All articles by "Solonin V.I."
Metal Liner Reliability Assessment for BREST-OD-300 Reactor Vessel Accounting for Brittle Fracture and Leaks
| Authors: Solonin V.I., Terekhin A.N., Shiverskiy E.A. | Published: 17.10.2019 |
| Published in issue: #5(128)/2019 | |
| DOI: | |
| Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
| Keywords: multi-layer metal-concrete vessel, metal liner, vessel reliability, probabilistic mechanical model-ing, brittle fracture and leak | |
Mean Flow and Mass Exchange Structure in Dense Bundle of Fuel Rods of Gas-Cooled Reactor
| Authors: Dunaytsev A.A., Solonin V.I. | Published: 12.04.2017 |
| Published in issue: #2(113)/2017 | |
| DOI: | |
| Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
| Keywords: hydrodynamics, mass transfer, rod bundle, cell, channel, numerical simulation, computational fluid dynamics, fuel rod element spacing, local heating, heat transfer, heat exchange intensification, speed, temperature, friction loss, static pressure | |
Plastic deformation of the neutron absorbing rod containing a swelling powder core
| Authors: Alexandrov D.A., Solonin V.I., Chernyshev V.M. | Published: 23.06.2015 |
| Published in issue: #1(26)/1997 | |
| DOI: | |
| Category: Simulation of Processes | |
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Structure of Turbulent Flow in the Pin Bundles of the BREST-OD-300
| Authors: Fomichev D.V., Solonin V.I. | Published: 19.06.2015 |
| Published in issue: #3(102)/2015 | |
| DOI: | |
| Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
| Keywords: wire-spaces fuel assembly, turbulent flow structure, computational fluid dynamics | |
Pin Bundles Hydraulic Characteristics of the BREST-OD-300 Wire-Spaced Fuel Subassemblies
| Authors: Fomichev D.V., Solonin V.I. | Published: 15.04.2015 |
| Published in issue: #2(101)/2015 | |
| DOI: | |
| Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
| Keywords: experimental nuclear reactor, wire-spaced fuel subassembly, computational fluid dynamics | |
Fluid Flow and Mass Transfer in Finned Fuel Rod Assemblies of Nuclear Reactor BREST-OD-300
| Authors: Getya S.I., Krapivtsev V.G. , Markov P.V., Solonin V.I. | Published: 09.02.2015 |
| Published in issue: #1(100)/2015 | |
| DOI: | |
| Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
| Keywords: nuclear reactor BREST-OD-300, models of fuel rod assemblies, spacing of fuel rods by spiral fins, aerodynamic experiments, computational fluid dynamics, method of heat wake | |
Use of Individual Throttle Devices for Hydraulic Profiling of the Coolant Flux in Reactor Model
| Authors: Solonin V.I., Satin A.A., Getya S.I., Kobzev P.V. | Published: 02.10.2014 |
| Published in issue: #5(98)/2014 | |
| DOI: | |
| Category: Power-generating and Transport Machine Building | |
| Keywords: discharge header, throttling, aerodynamic experiment, computational fluid dynamics | |
Damping a Bunch of Heat Releasing Elements of Heat Releasing Assemblies of Water-Cooled Reactors in Flow of Heat Carrier
| Authors: Solonin V.I., Sorokin F.D., Perevezentsev V.V. | Published: 03.02.2014 |
| Published in issue: #3(76)/2009 | |
| DOI: | |
| Category: Power-generating and Transport Machine Building | |
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Damping Oscillations of Cluster of Fuel Elements of Case Heat-Generating Assemblies for Water-Cooled Reactors
| Authors: Solonin V.I., Sorokin F.D., Perevezentsev V.V. | Published: 17.01.2014 |
| Published in issue: #3(72)/2008 | |
| DOI: | |
| Category: Simulation of Processes | |
| Keywords: | |
Hydrodynamic Characteristics of Coolant Flow in Bundles of Ribbed Fuel Rods Located with Increased Pitch of Spacing
| Authors: Markov P.V., Solonin V.I. | Published: 20.11.2013 |
| Published in issue: #4(93)/2013 | |
| DOI: | |
| Category: Power-generating and Transport Machine Building | |
| Keywords: fast fission reactors, spacing of fuel rods, pressure drop coefficient, mass transfer, computational fluid dynamics | |