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Published in 2020 at "Acta Materialia"
DOI: 10.1016/j.actamat.2019.10.041
Abstract: Abstract The environmental degradation of four different types of grain boundaries were investigated on alloy 690 following slow strain rate tensile tests in 360°C hydrogenated water. Random high angle boundaries (RHABs) support fast Cr diffusion…
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Keywords:
boundary structure;
grain boundary;
alloy 690;
hydrogenated water ... See more keywords
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Published in 2017 at "Corrosion Science"
DOI: 10.1016/j.corsci.2017.07.004
Abstract: Abstract The oxide film formed on alloy 690 in simulated pressurized water reactor primary water is decorated with NiFe 2 O 4 particles which remain epitaxial with matrix. The penetrative inner oxides on both surface…
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Keywords:
water reactor;
simulated pressurized;
water;
alloy 690 ... See more keywords
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Published in 2020 at "Corrosion Science"
DOI: 10.1016/j.corsci.2019.108313
Abstract: Abstract The effect of intergranular (IG) carbides on the cracking behavior of cold worked Alloy 690 was studied in both subcritical and supercritical water (SCW) environments. The crack growth rate (CGR) was lower when IG…
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Keywords:
water;
alloy 690;
cold worked;
effect ... See more keywords
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Published in 2021 at "Corrosion Science"
DOI: 10.1016/j.corsci.2021.109442
Abstract: Abstract Crevice corrosion behavior of Alloy 690 in 290 °C deaerated chloride solution was investigated using a high-temperature crevice corrosion exposure device. The results show that the oxide film enriched in Cr formed inside the crevice…
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Keywords:
chloride solution;
nodular corrosion;
alloy 690;
corrosion ... See more keywords
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Published in 2019 at "Journal of Alloys and Compounds"
DOI: 10.1016/j.jallcom.2019.03.362
Abstract: Abstract The effectiveness of zinc on the electrochemical behavior and oxide film formation of a 30% cold forged Alloy 690 exposed to high-temperature borated and lithiated water was investigated. The morphology and chemical composition of…
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Keywords:
water;
forged alloy;
alloy 690;
corrosion ... See more keywords
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Published in 2021 at "Journal of Alloys and Compounds"
DOI: 10.1016/j.jallcom.2020.156694
Abstract: Abstract M23C6 carbides with a distinct dendritic morphology are discovered for the first time in continuously cooled Alloy 690. Branches stretch out from the interfaces of initial carbides, and as much as the fifth order…
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Keywords:
alloy 690;
m23c6 carbides;
dendritic morphology;
precipitation dendritic ... See more keywords
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Published in 2018 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2017.10.003
Abstract: Abstract The stress corrosion cracking (SCC) behavior of Alloy 690 with 0, 20% and 30% cold work (CW) was studied in supercritical water (SCW) environment with an emphasis on CW and creep on the CGRs…
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Keywords:
corrosion cracking;
alloy 690;
stress corrosion;
behavior alloy ... See more keywords
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Published in 2019 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2019.03.016
Abstract: Abstract By anodic potentiostatic polarization and electrochemical impedance spectroscopy (EIS) measurements, the effect of temperature (200 °C, 250 °C, and 300 °C) on the electrochemical behavior of Alloy 690 was investigated in oxygenated borate buffer solution containing H…
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Keywords:
effect temperature;
passive film;
water;
temperature ... See more keywords
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Published in 2017 at "Tribology International"
DOI: 10.1016/j.triboint.2017.07.001
Abstract: Abstract The effects of sliding amplitude and normal load on the fretting wear behavior of alloy 690 tube exposed to an environment simulating the secondary side water chemistry of nuclear power plant are studied and…
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Keywords:
sliding amplitude;
alloy 690;
fretting wear;
690 tube ... See more keywords
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Published in 2018 at "Corrosion"
DOI: 10.5006/2562
Abstract: Nickel alloy 690 (UNS N06690) is one of the current choices for nuclear power plant steam generator tubing. The severity of certain stress corrosion cracking submodes in Ni-Cr-Fe alloys, such as Al...
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Keywords:
loop electrochemical;
double loop;
alloy 690;
nickel alloy ... See more keywords