Results 21 to 30 of about 1,077,086 (402)

PROTECTIVE VACUUM-ARC COATINGS ON ZIRCONIUM ALLOY FUEL CLADDING TO PREVENT CATASTROPHIC ACCIDENTS AT NUCLEAR REACTORS

open access: yesProblems of Atomic Science and Technology, 2023
The processes of vacuum arc deposition of multicomponent coatings based on Cr, Ti, Al, Fe, Y, Si, and their nitrides with a thickness of 5…9 µm for the protection of zirconium alloy fuel rods were developed.
A. Kuprin   +7 more
semanticscholar   +1 more source

Oxidation behavior of Cr-coated zirconium alloy cladding in high-temperature steam above 1200 °C

open access: yesnpj Materials Degradation, 2021
Dense, uniform, and well-adhered chromium (Cr) coatings were deposited on zirconium (Zr) alloy claddings by using physical vapor deposition (PVD). The Cr-coated samples were tested at 1200  o C and 1300  o C, respectively, for different exposure time in ...
Hai-Bin Ma   +8 more
semanticscholar   +1 more source

Shear Performance of Zirconium Alloy Welds Under Different Strain Rates

open access: yesFrontiers in Energy Research, 2022
Welding is one of the important connection methods for zirconium alloy, and the shear failure under the dynamic load is a typical failure mode of the weld.
Haoyu Wang   +8 more
doaj   +1 more source

Effect of Heat Treatment in Oxygen-Containing Medium on Fatigue Life of Zirconium Alloy

open access: yesStrojnícky časopis - Journal of Mechanical Engineering, 2022
The effect of heat treatment in oxygen-containing medium on fatigue properties of zirconium alloy samples was shown. This gas treatment improved fatigue life in pure bending and cyclic tensile testing.
V. Trush   +4 more
semanticscholar   +1 more source

Production of Zirconium-Niobium Alloys for Nuclear Reactors Fuel Rods via SHS Process

open access: yesAlloys, 2023
This article presents the results of studies of the self-propagating high-temperature synthesis (SHS) for obtaining zirconium alloys with niobium by the method of calcium-thermal reduction of nuclear-grade zirconium tetrafluoride in the presence of ...
Anatoly Mukhachev   +2 more
doaj   +1 more source

Trial manufacture and properties of protective lubricants for hot extrusion of zirconium alloy

open access: yes工程科学学报, 2021
Lubrication is the key in obtaining excellent products when zirconium alloys are hot extruded. Reasonable lubrication conditions are important to improve the product quality, reduce energy consumption, and prolong the service life of tools and dies ...
Fan ZHAO   +3 more
doaj   +1 more source

Multi-Elemental Coatings on Zirconium Alloy for Corrosion Resistance Improvement

open access: yesCoatings, 2022
Zirconium alloys are commonly used as a cladding material for fuel elements in nuclear reactors. This application is connected with zirconium alloy’s good resistance to water corrosion and radiation resistance under normal working conditions. In the case
B. Sartowska   +4 more
semanticscholar   +1 more source

Relations of Microstructural Attributes and Strength-Ductility of Zirconium Alloys with Hydrides

open access: yesChinese Journal of Mechanical Engineering, 2023
As the first safety barrier of nuclear reactors, zirconium alloy cladding tubes have attracted extensive attention because of its good mechanical properties.
Chao Fang   +3 more
doaj   +1 more source

Capability assessment for application of clay mixture as barrier material for irradiated zirconium alloy structure elements long-term processing for storage during decommissioning of uranium-graphite nuclear reactors [PDF]

open access: yes, 2004
The radionuclide composition and the activity level of the irradiated zirconium alloy E110, the radionuclide immobilization strength and the retention properties of the mixed clay barrier material with respect to the radionuclides identified in the alloy
S G Kotlyarevskiy   +7 more
core   +2 more sources

Application of Low Melting Metals for Separation of Uranium and Zirconium in a “Fused Chloride—Liquid Alloy” System

open access: yesMetals, 2021
Closeness of electrochemical properties of uranium and zirconium makes separation of these metals in pyroelectrochemical reprocessing of spent nuclear fuels a challenging task. Varying electrode material can change metals’ deposition potentials.
Vladimir A. Volkovich   +4 more
doaj   +1 more source

Home - About - Disclaimer - Privacy