Results 11 to 20 of about 30,108 (299)
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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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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Influence of oxide films on primary water stress corrosion cracking initiation of alloy 600 [PDF]
, 2006 In the present study alloy 600 was tested in simulated pressurised water reactor (PWR) primary water, at 360 °C, under an hydrogen partial pressure of 30 kPa. These testing conditions correspond to the maximum sensitivity of alloy 600 to crack initiation.
Andrieu, Eric +5 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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Chemical Evolution in the Substrate due to oxidation: A Numerical Model with Explicit Treatment of Vacancy Fluxes [PDF]
, 2008 To get a better understanding of oxidation behavior of Ni-base alloys in PWR primary water, a numerical model for oxide scale growth has been developed. The final aim of the model is to estimate the effects of possible changes of experimental conditions.
Bertrand, Nathalie +5 more
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Atomic simulations of nanoscale friction behavior in polycrystalline alloy 690
Materials Research Express, 2022 Fretting wear is one of the most important failure forms of alloy 690 heat exchanger tubes in nuclear power plants. The key to understanding the fretting wear of alloys lies in the friction process, especially at the atomic scale.
Ai-Long Zhou +4 more
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Shear enhanced heterogeneous nucleation in some Mg- and Al- alloys [PDF]
, 2009 Intensive shearing was applied to alloy melts at temperatures above their liquidus by using a twinscrew mechanism. The sheared melt was then cast into a TP1 mould for microstructural examination.
Fan, Z +7 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 +4 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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