Results 31 to 40 of about 418,826 (248)
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, 2019 Low-cycle fatigue (LCF) tests were performed for Alloy 690 and 316 SS in a simulated pressurized water reactor (PWR) environment. Alloy 690 showed about twice longer LCF life than 316 SS at the test condition of 0.4% amplitude at strain rate of 0.004%/s.
Junjie Chen +5 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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, 2023 Inconel 690 alloy is widely used in nuclear power, petrochemical, aerospace, and other fields due to its excellent high-temperature mechanical properties and corrosion resistance.
Shuo Shang +5 more
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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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Advances in Materials Science and Engineering, 2015 This work clarifies the effect of surface modifications on the corrosion rate of Alloy 690, a nickel-based alloy for steam generator tubes, under the simulated test conditions of the primary water chemistry in nuclear power plants. The surface stress was
Kyung Mo Kim +3 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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