Results 31 to 40 of about 1,077,086 (402)

Study of Coatings Formed on Zirconium Alloy by Plasma Electrolytic Oxidation in Electrolyte with Submicron Yttria Powder Additives

open access: yesMetals, 2021
Coatings with thickness 40 to 150 μm were formed by plasma electrolytic oxidation (PEO) on the zirconium alloy Zr-1Nb (Zr-1% Nb) in the slurry electrolyte containing 9 g/L Na2SiO3 5H2O, 5 g/L Na(PH2O2) and 6 g/L submicron Y2O3 yttria powder during 60 min
S. Savushkina   +3 more
semanticscholar   +1 more source

Corrosion and Wear-Resistant Composite Zirconium Nitride Layers Produced on the AZ91D Magnesium Alloy in Hybrid Process Using Hydrothermal Treatment

open access: yesCrystals, 2023
The aim of the study was to investigate the possibility of an effective improvement in performance properties, including corrosion and wear resistance of magnesium AZ91D alloy using a surface engineering solution based on zirconium nitride composite ...
Michał Tacikowski   +5 more
doaj   +1 more source

Influence of HPT and Accumulative High-Pressure Torsion on the Structure and Hv of a Zirconium Alloy

open access: yes, 2021
The authors previously used the accumulative high-pressure torsion (ACC HPT) method for the first time on steel 316, β-Ti alloy, and bulk metallic glass vit105.
D. Gunderov   +3 more
semanticscholar   +1 more source

The influence of boron addition on properties of copper-zirconium alloys [PDF]

open access: yesScience of Sintering, 2023
Copper-zirconium alloys with high conductivity were produced using powder metallurgy. Two-steps manufacturing process, containing mechanical alloying followed by hot pressing, was applied in achieving improved mechanical and physical properties of Cu-Zr ...
Simić M.   +6 more
doaj   +1 more source

Influence of surface state on hydrogen sorption by zirconium alloy Zr1Nb [PDF]

open access: yes, 2003
This work is focused on the investigation of hydrogen sorption behavior by zirconium alloy Zr1Nb with different surface states. Zirconium alloy samples in initial state, after ion cleaning with subsequent nickel deposition and after treatment by Low ...
Kudiyarov, Victor Nikolaevich   +4 more
core   +1 more source

Protection of AlCrNbSiTi High Entropy Alloy Coating on Zirconium Alloy by High-temperature Steam Oxidation at 1 200 ℃

open access: yesYuanzineng kexue jishu, 2023
It is one of the main ideas of developing ATF cladding materials to improve the accident resistance of zirconium alloy by coating. In the existing research on the protection mechanism of the coating on zirconium alloy substrate, the main focus is on the ...
TU Menghe;HU Yong;ZHANG Baoliang;LIU Xin;LI Shen;WANG Hui
doaj  

Rapid assessment of structural and compositional changes during early stages of zirconium alloy oxidation

open access: yesnpj Materials Degradation, 2020
A multimodal chemical imaging approach has been developed and applied to detail the dynamic, atomic-scale changes associated with oxidation of a zirconium alloy (Zircaloy-4). Scanning transmission electron microscopy, a gas-phase reactor chamber attached
E. Kautz   +11 more
semanticscholar   +1 more source

Microstructural characterization of creep anisotropy at 673K in the M5® alloy [PDF]

open access: yes, 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
core   +3 more sources

Study on hydrogen permeation method of zirconium alloy tube

open access: yesAdvances in Materials Science, 2020
Physical and Chemical Testing Center of North Nuclear Fuel Components Co., Ltd., Baotou, Inner Mongolia, 014035, China The determination process of hydride orientation factor of zirconium alloy mainly includes hydrogen permeation process and hydride ...
Du Hao
semanticscholar   +1 more source

Study on Quantitative Method for Hydrogen Distribution in Zirconium Alloy via Neutron Tomography

open access: yesYuanzineng kexue jishu, 2023
Hydrogen ingress into zirconium cladding can cause embrittlement and affects the service safety of nuclear fuel cladding. Traditional hydrogen analysis methods like hydrogen determination instrument method and metallographic method, can only give the ...
WU Meimei;LIU Xin;HE Linfeng;HU Yong;RUAN Shihao;WANG Tianyun;LI Yuqing;WEI Guohai;SUN Kai
doaj  

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