Results 211 to 220 of about 1,326,999 (268)

Effects of PbO on the repassivation kinetics of alloy 690

Corrosion Science, 2006
Effects of PbO on the repassivation kinetics of alloy 690 were examined to elucidate the reason why the alloy, otherwise immune, is susceptible to stress corrosion cracking (SCC) in high temperature water contaminated with a small amount of Pb compounds.
Ahn, S, Rao, VS, Kwon, H Kwon, Hyuk-Sang, Kim, U   +3 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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Low Cycle Fatigue of Alloy 690 in the PWR Environment

Volume 2: Design & Analysis
Abstract Environmentally Assisted Fatigue (EAF) is one of the concerns for the extended operation of nuclear power plants. Over time, certain components experience thermal cycling while being exposed to the chemically active environment of Pressurized Water Reactors (PWRs).
Kushal Gowda Jayaram, Joseph Huret, Jonathan Quibel, Walter-John Chitty, Gilbert Henaff   +4 more
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Carbide Faceting in Alloy 690: HRTEM Study

Materials Performance and Characterization, 2020
Abstract Alloy 690 (Unified Numbering System [UNS] No. 6690) in thermally treated (TT) condition is an advanced steam generator tubing material that offers high corrosion resistance with tailored carbide morphology and chromium concentration adjacent to the grain boundary.
Sumita Santra, S. V. Ramana Rao, K. Kapoor, D. Srivastava   +3 more
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Corrosion Performance of Alloy 690

CORROSION 1989, 1989
Abstract Alloy 690 steam generator tubing with continuous grain boundary carbides has consistently the lowest caustic stress corrosion rates at 332-343°C. This microstructure is effected by mill annealing at >1050°C and subsequent thermal treatment for 5-20 h at 725°C.
R. G. Aspden, T. F. Grand, D. L. Harrod
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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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Microstructural and corrosion aspects of alloy 690

British Corrosion Journal, 1999
AbstractUndissolved particles in alloy 690 were identified as titanium nitrides with a hexagonal crystal structure. On subsequent thermal treatment of the alloy these inclusions were found to act as preferred sites for the precipitation of chromium carbide.
R.S. Dutta, R. Tewari
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Microstructural characterization of inconel alloy 690

Proceedings, annual meeting, Electron Microscopy Society of America, 1988
Inconel 690 is a nickel-base superalloy which, because of its superior corrosion resistance, is being considered as a substitute for Inconel 600. The composition of Alloy 690 is nominally 30wt.%Cr-10wt.%Fe-0.3wt.%Ti-bal Ni. This alloy is generally used in the thermally treated condition: solution anneal in the range 1030-1120*C for ∼0.07-lh followed by
M. G. Burke, B. Z. Hyatt
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Effect of Deformation and Orientation on SCC of Alloy 690

CORROSION 2009, 2009
Abstract Alloy 690, of various microstructures and types of cold work, was tested in representative pressurized water reactor primary water at 340 and 360 °C. Intergranular cracking was observed on Alloy 690 at constant stress intensity factor (no cycling) and with “gentle” cyclic loading.
Peter L. Andresen, Martin M. Morra, John Hickling, Al Ahluwalia, John Wilson   +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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