Formation of pure zirconium islands inside c-component loops in high-burnup fuel cladding
Artikel i vetenskaplig tidskrift, 2024
High-burnup Zr-based nuclear fuel claddings exhibit accelerated irradiation growth, corrosion and hydrogen pick-up, all correlated with the emergence of c-component dislocation loops. We made use of sub-nm-resolution atom probe tomography to characterize the nanoscale chemistry of c-loops in fuel cladding from boiling water reactor operation. We found segregation of Fe, Ni and Sn to dislocation lines and depletion of Sn and O inside the loops, resulting in nearly pure Zr islands. We also observed nucleation of suboxide inside one c-loop, pointing to a possible mechanism of accelerated in-reactor corrosion. Such Zr-islands might also promote hydride precipitation and associated degradation.
Zr-alloys
Dislocations
Nuclear fuel cladding
Irradiation-induced damage
Segregation
Atom probe tomography
Författare
David Mayweg
Chalmers, Fysik, Mikrostrukturfysik
Johan Eriksson
Chalmers, Kemi och kemiteknik, Energi och material
Chalmers, Fysik, Mikrostrukturfysik
Mohammad Sattari
Chalmers, Fysik, Mikrostrukturfysik
Gustav Sundell
ESAB
Chalmers, Kemi och kemiteknik, Tillämpad kemi
Magnus Limbäck
Westinghouse Electric Company
Itai Panas
Chalmers, Kemi och kemiteknik, Energi och material
Hans-Olof Andrén
Chalmers, Fysik, Mikrostrukturfysik
Mattias Thuvander
Chalmers, Fysik, Mikrostrukturfysik
Journal of Nuclear Materials
0022-3115 (ISSN)
Vol. 597 155116Ämneskategorier
Oorganisk kemi
Energiteknik
Materialkemi
DOI
10.1016/j.jnucmat.2024.155116