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Electroslag Strip Cladding of Steam Generators With Alloy 690
Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management, 2006The present paper details the results of electroslag cladding and tube-to-tubesheet welding qualification tests conducted by Ansaldo-Camozzi ESC with Alloy 690 (Alloy 52 filler metal) on steel for nuclear power stations’ steam generators shell, tubesheet and head; the possibility of submerged arc cladding on first layer was also considered.
M. Consonni, F. Maggioni, F. Brioschi
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Wear behavior of plasma nitrided inconel 690 alloy
AIP Conference Proceedings, 2019In this study an effort has been made for the plasma ion nitriding (PIN) of inconel 690 alloy. After plasma nitriding, samples were investigated by various characterization techniques such as; micro-hardness measurement, X-ray diffraction analysis and pin on disk wear test.
Ravindra Kumar +3 more
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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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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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