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 |
Analysis of Test Results of Turbine Bladed Discs
Authors: Seleznev V.G., Pavlov Yu.I., Il | Published: 09.02.2015 |
Published in issue: #1(100)/2015 | |
DOI: | |
Category: Power Engineering | Chapter: Turbomachines and Combination Turbine Plants | |
Keywords: forced vibrations, self-excited vibrations, Van der Pol equation, spectral analysis, holographic interferometry |
Operation Analysis of Channel Guide Vane of Radial-Axial Freon Turbine
Authors: Kostenko A.A., Rozenoer T.M., Leonov V.P. | Published: 09.02.2015 |
Published in issue: #1(100)/2015 | |
DOI: | |
Category: Power Engineering | Chapter: Machines and Devices, Processes of Refrigeration and Cryogenic Engineering, Air Conditioning | |
Keywords: channel guide vane, freon turbine, Rankine cycle, heat utilization, organic working fluid |
Research the Wind Effect on the Fans Performance of Air-Cooled Condenser for Geothermal Power Station
Authors: Zhinov A.A. , Shevelev D.V. | Published: 09.02.2015 |
Published in issue: #1(100)/2015 | |
DOI: | |
Category: Power Engineering | Chapter: Machines and Devices, Processes of Refrigeration and Cryogenic Engineering, Air Conditioning | |
Keywords: air-cooled condenser (ACC), fan, numerical investigation, wind |
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 |
Forecast of Reactor Steel 08Х16Н11М3-ПД Mechanical Properties under Creep Conditions with Regard for Irradiation and without Irradiation
Authors: Demidov A.S., Kashelkin V.V., Kashtanov A.D., Jakovlev V.A. | Published: 15.04.2015 |
Published in issue: #2(101)/2015 | |
DOI: | |
Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
Keywords: long-term strength, creep, forecast, irradiation, strain, steel 08Х16Н11М3-ПД, steel AISI 316 |
Optimization and Application of Analytical Model to Define Heat Carrier Parameters in T-Joints of Pipelines
Authors: Kurnosov M.M. | Published: 15.04.2015 |
Published in issue: #2(101)/2015 | |
DOI: | |
Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
Keywords: T-joint, analytical model, numerical simulation, computational fluid dynamics (CFD), LES, sub-grid model, analytical model scaling |
Investigation of gas thermal stratification
Authors: Burtsev S.A. | Published: 28.05.2015 |
Published in issue: #2(31)/1998 | |
DOI: | |
Category: Power Engineering | Chapter: Hydraulic Machines and Hydropneumatic units | |
Keywords: |
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 |
Diagnostics of Two-Phase Flows in Vertical Channels During the Natural Circulation by Near-Wall Pressure Pulsations
Authors: Isakov N.Sh., Perevezentsev V.V. | Published: 19.06.2015 |
Published in issue: #3(102)/2015 | |
DOI: | |
Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
Keywords: hydrodynamics, two-phase flows, diagnostics, natural circulation, nearwall pressure pulsations, flow regime, power plants, nuclear reactors |