[HTML][HTML] Cold sprayed Cr-coating on Optimized ZIRLO™ claddings: the Cr/Zr interface and its microstructural and chemical evolution after autoclave corrosion testing
A Fazi, K Stiller, HO Andrén, M Thuvander - Journal of Nuclear Materials, 2022 - Elsevier
Abstract Cr-coated Optimized ZIRLO™ cladding material fabricated with the cold-spray
deposition process is studied. Microstructure and chemistry of this material are investigated …
deposition process is studied. Microstructure and chemistry of this material are investigated …
APT and TEM study of behaviour of alloying elements in neutron-irradiated zirconium-based alloys
In this study, APT and TEM analyses were used to characterise two Zr-based alloys neutron-
irradiated to 13.7 dpa. The high spatial and chemical resolution of these techniques has …
irradiated to 13.7 dpa. The high spatial and chemical resolution of these techniques has …
[HTML][HTML] Focused Ion Beam induced hydride formation does not affect Fe, Ni, Cr-clusters in irradiated Zircaloy-2
D Mayweg, J Eriksson, O Bäcke, AJ Breen… - Journal of Nuclear …, 2023 - Elsevier
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 …
Solute concentrations in the matrix of zirconium alloys studied by atom probe tomography
J Eriksson, D Mayweg… - … on Zirconium in …, 2023 - asmedigitalcollection.asme.org
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 …
[HTML][HTML] Modeling of irradiation-induced microstructure evolution in Fe: Impact of Frenkel pair distribution
E Mansouri, P Olsson - Computational Materials Science, 2024 - Elsevier
This study investigated the irradiation-induced microstructure evolution in Fe, employing the
Creation-Relaxation Algorithm and different interatomic potentials. The influence of self …
Creation-Relaxation Algorithm and different interatomic potentials. The influence of self …
[HTML][HTML] Nanoscale chemistry of Zircaloy-2 exposed to three and nine annual cycles of boiling water reactor operation—an atom probe tomography study
J Eriksson, G Sundell, P Tejland, HO Andrén… - Journal of Nuclear …, 2022 - Elsevier
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 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 …
Advanced Microscopy and 3D Atom Probe on Irradiated BWR Structural Materials to Elucidate Hydrogen Pickup Mechanism
A Kucuk, S Yagnik, I Arimescu… - Zirconium in the …, 2023 - asmedigitalcollection.asme.org
High hydrogen pickup (HPU) and large scatter on HPU at high burnup/high exposure times
is observed for Zircaloy-2 (Zr-2), which is used as fuel cladding, fuel channels, water rods …
is observed for Zircaloy-2 (Zr-2), which is used as fuel cladding, fuel channels, water rods …
[HTML][HTML] Insights into the interfacial speciation of Ni in the corrosion layer of high burnup Zircaloy-2 cladding: A combined XRD, XAS, and LFDFT study
G Kuri, H Ramanantoanina, S Bhattacharya, J Bertsch… - Corrosion …, 2023 - Elsevier
This work reports atomic-scale experimental and modeling studies of the zirconium oxide
microstructure formed at the metal-oxide (M/O) interface, and the crystallography as well as …
microstructure formed at the metal-oxide (M/O) interface, and the crystallography as well as …
[HTML][HTML] Formation of pure zirconium islands inside c-component loops in high-burnup fuel cladding
D Mayweg, J Eriksson, M Sattari, G Sundell… - Journal of Nuclear …, 2024 - Elsevier
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 …