Innovative approach for the in vitro research on biomedical scaffolds designed and customized with CAD-CAM technology [PDF]
, 2016 Studies on biomaterials involve assays aimed to assess the interactions between the biomaterial and the cells seeded on its surface. However, the morphology of biomaterials is heterogeneous and it could be tricky to standardize the results among ...
Apicella, Davide +11 more
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Study of Trivalent Chromium Conversion Coating Formation at Solution—Metal Interface
Metals, 2023 The present study employed a tungsten pH microelectrode to study the formation of trivalent chromium conversion (TCC) coatings on Al, AA 2024-T3 aluminum alloy and AZ91D magnesium alloy in SurTec ChromitAL solutions.
Wentao Sun +7 more
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Anomalous electrical conductivity in rapidly crystallized Cu${}_{50-x}$Zr${}_{x}$ (x = 50 - 66.6) alloys [PDF]
, 2015 Cu${}_{50-x}$Zr${}_{x}$ (x = 50, 54, 60 and 66.6) polycrystalline alloys were prepared by arc-melting. The crystal structure of the ingots has been examined by X-ray diffraction.
Chtchelkatchev, N. M. +3 more
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Effect of Zr on Microstructure and Mechanical Properties of the Al–Cu–Yb and Al–Cu–Gd Alloys
Metals, 2022 The effect of zirconium on the microstructure, phase composition, and mechanical properties of AlCuYb and AlCuGd alloys was studied. The microstructure of the as-cast alloys did not consist of new intermetallic phases of zirconium with other elements, so
Olga I. Mamzurina +6 more
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Casting Process and Quality Control Analysis of Zr705C Zirconium Alloy
MetalsBasic research on and the industrial development of zirconium alloys in China started relatively late, with insufficient domestic production capacity for zirconium alloy castings; especially for large-sized zirconium alloy castings, there is little ...
Youwei Zhang +6 more
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Microstructural characterization of creep anisotropy at 673K in the M5® alloy [PDF]
, 2012 Zirconium alloy tubing is used in pressurized water nuclear reactors in order to prevent fissile material from leaking into the coolant. It can be the first safety wall of nuclear fuel, and is submitted to complex thermomechanical loadings.
Cloué, Jean-Marc +3 more
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Yuanzineng kexue jishuThe corrosion resistance of zirconium alloy is of great relevance to the long-term operation of reactors. The surface of zirconium alloy undergoes oxidation in the complex environment of nuclear reactors, and their weight increases gradually. In order to
WU Jing1, , WEI Tianguo1, ZHAO Boxue2, FAN Hongyuan2, WANG Jun2, ZHAO Yi1
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Oxygen Diffusion in Oxide Film and Matrix of Zirconium Alloys
Yuanzineng kexue jishuThe diffusion coefficient of oxygen in zirconium alloy oxide film and matrix is an important parameter in corrosion kinetics of zirconium alloys. At present, there are some reports on the diffusion coefficient of oxygen in zirconium and oxide film, but ...
ZHANG Junsong, WU Jun, LIAO Jingjing, WEI Tianguo, LONG Chongsheng
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Investigating new cladding material for NuScale reactor based on neutronic and thermo-mechanical properties using M5, E110, Zircaloy 4 and FeCrAl claddings [PDF]
مجله علوم و فنون هستهایNuclear fuel clads are among the most important components of a nuclear reactor. These clads are typically made of zirconium alloy; However these alloys do not possess the best thermo-mechanical properties.
H. Zayermohammadi Rishehri +1 more
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Radiation tests of products made of calcium-thermal zirconium grade СTZ-110 under operation of the VVER-440 reactor [PDF]
Ядерна фізика та енергетика, 2020 The paper presents the results of reactor tests of fuel assemblies with cladding made of zirconium alloy grade СTZ-110 at the material testing reactor of National Research Center (NRC) "Kurchatov Institute" at Novovoronezh and Leningrad NPP under various
A.P. Mukhachev +2 more
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