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[HTML][HTML] Focused Ion Beam induced hydride formation does not affect Fe, Ni, Cr-clusters in irradiated Zircaloy-2
Room temperature focused ion beam (FIB) milling is known to potentially promote the
formation of hydrides in zirconium and its alloys. We used atom probe tomography (APT) to …
formation of hydrides in zirconium and its alloys. We used atom probe tomography (APT) to …
[HTML][HTML] A multiscale study on the microstructure and hardening models of the irradiation defects on reactor pressure vessel steels: Modelling and experiment
P Lin, J Nie, W Cui, L He, Y Lu, S Cui - Journal of Materials Research and …, 2024 - Elsevier
Irradiation defects are known to impede the dislocation motion in irradiated reactor pressure
vessel (RPV) steels. However, consistent experimental studies of the respective irradiation …
vessel (RPV) steels. However, consistent experimental studies of the respective irradiation …
Creep-induced redistribution of alloying elements in CZ1 zirconium alloys
Introducing minor alloying elements is an effective strategy to improve the corrosion and
mechanical properties of zirconium alloys for nuclear applications. During in-reactor service …
mechanical properties of zirconium alloys for nuclear applications. During in-reactor service …
[HTML][HTML] Nanoscale chemistry of Zircaloy-2 exposed to three and nine annual cycles of boiling water reactor operation—an atom probe tomography study
Atom probe tomography was used in this work to study the metal close to the metal/oxide
interface in the zirconium alloy Zircaloy-2 exposed to three and nine annual cycles of …
interface in the zirconium alloy Zircaloy-2 exposed to three and nine annual cycles of …
An interesting oxidation-reduction phenomenon between the Zr (Cr, Fe) 2 Laves phase and Cr2O3 under high temperature
K Wei, J Wei, G Cao, G Cheng, W Li, J Hu, S Kano… - Corrosion …, 2025 - Elsevier
Abstract Studying Zr (Cr, Fe) 2 Laves phase oxidation is vital for deepening our
understanding of the oxidation mechanism of accident tolerant fuel (ATF) Cr-coated Zr and …
understanding of the oxidation mechanism of accident tolerant fuel (ATF) Cr-coated Zr and …
An atom probe study on the Fe distribution in Zr-based alloys with different Fe content under high fluence neutron irradiation
T Sawabe, T Sonoda - Journal of Nuclear Materials, 2022 - Elsevier
In the present study, atom probe tomography was used to investigate the relationship
between the distribution of Fe and other alloying elements and irradiation defects in …
between the distribution of Fe and other alloying elements and irradiation defects in …
[HTML][HTML] Formation of pure zirconium islands inside c-component loops in high-burnup fuel cladding
High-burnup Zr-based nuclear fuel claddings exhibit accelerated irradiation growth,
corrosion and hydrogen pick-up, all correlated with the emergence of c-component …
corrosion and hydrogen pick-up, all correlated with the emergence of c-component …
[PDF][PDF] Solute concentrations in the matrix of zirconium alloys studied by atom probe tomography
This work indicates that the matrix content of the alloying elements iron, chromium, and
nickel in as-produced commercial Zircaloy-2-type materials is lower than what has been …
nickel in as-produced commercial Zircaloy-2-type materials is lower than what has been …
The influence of hydrogen content on the Zr-4 alloy diffusion bonding joint: From experiments to molecular dynamics simulations
Y Wang, Y Li, Y Bai, Y Liu, Z Zhu, H Chen - Materials Today …, 2024 - Elsevier
Bonding the Zr-4 alloy in the high temperature can lead to many problems, for example grain
coarsening and large welding deformation resulting from high residual stresses …
coarsening and large welding deformation resulting from high residual stresses …
Unexpected {011¯ 1} pyramidal stacking faults in Zr (Fe, Cr) 2 secondary phase particle induced by the C15→ C14 Laves phase transformation in Zircaloy-4
W Guo, G Li, J Ren, M Ali, J Hu, Q Wang, F Yuan… - Scripta Materialia, 2023 - Elsevier
The formation mechanism of (01 1¯ 1) C14 pyramidal stacking faults (SFs) with a 8.6°
deflection to the SFs on (11 1¯) C15 planes of Zr (Fe, Cr) 2 secondary phase particle (SPP) …
deflection to the SFs on (11 1¯) C15 planes of Zr (Fe, Cr) 2 secondary phase particle (SPP) …