Results 31 to 40 of about 1,067,811 (382)

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, Sayed M. Amer, Irina S. Loginova, Maria V. Glavatskikh, Andrey G. Mochugovskiy, Ruslan Yu. Barkov, Andrey V. Pozdniakov   +6 more
doaj   +1 more source

Analysis on Film Forming Mechanism of Chromium-Free Passivation Agent for Aluminum Alloy Wheel Hub [PDF]

Cailiao Baohu, 2023
In order to study the film forming mechanism of chromium-free passivation film for aluminum alloy wheel hub， the film-forming effect and mechanism of chromium-free chemical conversion film on aluminum alloy automobile wheel hub were studied by ...
CHEN Yingjiao, CHEN Bihong, YAN Liqiang, LI Heng, LIU Wanqing
doaj   +1 more source

Casting Process and Quality Control Analysis of Zr705C Zirconium Alloy

Metals
Basic 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, Zhongde Shan, Yong Zang, Dehua Jin, Chunling Bao, Xiao Liang, Qian Yao   +6 more
doaj   +1 more source

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, O.A. Kharytonova, T.A. Evdokymova   +2 more
doaj   +1 more source

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, Feaugas, Xavier, Martin, Rautenberg, Poquillon, Dominique   +3 more
core   +2 more sources

Oxygen Diffusion in Oxide Film and Matrix of Zirconium Alloys

Yuanzineng kexue jishu
The 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
doaj   +1 more source

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 هسته‌ای
Nuclear 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, M. Zaidabadi Nejad   +1 more
doaj   +1 more source

A Pilot Study with Randomised Controlled Design Comparing TiZr Alloy Dental Implants to Ti Implants

eJournal of Oral Maxillofacial Research, 2020
Objectives: Evidence on the clinical performance of recently introduced dental implants in titanium-zirconium alloy is sparse. The aim of the present pilot study with randomized controlled design is to compare changes in supporting structures around ...
Kristina Hultin, Annelie Eriksson, Christina Backe, Ulf Johansson, Kostas Bougas   +4 more
doaj   +1 more source

Investigations of Zr(IV) in LiF-CaF2: stability with oxide ions and electroreduction pathway on inert and reactive electrodes [PDF]

, 2013
In this work, a detailed electrochemical study of the molten LiF-CaF2-ZrF4 system is provided in the 810-920°C temperature range, allowing the determination of the reduction potential, the diffusion coefficient and the reduction mechanism of dissolved Zr(
Cassayre, Laurent, Chamelot, Pierre, Gibilaro, Mathieu, Massot, Laurent, Taxil, Pierre   +4 more
core   +2 more sources

Research on Machine Learning-based Corrosion Prediction Method for Zirconium Alloy in Dissolved Oxygen Water at 360 °C/18.6 MPa

Yuanzineng kexue jishu
The 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
doaj   +1 more source