Results 211 to 220 of about 1,567 (242)
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New Etching Procedure for Alloy 690 Ein neues Ätzverfahren für die Legierung 690
Practical Metallography, 1998Alloy 690 for steam generator tubing is now etched in bromine-methanol for the microstructural examination prior to delivery. A number of etching methods have been tested to find an alternative procedure that is highly reproducible, that clearly reveals all grain boundaries and carbides and that does not involve too harmful chemicals.
Agneta Östberg, Johan Frodigh
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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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SCC Behavior of Alloy 690 HAZ in a PWR Environment
Volume 6: Materials and Fabrication, Parts A and B, 2011The objective of this work is to determine the cyclic and stress corrosion cracking (SCC) crack growth rates (CGRs) in a simulated PWR water environment for Alloy 690 heat affected zone (HAZ). In order to meet the objective, an Alloy 152 J-weld was produced on a piece of Alloy 690 tubing, and the test specimens were aligned with the HAZ.
Bogdan Alexandreanu +3 more
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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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Dissolution Mitigation of Alloy 690 By Electrochemical Surface Modification
ECS Meeting Abstracts, 2014Metal oxide particles and metal ions are released from the inside surface of steam generator (SG) tubes in operating nuclear power plants. These corrosion products are transported into the core, forming a crud on fuel cladding. The composition of the fuel crud consists mainly of nickel ferrite, and it indicates that the primary source is the nickel ...
Kyung Mo Kim +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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