Transmission Kikuchi diffraction in a scanning electron microscope: A review

GC Sneddon, PW Trimby, JM Cairney - Materials Science and Engineering …, 2016 - Elsevier
Transmission Kikuchi diffraction (TKD), also known as transmission electron backscatter
diffraction (t-EBSD), has received significant interest for the characterisation of …

[PDF][PDF] 5.03 corrosion of zirconium alloys

TR Allen, RJM Konings, AT Motta - Comprehensive nuclear materials, 2012 - nuce.psu.edu
Zirconium alloys are widely used for fuel cladding and in pressure tubes, fuel channels
(boxes), and fuel spacer grids in almost all water-cooled reactors: light water reactors such …

Corrosion of Zircaloy-4, Zr-1Nb and FeCrAl alloys in deaerated water at 330 C and 14 MPa: Superior corrosion resistance and corrosion mechanism of FeCrAl alloy by …

G Jiang, D Xu, Y Wei, H Liu, L Liu, W Kuang - Chemical Engineering …, 2023 - Elsevier
After the Fukushima explosion, the research and development of accident tolerant fuel (ATF)
cladding has become a hot spot in the nuclear field. In this work, corrosion behavior of …

Oxide formation mechanism of a corrosion-resistant CZ1 zirconium alloy

J Hu, W Lin, Q Lv, C Gao, J Tan - Journal of Materials Science & …, 2023 - Elsevier
Tailoring microstructure and microchemistry by altering elemental compositions and
thermomechanical treatment parameters enables superior corrosion performance in …

Hydrogen pickup during oxidation in aqueous environments: The role of nano-pores and nano-pipes in zirconium oxide films

J Hu, J Liu, S Lozano-Perez, CRM Grovenor… - Acta Materialia, 2019 - Elsevier
Oxidation of metals by water generates hydrogen which can enter the solid causing serious
degradation of its mechanical properties and may also influence the corrosion rate. The …

Mechanism of the α-Zr to hexagonal-ZrO transformation and its impact on the corrosion performance of nuclear Zr alloys

J Liu, H Yu, P Karamched, J Hu, G He, D Goran… - Acta Materialia, 2019 - Elsevier
Displacive transformations have been widely reported in metals, alloys and ceramics, but
rarely reported to be important in the aqueous corrosion of alloys. We report here our …

Effect of micro-arc oxidation on fretting wear behavior of zirconium alloy exposed to high temperature water

P Lai, H Zhang, L Zhang, Q Zeng, J Lu, X Guo - Wear, 2019 - Elsevier
Flow-induced vibrations can result in fretting wear damage to the surfaces of clad fuel rods
(tubes) against their supports in nuclear power plants. One possible solution to this problem …

Effect of temperature on the fretting wear behavior of Cr-coated Zircaloy cladding in high-temperature pressurized water

J Wang, H Li, Z Li, Y Lei, Q Ren, Y Jiao, Z Cai - Journal of Nuclear Materials, 2023 - Elsevier
Cr-based coatings are promising candidates to protect the claddings on accident-tolerant
fuel (ATF) rods in pressurized water reactors (PWRs). In this study, the effect of water …

[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 …

The correlation between tetragonal phase and the undulated metal/oxide interface in the oxide films of zirconium alloys

J Liao, Z Yang, S Qiu, Q Peng, Z Li, J Zhang - Journal of Nuclear Materials, 2019 - Elsevier
The transition mechanism is of significance to the corrosion behavior of zirconium alloys.
Two important phenomena may be the causes of transition, which are the undulated wavy …