Endochronic Theory of Viscoplasticity. An Example of its Practical Implementation for Highly Filled Polymeric Material
| Authors: Eremichev A. | Published: 02.08.2018 |
| Published in issue: #4(121)/2018 | |
| DOI: | |
| Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
| Keywords: plasticity, viscoplasticity, thermodynamics, internal variables, K. Valanis, endochronic theory, highly filled polymer material, finite element method, testing of materials | |
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 | |
Determining time of the complete relaxation of contact interaction between the fuel clad and the elastic spacer grid cell in WWER fuel assembly
| Authors: Gusev M.P., Danilov V.L., Yakovlev V.Yu. | Published: 06.10.2015 |
| Published in issue: #5(104)/2015 | |
| DOI: | |
| Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
| Keywords: fuel assembly, contact force relaxation, fuel rod, spacer grid | |
Modified Model of the Instantaneous Jump for the Dynamics of a Nuclear Reactor
| Authors: Koposov E.B. | Published: 19.06.2015 |
| Published in issue: #3(102)/2015 | |
| DOI: | |
| Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
| Keywords: nuclear reactor, reactivity, kinetics, dynamics, process, computing, model, instant jump | |
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 | |
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 | |
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 | |
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 | |
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 | |