Results 231 to 240 of about 1,326,999 (268)
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Microstructural effects on the hydrogen permeation of an Inconel alloy 690
Corrosion Science, 2008Abstract In the present work, hydrogen permeability tests were carried out in Inconel 690 in the as-received (AR) condition and after heat treating. The heat treatments promoted total solid solution (SA) or a microstructure full of grain boundary (gb) coverage with M 23 C 6 carbides (A800).
J.M. Zagal +4 more
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The growth mechanism of grain boundary carbide in Alloy 690
Materials Characterization, 2013Abstract The growth mechanism of grain boundary M23C6 carbides in nickel base Alloy 690 after aging at 715 °C was investigated by high resolution transmission electron microscopy. The grain boundary carbides have coherent orientation relationship with only one side of the matrix. The incoherent phase interface between M23C6 and matrix was curved, and
Hui Li +3 more
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Degradation of Alloy 690 After Relatively Short Times
Corrosion, 2016The purpose of this work is to understand quantitative processes which underlie the initiation of stress corrosion cracking (SCC) of cold-worked, thermally treated Alloy 690 after long-term exposures in high-temperature water. Long-term stress corrosion cracking initiation tests up to 34,484 h have been performed on cold-worked, thermally treated Alloy
Koji Arioka +4 more
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Corrosion behavior of Alloy 690 in aerated supercritical water
Corrosion Science, 2013Abstract The oxidation behavior of Alloy 690 exposed to aerated supercritical water at different temperatures was investigated using gravimetry, scanning electron microscopy/energy dispersive X-ray spectroscopy, X-ray diffraction, X-ray photoelectron spectroscopy, Raman spectroscopy and electron probe micro-analyzer.
Xiangyu Zhong, En-Hou Han, Xinqiang Wu
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The oxidation of Inconel-690 alloy at 600 K in air
Applied Surface Science, 1988Abstract The alloy Inconel-690 has been oxidised at 600 K in air for periods varying between 30 s and 120 h and the composition of the oxide layer formed examined by scanning Auger microscopy (SAM), scanning electron microscopy with energy dispersive analysis of X-rays (SEM/EDAX), secondary ion mass spectrometry (SIMS) and X-ray photoelectron ...
G.C. Allen +3 more
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Carbide Precipitation and SCC Behavior of Inconel Alloy 690
Corrosion, 1988The carbon solubility, stress corrosion cracking (SCC) resistance, and microstructure of Inconel Alloy 690 was studied and compared to Alloy 600. Alloy 690 exhibited lower carbon solubility than Alloy 600 and, after a high temperature/short time thermal treatment, displayed greater SCC resistance in 10% NaOH than Alloy 600 which had been thermally ...
J. M. Sarver, J. R. Crum, W. L. Mankins
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Corrosion behavior for Alloy 690 and Alloy 800 tubes in simulated primary water
Corrosion Science, 2013Abstract Corrosion behavior for Alloy 690 and Alloy 800 in simulated primary water is studied by open-circuit potential (OCP) measurement, electrochemical impedance spectroscopy (EIS) and potentiodynamic polarization. Rise of pressure and temperature lead to negative shift of corrosion potential for both Alloy 690 and Alloy 800. EIS results show that
Xiaohui Li +3 more
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The IGSCC, sensitization, and microstructure study of Alloys 600 and 690
Nuclear Engineering and Design, 1993Both Alloys 600 and 690 were studied to understand the effect of heat treatment on the sensitization and SCC behavior of these alloys. The microstructural evolution and chromium depletion near the grain boundaries were carefully studied using analytical electron microscopy.
J.J. Kai, C.H. Tsai, G.P. Yu
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Development of U-Bending Technology for Alloy 690 Tubes
Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovatio, 2012Steam generator installed with heat-transfer tubes (HTT) is an enormous heat exchanger that uses heat energy derived from a reactor to generate steam. The steam drains into turbine generator of an nuclear power plant, and plays an important role in producing electric power in nuclear power plant.
Tae-Wan Ku +3 more
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