Results 211 to 220 of about 1,533 (254)
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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   +3 more
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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, 2006
The 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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Corrosion behavior of Alloy 690 in aerated supercritical water

Corrosion Science, 2013
Abstract 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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Carbide Precipitation and SCC Behavior of Inconel Alloy 690

Corrosion, 1988
The 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, 2014
Metal 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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Corrosive Characteristics of Alloy 690 Investigated by Electrochemical Analysis

ICPTT 2013, 2013
Pitting corrosion is one of the major damage forms for Alloy 690, which is one of the usual used materials in SG tubing. It is very important to understand corrosion behavior deeply to ensure the structural integrity. In this paper, the electrochemical experiments are used to analyze the corrosion characters of Alloy 690.
Jun Hu   +4 more
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Intergranular corrosion resistance of nickel-based alloy 690 weldments

Corrosion Science, 2010
Abstract This study focused on the temperature distributions and thermal histories of alloy 690 weldments, as well as the residual stress, grain boundary character distribution, degree of sensitization, and carbide precipitation, to evaluate the combined effects of these factors on the intergranular corrosion resistance of the weldments.
Hwa Teng Lee, Jia Lin Wu
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