Results 31 to 40 of about 35,202 (297)
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
core +1 more source
Copper-acrylic enamel serves as lubricant for cold drawing of refractory metals [PDF]
, 1966 Acrylic enamel spray containing metallic copper pigment lubricates refractory metal tubing during cold drawing operations so that the tubing surface remains free from scratches and nicks and does not seize in the die.
Beane, C., Karasek, F.
core +1 more source
Advanced Engineering Materials, Volume 27, Issue 6, March 2025.The stability criteria affecting the formation of high‐entropy alloys, particularly focusing in supersaturated solid solutions produced by mechanical alloying, are analyzed. Criteria based on Hume–Rothery rules are distinguished from those derived from thermodynamic relations. The formers are generally applicable to mechanically alloyed samples.
Javier S. Blázquez +5 more
wiley +1 more source
Nicral ternary alloy having improved cyclic oxidation resistance [PDF]
, 1982 NiCrAl alloys are improved by the addition of zirconium. These alloys are in the Beta or gamma/gamma' + Beta region of the ternary system. Zirconium is added in a very low amount between 0.06 and 0.20 weight percent.
Barrett, C. A. +2 more
core +1 more source
Crystal Structure of the ZrO Phase at Zirconium/Zirconium Oxide Interfaces [PDF]
, 2014 Zirconium-based alloys are used in water-cooled nuclear reactors for both nuclear fuel cladding and structural components. Under this harsh environment, the main factor limiting the service life of zirconium cladding, and hence fuel burn-up efficiency ...
Grovenor, CRM +8 more
core +1 more source
Advanced Engineering Materials, EarlyView.The tribological behavior of 100Cr6 steel spheres textured via Vickers microindentation is evaluated under lubricated sliding by varying both dimple size and density. Fine and dense textures significantly reduce friction across all lubrication regimes, while large dimples increase it.
Farideh Davoodi +3 more
wiley +1 more source
He jishuBackgroundIn the nuclear industry, zirconium alloys, employed as structural materials, undergo irradiation-induced deformation owing to the combined effects of thermo, mechanical stress, and neutron irradiation during the irradiation process, thereby ...
HUANG Jun +3 more
doaj +1 more source
INFLUENCE OF ALLOY COMPOSITION ON WORK HARDENING BEHAVIOR OF ZIRCONIUM-BASED ALLOYS
Nuclear Engineering and Technology, 2013 Three types of zirconium base alloy were evaluated to study how their work hardening behavior is affected by alloy composition. Repeated-tensile tests (5% elongation at each test) were performed at room temperature at a strain rate of 1.7 × 10−3 s−1 for ...
HYUN-GIL KIM +3 more
doaj +1 more source
Modeling the water side corrosion and hydrogen pickup of VVER 1000 fuel clad [PDF]
Nuclear Technology and Radiation Protection, 2018 Zirconium alloys, are usually used as fuel cladding materials in VVER (water-cooled, water-moderated energy reactor) type reactors, mainly, due to their low neutron absorption cross-section, desirable mechanical properties, and good corrosion resistance ...
Ramezani Leila +2 more
doaj +1 more source
Advanced Engineering Materials, EarlyView.This study demonstrates an efficient recycling route for out‐of‐spec AlSi10Mg atomized powders through compaction and arc remelting followed by suction casting. By correlating compaction load, cooling rate, and resulting microstructure, we show that intermediate pressures (50–80 kN) and rapid cooling refine dendrites, reduce porosity, and enhance ...
Mila Christy de Oliveira +4 more
wiley +1 more source