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Corrosion of FeCrAl alloys used as fuel cladding in nuclear reactors
The safety of nuclear power plants has put forward new requirements for the corrosion
resistance of fuel cladding with the advancement of industrialization. FeCrAl alloys are …
resistance of fuel cladding with the advancement of industrialization. FeCrAl alloys are …
Review on synergistic damage effect of irradiation and corrosion on reactor structural alloys
H Liu, GH Lei, HF Huang - Nuclear Science and Techniques, 2024 - Springer
The synergistic damage effect of irradiation and corrosion of reactor structural materials has
been a prominent research focus. This paper provides a comprehensive review of the …
been a prominent research focus. This paper provides a comprehensive review of the …
Combined dual-exposure test and DFT investigations into effects of interstitial hydrogen on oxide film of Alloy 600 in high temperature water
The influence of interstitial hydrogen (H i) in the oxide film of Alloy 600 was investigated
using in-situ H charging via dual-exposure test and DFT calculations. H charging modified …
using in-situ H charging via dual-exposure test and DFT calculations. H charging modified …
Hydrogen charging effects on the alternation of oxide film formed on Ni, Cr and Alloy 690 in high-temperature water
The effects of hydrogen charging on the oxide film of Ni, Cr and Alloy 690 in high-
temperature water were studied. Hydrogen was charged to the specimen during …
temperature water were studied. Hydrogen was charged to the specimen during …
Effect of polyacrylic acid on the corrosion behavior of Alloy 690 in pressurized water reactor secondary water
The effect of polyacrylic acid (PAA) on the corrosion behavior of Alloy 690 in simulated
pressurized water reactor secondary water was investigated. The duplex oxide film structure …
pressurized water reactor secondary water was investigated. The duplex oxide film structure …
[HTML][HTML] A facility for studying corrosion via in-situ Raman spectroscopy
VS Ramsundar, K Daub, SY Persaud… - Journal of Nuclear …, 2024 - Elsevier
Several in-core components in nuclear power systems are exposed to high-temperature
water in the presence of radiation fields. The dynamic effect of radiation and water chemistry …
water in the presence of radiation fields. The dynamic effect of radiation and water chemistry …
Isothermal oxidation behaviour of TiAl alloys prepared by spark plasma sintering with the addition of Gd under water vapour at 900° C
X Liu, H Sun, X Jiang, R Liu, W Yan, S Chen, L Wang - Intermetallics, 2023 - Elsevier
In this paper, dense TiAl-xGd alloys with multiple compositions were prepared by spark
plasma sintering (SPS) technique, and isothermal oxidation tests were carried out at 900° C …
plasma sintering (SPS) technique, and isothermal oxidation tests were carried out at 900° C …
Microstructural evolution and corrosion behaviour of thermally aged dissimilar metal welds of low-alloy steel and nickel-based alloy
The influences of thermal aging on the microstructure, mechanical properties, and corrosion
resistance of two different Ni-based weld metal/low-alloy steel dissimilar metal weld fusion …
resistance of two different Ni-based weld metal/low-alloy steel dissimilar metal weld fusion …
Cyclic oxidation behaviour of Co/Si co-doped β-NiAl coating on nickel based superalloys
X Meng, P Yuwen, W Shao, W Qu, C Zhou - Corrosion Science, 2018 - Elsevier
Co/Si co-doped β-NiAl coating on nickel based superalloys was prepared using pack
cementation method. Microstructure and cyclic oxidation behaviour of the coating were …
cementation method. Microstructure and cyclic oxidation behaviour of the coating were …
Monte Carlo simulation of stress corrosion cracking in welded metals
Stress corrosion cracking (SCC) behavior in welded metals is strongly affected their
microstructures because the metals have complicated microstructures with broad grain size …
microstructures because the metals have complicated microstructures with broad grain size …