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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, 2006The 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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Wear behavior of plasma nitrided inconel 690 alloy
AIP Conference Proceedings, 2019In 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 +3 more
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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, 2012Steam 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 +3 more
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Corrosive Characteristics of Alloy 690 Investigated by Electrochemical Analysis
ICPTT 2013, 2013Pitting 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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Low Cycle Fatigue of Alloy 690 in the PWR Environment
Volume 2: Design & AnalysisAbstract 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 +4 more
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The effect of thermomechanical processing on the creep behavior of Alloy 690
Materials Science and Engineering: A, 2008Abstract The effect of thermomechanical processing on the microstructure and elevated-temperature creep behavior of Alloy 690 was investigated. Commercially available sheet was subjected to four cycles of cold rolling to 25% deformation followed by annealing at 1000 °C for 1 h.
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