Results 41 to 50 of about 35,202 (297)
Yuanzineng kexue jishuIn the severe accidents in pressurized water reactors (PWR), the oxidation behavior of zirconium alloy cladding melts will increase the apparent viscosity of the melt, which significantly influences the migration and relocation process of core melts and ...
WANG Haoli, ZHANG Yapei, TIAN Wenxi, QIU Suizheng, SU Guanghui
doaj +1 more source
Hydride Phases and Hydride Orientation in Zirconium Alloys
Cailiao gongcheng, 2018 As a fuel cladding materials of the nuclear reactor, water side corrosion and hydrogen absorption generated in zirconium alloys which due to the embrittlement of matrix and hydrogen induced delayed cracking.
ZENG Wen, LUAN Bai-feng, LIU Na
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Synthesis and Structural Characterization of U-Zr-Nb Alloys [PDF]
Materials Research, 2017 U-xZr-yNb alloys with values of x varying from 32% to 50% (wt.%Zr) and y varying from 6% to 10% (wt.%Nb) were produced by the arc melting technique. The effect of the addiction of zirconium and niobium on the phase stabilization of γ-U, lattice parameter,
Ailton da Silva Ferreira +5 more
doaj +2 more sources
Nickel base coating alloy [PDF]
, 1986 Zirconium is added to a Ni-30 Al (beta) intermetallic alloy in the range of 0.05 w/o to 0.25 w/o. This addition is made during melting or by using metal powders.
Barrett, C. A., Lowell, C. E.
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Advanced Engineering Materials, EarlyView.Trace additions of Sn and Sr combined with a two‐step aging treatment are shown to enhance the microstructure and performance of Al–Zr–Sc conductor alloys. Strength and electrical conductivity increase concurrently through accelerated precipitation of fine Al3(Sc, Zr) precipitates and improved dislocation resistance, offering a cost‐effective pathway ...
Quan Shao +3 more
wiley +1 more source
Structure and Thermodynamical Properties of Zirconium hydrides from first-principle
, 2011 Zirconium alloys are used as nuclear fuel cladding material due to their mechanical and corrosion resistant properties together with their favorable cross-section for neutron scattering.
Ackland +24 more
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Application of Raman and Photoluminescence Spectroscopy to MgO‐C Refractories
Advanced Engineering Materials, EarlyView.Visible to near infrared luminescence of MgO is studied on MgO‐C bricks and nominally pure MgO powder, with focus on two similar sharp high‐intensity signals, at 699 and 871 nm, each surrounded by symmetrical sidebands. The nature of these sidebands is investigated by temperature‐dependent spectroscopic measurements, confirming phonon involvement by ...
Julia Richter +5 more
wiley +1 more source
Успехи физики металловThe available literature experimental data on corrosion resistance of traditional and advanced fuel rod cladding materials for water-cooled reactors are summarized.
V.A. Zuyok, Yu.V. Kovalenko, V.V. Shtefan, R.O. Rud, M.V. Tretiakov, and Ya.O. Kushtym
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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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Effect of Laser Deoxidation on Adhesive‐Bonded Aluminum in an Oxygen‐Free Atmosphere
Advanced Engineering Materials, EarlyView.This study investigates laser ablation of aluminum under oxygen‐free conditions. The goal is to produce oxide‐free substrates that enable improved adhesive bonding with epoxy. Optimized laser parameters (90% overlap, 300 µJ) combined with oxide‐free substrates result in the highest tensile strength of the adhesive bond.
Sandra Gerland +5 more
wiley +1 more source