irradiated in the MIR reactor to fission product content 0.9 g/cm³, was conducted at SSC RIAR. The mechanism of fuel rod depr...

G. V. Kulakov, Yu. V. Konovalov, A. V. Vatulin, A. A. Kosaurov… in Atomic Energy (2021)

Article

Methodological Issues and Results of Experimental and Computational Studies of Critical Heat Flows in RITM-200 Reactor Fuel Assemblies for Small NPP

Experimental studies of critical and post-crisis heat transfer, performed on electrically heated models of different modifications of cassette-core fuel assemblies, that can be used to justify the heat-enginee...

A. A. Zakharychev, G. Sh. Iksanova, A. V. Kupriyanov, A. B. Osin… in Atomic Energy (2021)

Article

Tests of a Two-Stage Core at the KV-1 Test Facility: Physical Aspects and Results

The physical aspects and main results of reactor tests of a two-stage core consisting of fresh fuel assemblies and a significant number of fuel assemblies from the previous core, which are left for re-burning ...

V. S. Ustinov, A. N. Volkov, O. B. Samoilov, O. A. Morozov… in Atomic Energy (2021)

Article

OKBM Afrikantov Research and Testing Complex: From Creation to the Present Day

Testing and experimental substantiation are a significant and integral part at all phases of the life cycle of reactor equipment. The Research and Testing Complex (RTC) operates at OKBM Afrikantov to ensure th...

S. V. Babushkin, A. M. Bakhmet’ev, B. A. Vasil’ev, D. L. Zverev… in Atomic Energy (2020)

Article

Fuel for VVER and PWR: Current Status and Prospects

The Rosatom State Corporation activity in the nuclear fuel market requires the development of new designs and modifications meeting the current requirements of safety and operational reliability. The history o...

D. L. Zverev, O. B. Samoilov, A. I. Romanov, V. A. Panov, A. A. Fal’kov… in Atomic Energy (2020)

Article

Efficiency Studies of Heat-Transfer Intensifier Grids in TVSA-T Model Fuel Assemblies

The results of studies of the intensification of heat-and-mass transfer and mixing of coolant are presented. Justification is given for the design, number, and arrangement of intermediate intensifier plate gri...

O. B. Samoilov, D. L. Shipov, A. V. Kupriyanov, E. V. Sholin… in Atomic Energy (2020)

Article

Concept Selection and Neutronic Characteristics of Nuclear Icebreaker Cores

The developmental history of the series-produced core for nuclear icebreakers and its conceptual and structural designs and the computational-methodological base of the physical design are presented. The funda...

E. A. Dvoinishnikov, V. I. Makarov, A. G. Promokhov, O. B. Samoilov… in Atomic Energy (2019)

Article

Hydrodynamic Features of the Flow Downstream from the Mixing Spacer Grid in a Kvadrat Fuel Assembly in PWRs

The experimental investigation of local hydrodynamic characteristics of the coolant flow downstream of a mixing spacer grid (MSG) in characteristic regions of a Kvadrat fuel assembly in PWRs was performed. The...

O. B. Samoilov, A. S. Noskov, D. L. Shipov, S. M. Dmitriev… in Thermal Engineering (2019)

Article

Investigation of Thermal and Epithermal Neutron Flux Distributions in Universal Nuclear Icebreaker Fuel Assemblies

The results of experimental investigations of the spatial and energy distributions of the thermal and epithermal neutrons in a cassette fuel assembly, similar in design to that developed for the RITM-200 react...

O. B. Samoilov, V. I. Alekseev, V. Yu. Galitskikh, A. V. Belin… in Atomic Energy (2017)

Article

Method of Routine Monitoring of Fuel-Element Cladding Tightness During Icebreaker Core Removal

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 assemblie...

M. M. Kashka, A. N. Pastukhov, O. B. Samoilov, B. I. Kolomiets… in Atomic Energy (2017)

Article

Methods of Thermomechanical Reliability Validation of Thermal Water-Moderated and Water-Cooled Reactor Cores

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 re...

A. A. Barinov, S. M. Dmitriev, A. E. Khrobostov, O. B. Samoilov in Atomic Energy (2016)

Article

Combined numerical and experimental investigations of local hydrodynamics and coolant flow mass transfer in Kvadrat-type fuel assemblies of PWR reactors with mixing grids

Results of research works on studying local hydrodynamics and mass transfer for coolant flow in the characteristic zones of PWR reactor fuel assemblies in case of using belts of mixing spacer grids are present...

S. M. Dmitriev, O. B. Samoilov, A. E. Khrobostov, A. V. Varentsov… in Thermal Engineering (2014)

Article

Experimental Investigation of the Heat-Engineering Characteristics of TVSA Fuel Assemblies With Mixing Lattices

The results of experimental studies of the heat-engineering characteristics and critical heat transfer in 19-rod, electrically heated, models of the alternative heat assemblies TVSA with mixing lattices with d...

O. B. Samoilov, A. V. Kupriyanov, A. A. Fal’kov, D. L. Shipov… in Atomic Energy (2014)

Article

Scientific and Technical Communications

O. B. Samoilov, V. I. Alekseev, V. Yu. Galitskikh in Atomic Energy (2014)

Article

VVÉR-1000 TVSA fuel assembly: Direction of development and operating results

The structural and main characteristics of an alternative fuel assembly TVSA VVÉR-1000 are examined. The results of experimental validation, reactor tests, and operation are presented. The main directions of s...

V. B. Kaidalov, D. G. Preobrazhenskii, A. I. Romanov, O. B. Samoilov… in Atomic Energy (2007)

Article

VBÉR-300 reactor system and power-generating units for regional nuclear power production

The basic design solutions and characteristics of the VBÉR-300 reactor system for the power-generating units of 150–300 MW(e) nuclear power plants and regional nuclear heat-and-electricity plants are described...

V. I. Kostin, V. V. Petrunin, O. B. Samoilov, A. V. Kurachenkov in Atomic Energy (2007)

Article

Reactor systems developed by OKBM in the development of the atomic energy industry, nuclear power, and the nuclear-powered fleet in Russia

The various types of reactor systems which OKBM designed for different purposes over the 60 years of its existence are reviewed: commercial uranium-graphite and heavy-water reactors, reactors and steam-generat...

V. I. Kostin, F. M. Mitenkov, V. V. Petrunin, I. V. Serov, Yu. K. Panov… in Atomic Energy (2007)

Article

Experemental investigations of transcritical heat transfer on an electrically heated model of a fuel assembly

The purpose of this work was to obtain experimental information on the temperature state of fuel elements in the transcritical region and to develop methods for calculating the heat-emission coefficient. The f...

O. B. Samoilov, A. V. Kupriyanov, I. A. Nagaev, S. M. Dmitriev in Atomic Energy (2000)