Results 261 to 270 of about 30,108 (299)

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, Hee-Sang Shim, Myung Ji Seo, Do Haeng Hur   +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, Ming Shuai, Haipeng Teng, Lijun Yu, Maosheng Zheng   +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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Development of U-Bending Technology for Alloy 690 Tubes

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovatio, 2012
Steam generator installed with heat-transfer tubes (HTT) is an enormous heat exchanger that uses heat energy derived from a reactor to generate steam. The steam drains into turbine generator of an nuclear power plant, and plays an important role in producing electric power in nuclear power plant.
Tae-Wan Ku, Woo-Sung Jin, Jin-Hyun Cha, Won-Seok Kim   +3 more
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Origins of Negative Strain Rate Dependence of Stress Corrosion Cracking Initiation in Alloy 690, and Intergranular Crack Formation in Thermally Treated Alloy 690

Metallurgical and Materials Transactions A, 2016
We show that enhanced stress corrosion cracking (SCC) initiation in cold-rolled Alloy 690 with decreasing strain rate is related to the rate of short-range ordering (SRO) but not to the time-dependent corrosion process. Evidence for SRO is provided by aging tests on cold-rolled Alloy 690 at 623 K and 693 K (350 °C and 420 °C), respectively, which ...
Young Suk Kim, Sung Soo Kim
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Pitting corrosion of Alloy 690 in thiosulfate-containing chloride solutions

Journal of Nuclear Materials, 2000
Abstract The effects of thiosulfate ion and solution pH on pitting corrosion of Alloy 690 in chloride solution were explored. Potentiodynamic polarization measurements were conducted to evaluate pitting corrosion susceptibility of Alloy 690 in these environments.
Wen-Ta Tsai, Tsung-Feng Wu
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Characterization of SCC Initiation Precursors in Cold-Worked Alloy 690

CORROSION 2017, 2017
Abstract Although highly cold-worked UNS N06690 has been shown to be susceptible to stress corrosion crack growth in pressurized water reactor primary water, it is unclear whether stress corrosion cracking initiation occurs under constant load test conditions.
Karen Kruska, Ziqing Zhai, Stephen M Bruemmer   +2 more
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