Results 251 to 260 of about 30,108 (299)

SCC of Alloy 690 and Its Weld Metals

CORROSION 2012, 2011
Abstract Extensive SCC growth rate testing of Alloy 690 base metal, HAZ and weld metal was performed in representative PWR primary water at 290 to 360 °C. Intergranular cracking was observed in all materials. Growth rates as high as 1.2 x 10-6 mm/s were observed in the S-L orientation with microstructural banded material after cold ...
Peter L. Andresen, Martin M. Morra, Kawaljit Ahluwalia   +2 more
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Cavitation erosion behavior of Inconel 690 alloy

Materials Science and Engineering: A, 2008
The cavitation erosion behavior of Inconel 690 alloy was investigated using 20-kHz vibratory cavitation test equipment and analyzed by scanning electron microscopy (SEM). To clarify the development of cavitation damage with time, scanning electron photographs were recorded for various test durations, where the time was measured from the commencement of
Jie-Hao Chen, Weite Wu
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Constitutive model for nickel alloy 690 (Inconel 690) at various strain rates and temperatures

International Journal of Plasticity, 2016
no ...
Blaizot, Jérôme, Chaise, Thibaut, Nélias, Daniel, Perez, Michel, Cazottes, Sophie, Chaudet, Philippe   +5 more
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Wear behavior of plasma nitrided inconel 690 alloy

AIP Conference Proceedings, 2019
In 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, Yogesh Chandra Sharma, Vajja Vidyasagar, Dheeraj Bhardwaj   +3 more
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Research on M23C6 precipitation of 690 alloy

2014
Precipitation M23C6 of 690 alloy was studied in this paper. Firstly, M23C6 precipitation and evolution of chromium-depleted zone of 690 alloy during TT were studied. Evolution of chromium-depleted zone of 690 alloy was affected markedly by TT.The test results showed that the lowest chromium concentration in chromium-depleted zone raised dramatically ...
Song Zhigang, Feng han, Zheng Wenjie, Zhang Lihong, Ma Mingjuan, Sang Weijun   +5 more
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Degradation of Alloy 690 After Relatively Short Times

Corrosion, 2016
The 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, Roger W. Staehle, T. Yamada, T. Miyamoto, T. Terachi   +4 more
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Comparison of Different Thermal Treatments for Alloy 690

CORROSION 1990, 1990
Abstract Intergranular carbide precipitation reactions are known to increase the resistance of INCONEL* alloys 600 and 690 (UNS N06600 and N06690)to stress corrosion cracking in nuclear steam generator environments. Initially the same thermal treatment used for alloy 600 was applied to alloy 690, i.e., 1300°F (704°C)/15 hrs.
J R Crum, K A Heck, T. M. Angeliu
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INCONEL ALLOY 690

Alloy Digest, 1981
Abstract INCONEL Alloy 690 is a wrought nickel-base alloy with excellent resistance to many corrosive aqueous media and high-temperature atmospheres. It also has high strength, good metallurgical stability, and favorable fabrication characteristics. It has excellent resistance to stress-corrosion cracking in chloride-containing solutions
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Internal oxidation of alloy 690 in hydrogenated steam

Corrosion Science, 2015
Abstract Alloy 690 was exposed to a hydrogenated steam environment at 480 °C and 1 bar, considered to simulate primary water in a pressurized water reactor. The possibility of internal oxidation in Alloy 690 was evaluated and the likely relevance to SCC in primary water is discussed. Initial surface imaging revealed intragranular metallic Ni nodules,
S.Y. Persaud, S. Ramamurthy, R.C. Newman
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SCC of Alloy 690 in High Temperature Water

CORROSION 2010, 2010
Abstract Various microstructures of Alloy 690 and types of cold work were tested in representative pressurized water reactor primary water at 290 to 360 °C. Intergranular cracking was observed on Alloy 690 at constant stress intensity factor (no cycling) and with “gentle” cyclic loading, but not in every case.
Peter L. Andresen, Martin M. Morra, Al Ahluwalia, John Wilson   +3 more
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