Results 21 to 30 of about 1,326,999 (268)
Journal of Materials Research and Technology, 2021 The precipitation characteristics of intergranular carbides generally have a significant impact on the microstructural homogeneity and properties of Alloy 690.
Xia Zhao +7 more
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Journal of Materials Research and Technology, 2022 In this study, in response to the requirement for a higher heat transfer efficiency of the small-scale nuclear power reactors, a novel material treatment method in the form of electromagnetic coupling treatments (EMCT) was studied and applied to improve ...
Qianwen Zhang +6 more
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Nuclear Engineering and Technology, 2021 The dislocation density in strain-hardened Alloy 690 was analyzed using scanning transmission electron microscopy (STEM) to study the relationship between the local plastic strain and susceptibility to primary water stress corrosion cracking (PWSCC) in ...
Sung-Woo Kim +2 more
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A Look Into The Process, Structure, Properties, and Performance of Inconel 690 [PDF]
, 2021 Inconel 690 (Alloy 690) is a high-chromium nickel super alloy. This alloy is used in many ways, mostly in a setting where corrosion is a concern. The alloy is very resistant to corrosion in an aqueous media as well as a high temperature atmosphere.
Camacho, Patrick +3 more
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Stress Corrosion Crack Initiation of Alloy 600 and Alloy 690 in Hydrogenated Supercritical Water. [PDF]
, 2015 Stress corrosion crack (SCC) initiation of highly resistant materials can be studied by conducting accelerated testing as long as there is no change in the cracking mechanism.
Moss, Tyler Elliot
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Archives of Metallurgy and Materials, 2017 This work aims to study the stress corrosion crack growth behavior of cold-rolled Alloy 690 in the primary water of a pressurized water reactor. Compared with Alloy 600, which shows typical intergranular cracking along high angle grain boundaries, the ...
Kim S.-W. +3 more
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Optimization of the Double Loop Electrochemical Potentiokinetic Reactivation Method for Detecting Sensitization of Nickel Alloy 690 [PDF]
, 2017 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 Alloy 690, may be a function of the alloy sensitization ...
Patricia Bozzano +11 more
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Fatigue Life Prediction of Steam Generator Tubes by Tube Specimens with Circular Holes
Metals, 2019 Heat exchangers manufactured from Inconel 690 tubes are widely used for steam generators in nuclear power plants. Inconel 690 tubes have suffered failures of fatigue fracture due to flow induced vibration.
Qiwei Wang +4 more
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Nuclear Engineering and Technology, 2019 This paper provides further validation of the burst pressure estimation equations for multiple axial surface cracked steam generator tubes, recently proposed by the authors based on analytical local collapse load approach against systematic FE damage ...
Ji-Seok Kim +3 more
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PWSCC growth rate model of alloy 690 for head penetration nozzles of Korean PWRs
Nuclear Engineering and Technology, 2019 This work aims to establish a model of a primary water stress corrosion crack growth rate of Alloy 690 material for the head penetration nozzles of Korean pressurized water reactors.
Sung-Woo Kim +3 more
doaj +1 more source