Results 31 to 40 of about 30,108 (299)
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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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
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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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Embrittlement of Hydrogen-Charged Alloy 690 Single Crystal.
Journal of Society of Materials Engineering for Resources of Japan, 1995 The effects of charging temperature and time on the embrittlement of cathodically hydrogen-charged specimens were investigated by tensile test and scanning electron microscopic studies on Alloy 690 single crystals with ‹100› tensile axis. Many cracks on the specimen surface were observed along {100} traces.
Kenzo KON +3 more
openaire +2 more sources
Bandgap engineering in semiconductor alloy nanomaterials with widely tunable compositions [PDF]
, 2017 Over the past decade, tremendous progress has been achieved in the development of nanoscale semiconductor materials with a wide range of bandgaps by alloying different individual semiconductors.
Dou, L, Peidong Yang, CZN, Yang, P
core +1 more source
Cracking Behavior In Inconel Alloy 690: Role Of The Environment In High Temperature H2-Supersaturated Steam [PDF]
, 2004 Nickel base alloys 600 and 690 have found widespread applications in nuclear reactor steam generators. In particular, alloy 690 with a major element composition of typically Ni-30Cr-9Fe, has shown an apparent improvement in performance when compared with
Ferguson, J. B., Lopez, H. F.
core
Advanced Functional Materials, EarlyView.This study investigates H4TBAPy‐based metal–organic frameworks (MOFs) ‐ NU‐1000, NU‐901, SrTBAPy, and BaTBAPy ‐ for multiphoton absorption (MPA) performance. It observes topology‐dependent variations in the 2PA cross‐section, with BaTBAPy exhibiting the highest activity.
Simon N. Deger +10 more
wiley +1 more source
Creep strain modeling for alloy 690 SG tube material based on modified theta projection method
Nuclear Engineering and Technology, 2022 During a severe accident, steam generator (SG) tubes undergo rapid changes in the pressure and temperature. Therefore, an appropriate creep model to predict a short term creep damage is essential.
Seongin Moon +5 more
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Advanced Functional Materials, EarlyView.The citric acid/urea (CA‐Urea) precursor system offers a versatile, scalable route to carbon dots with tunable luminescence and multifunctionality. Mechanistic insights into precursor chemistry and reaction parameters have enabled doping, surface modification, and hybridization strategies, yielding CDs for luminescent devices, sensing, catalysis ...
Yupeng Liu +10 more
wiley +1 more source
Corrosion and Materials DegradationPassive films that form on Alloy 600 and Alloy 690 during four hours in simulated Primary Water (PW) of Pressurized Water Nuclear Reactors (PWRs) at 320 °C were investigated by in situ surface-enhanced Raman spectroscopy (SERS).
Feng Wang, Thomas M. Devine
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