On the Development of Tolerant Fuel --- a New Generation Fuel
| Authors: Sotnikov A.S. | Published: 21.12.2021 |
| Published in issue: #4(139)/2021 | |
| DOI: | |
| Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
| Keywords: reactor core safety, fuel element cladding operation, zirconium alloys, silicon carbide, fragility, composite, tolerant fuel | |
Hybrid Fusion-Fission System with Neutron Source Based on Deuterium Plasma
| Authors: Chirkov A.Yu. | Published: 07.06.2020 |
| Published in issue: #3(132)/2020 | |
| DOI: | |
| Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
| Keywords: deuterium, fusion neutrons, hybrid reactor, magnetic confinement, plasma, energy balance | |
Unsteady Motion of Viscous Electrically Conductive Fluid Rotating in Half-Space Bounded by a Wall in the Presence of Medium Injection (Suction)
| Authors: Gurchenkov A.A. | Published: 20.02.2020 |
| Published in issue: #1(130)/2020 | |
| DOI: | |
| Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
| Keywords: magnetic hydrodynamic equations, electrically conductive fluid, normal oscillations, boundary layers | |
Comparative Analysis of the Effect of Technological Defects on the Strength of Е110 Alloy Fuel Cladding under Stress Corrosion Cracking
| Authors: Sotnikov A.S. | Published: 23.12.2019 |
| Published in issue: #6(129)/2019 | |
| DOI: | |
| Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
| Keywords: E110 zirconium alloy, fuel cladding, corrosion, stress, internal surface, technological defect, stress corrosion cracking | |
Simulation of Initiation and Development of Corrosion Cracks in Zirconium Fuel Claddings Under Conditions of Stress Corrosion Cracking in Environment of Iodine
| Authors: Sotnikov A.S. | Published: 17.10.2019 |
| Published in issue: #5(128)/2019 | |
| DOI: | |
| Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
| Keywords: E110 zirconium alloy, fuel cladding, stress corrosion cracking, simulation, reactor, operation | |
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 | |
Investigating the Correlation between Selective Laser Melting Parameters and Structural Defects in a VKNA-4UR-Type Nickel Alloy
| Authors: Bazyleva O.A., Unchikova M.V., Golovlev N.A., Evgenov A.G. | Published: 07.12.2018 |
| Published in issue: #6(123)/2018 | |
| DOI: | |
| Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
| Keywords: heat-resistant intermetallic nickel alloy, additive manufacturing, selective laser melting, laser power, distance between paths, scanning speed, porosity, microcracks, structural defects | |
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 | |