Results 61 to 70 of about 1,067,811 (382)
Diffusion of Hydrogen Isotopes in Zirconium Alloys
He huaxue yu fangshe huaxueTritium is a common radioactive product in nuclear power plants. It is easy to diffuse, penetrate and be easily absorbed by organisms due to its small atomic radius.
Long WANG +6 more
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He jishu, 2021 BackgroundLarge-grained UO2 pellet and coated zirconium cladding are the most practical fuel pellet and cladding material scheme for accident tolerant fuel (ATF) solutions, which are expected to be commercially available in the next few years.
YOU Yan, GONG Xin, LI Cong
doaj +1 more source
Calculation of the P-T phase diagram and tendency toward decomposition in equiatomic TiZr alloy
, 2010 Electronic, structural and thermodynamic properties of the equiatomic alloy TiZr are calculated within the electron density functional theory and the Debye-Gruneisen model.
Aksenenkov V V +4 more
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Advanced Engineering Materials, EarlyView.The influence of Hot Isostatic Pressing (HIP) temperature on the microstructure and creep performance of powder bed fusion–laser beam processed CM247LC superalloy is investigated. Grain growth and γ’ precipitate evolution are characterized following HIP at varying temperatures.
Ahmed Fardan +4 more
wiley +1 more source
Phase-Field Model of Hydride Blister Growth Kinetics on Zirconium Surface
Frontiers in Materials, 2022 The precipitation of zirconium hydride blisters on the surface of zirconium alloy cladding destroys the integrity of the material and leads to material failure, which has serious potential safety hazards.
Shuai Wu +11 more
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Advanced Engineering Materials, EarlyView.Bimetallic structures of Inconel 718 and CuCrZr are fabricated using the laser powder directed energy deposition method. The study reveals a strong dependence of interface characteristics such as width and interfusion on processing and heat treatment strategies.
Hamidreza Javidrad, Bahattin Koc
wiley +1 more source
Deep Learning of Accurate Interatomic Potentials for Uranium, Zirconium and Uranium-Zirconium Alloy
He huaxue yu fangshe huaxueUranium-zirconium alloy is an important nuclear fuel in Integral Fast Reactor, which is of great significance to study its basic physical properties at high temperature by using advanced calculation methods.
Wan-qiu YIN +5 more
doaj +1 more source
Effects of scandium and zirconium combination alloying on as-cast microstructure and mechanical properties of Al-4Cu-1.5Mg alloy [PDF]
China Foundry, 2011 The influences of minor scandium and zirconium combination alloying on the as-cast microstructure and mechanical properties of Al-4Cu-1.5Mg alloy have been experimentally investigated.
Xiang Qingchun, Zhao Jing, Pan Haicheng
doaj
Nickel-base alloy containing Mo-W-Al-Cr- Ta-Zr-C-Nb-B Patent [PDF]
, 1966 Nickel base alloy with resistance to oxidation at high temperatures and superior stress-rupture ...
Freche, J. C., Waters, W. J.
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HIGH-STRENGTH ZIRCONIUM ALLOYS [PDF]
, 1959 The properties of zirconium alloyed with aluminum tin, and molybdenum were investigated. Using reactorgrade zirconium sponge, 11 zirconium-base alloys were double arc-melted and cast into 6-in.-diam. ingots weighing 35 lb each. By such standard hot working procedures as extruding and rolling, the ingots were converted to 1/8-in.-thick strips.
Wagner, R. K., Kline, H. E.
openaire +2 more sources