Effects of alloying elements (Sn, Cr and Cu) on second phase particles in Zr-Sn-Nb-Fe-(Cr, Cu) alloys

B Tao, R Qiu, Y Zhao, Y Liu, X Tan, B Luan… - Journal of Alloys and …, 2018 - Elsevier
In this investigation, the effects of Sn, Cr, and Cu on the precipitation of the second-phase
particles (SPPs) in Zr–Sn–0.3 Nb–0.3 Fe–(Cr, Cu) alloys were investigated. Scanning …

Oxidation behaviour of zirconium alloys and their precipitates–A mechanistic study

C Proff, S Abolhassani, C Lemaignan - Journal of nuclear materials, 2013 - Elsevier
The precipitate oxidation behaviour of binary zirconium alloys containing 1wt.% Fe, Ni, Cr or
0.6 wt.% Nb was characterised in TEM on FIB prepared transverse sections of the oxide and …

[HTML][HTML] The corrosion of Zr (Fe, Cr) 2 and Zr2Fe secondary phase particles in Zircaloy-4 under 350 C pressurised water conditions

K Annand, M Nord, I MacLaren, M Gass - Corrosion Science, 2017 - Elsevier
Abstract Using Scanning Transmission Electron Microscopy (STEM) coupled with Dual
Electron Energy Loss Spectroscopy (DualEELS) and scanned diffraction, the corrosion and …

Origin and effect of lateral cracks in oxide scales formed on zirconium alloys

P Tejland, HO Andrén - Journal of nuclear materials, 2012 - Elsevier
Two varieties of Zircaloy-2, with different second phase particle (SPP) size distributions and
different corrosion resistance, were oxidized in a steam autoclave. Transmission electron …

Characterization of zirconium oxides part I: Raman map** and spectral feature analysis

CM Efaw, JL Vandegrift, M Reynolds… - Nuclear Materials and …, 2019 - Elsevier
Raman map** of sectioned zirconium cladding oxides was performed to analyze different
spectral features before and after breakaway, as well as between zirconium and its alloys Zr …

The influence of second phase particles on the crack formation in oxide films formed on zirconium alloys

J Huang, M Yao, C Gao, X Liang, J Peng, J Zhang… - Corrosion …, 2015 - Elsevier
The oxidation behavior of second phase particles (SPPs) and the formation of cracks in
oxide films on Zr-0.93 Sn-0.82 Nb-0.17 Fe-0.019 S alloy in lithiated water with 0.01 M LiOH …

On the oxidation behavior of (Zr, Nb) 2Fe under simulated nuclear reactor conditions

J Hu, L Yang, G Cao, Y Yun, G Yuan, Q Yue, G Shao - Corrosion Science, 2016 - Elsevier
The corrosion behavior of Zr alloys was affected by second phases, especially by those
containing Fe and Nb. Ti 2 Ni-type (Zr, Nb) 2 Fe compound was melted and exposed to H 2 …

Effect of Sn on stacking fault energies in zirconium and its hydrides

P Chakraborty, I Mouton, B Gault, A Tehranchi… - Physical Review …, 2024 - APS
Hydrogen embrittlement in Zr-alloy fuel cladding is a primary safety concern for water-based
nuclear reactors. Here we investigated the stabilization of planar defects within the forming …

Grain morphology and crystal structure of pre-transition oxides formed on Zircaloy-4

W Gong, H Zhang, Y Qiao, H Tian, X Ni, Z Li, X Wang - Corrosion science, 2013 - Elsevier
Grain morphology and crystal structure of pre-transition oxides formed on a Zircaloy-4 alloy
were investigated. The results show that monoclinic columnar grains align tightly in inner …

The corrosion resistance of Zr-0.7 Sn-1Nb-0.2 Fe-xCu-xGe alloys in 360° C lithiated water

J Zhang, Y Hu, J Huang, L Tu, M Yao, B Zhou - Corrosion Science, 2016 - Elsevier
The corrosion behavior of Zr-0.7 Sn-1Nb-0.2 Fe-xGe-xCu alloys (x= 0, 0.05, 0.1, 0.2, wt%)
and the microstructures of the oxide film formed on the specimens were investigated in …