Results 11 to 20 of about 1,567 (242)
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 +2 more
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EFFECTS OF IRRADIATION ON THERMAL CONDUCTIVITY OF ALLOY 690 AT LOW NEUTRON FLUENCE
Nuclear Engineering and Technology, 2013 Alloy 690 has been selected as a steam generator tubing material for SMART owing to a near immunity to primary water stress corrosion cracking. The steam generators of SMART are faced with a neutron flux due to the integrated arrangement inside a reactor
Woo Seog Ryu, Sang Bok Ahn
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Effect of Microstructure Evolution on Thermal Conductivity of Alloy 690 [PDF]
TeshugangThe effect of microstructure evolution on thermal conductivity of alloy 690 electrode was studied according to the working conditions of electrode materials in Joule furnace.
Feng Han +5 more
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Ultrasonic vibration assisted gas tungsten arc welding of Inconel 690 alloy: Ultrasonic effect to refine grains and improve mechanical properties [PDF]
Ultrasonics SonochemistryThe Inconel 690 alloy is widely used in the manufacturing of nuclear equipment, such as pipe welding for steam generators (SG) and pressure vessels, due to its excellent high-temperature strength, corrosion resistance, and thermal stability.
Yunhao Xia +3 more
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Nuclear Engineering and Technology, 2022 Alloy 690 tubing has been shown to be highly resistant to primary water stress corrosion cracking (PWSCC). Nevertheless, predicting the failure by PWSCC in Alloy 690 SG tubes is indispensable.
Dayu Fajrul Falaakh, Chi Bum Bahn
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Microstructure dependence on mechanical behavior of Alloy 690 [PDF]
AIP Conference Proceedings, 2016 The influence of microstructure on the mechanical behavior of Alloy 690 was studied in this work. The microstructures with and without carbide precipitation were obtained through solution annealing and/or thermal treatment. The mechanical impact tests on different microstructure at a high strain rate of 5.3×103/s were performed by compressive split ...
X. M. Pan +3 more
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Nuclear Engineering and Technology, 2021 By using miniature SENB specimens, the fracture properties of the materials in the region of welded metal, 321 stainless steel heat affected zone, 690 alloy heat affected zone of 321/690 dissimilar metal girth welded joints were tested.
Bao Chen +5 more
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Frontiers in Materials, 2022 In order to find the low-alloy high-strength steel welded with the strongest corrosion resistance, the corrosion resistance of HSAL weld metal was studied by considering different alloy compositions. Corrosion resistance of alloy compositions of 460, 690,
Liang Song +5 more
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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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