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A two-stage nucleation model with incubation effect for hydride precipitation in zirconium alloys

Kolesnik, Mikhail ORCID iD icon 1; Stuckert, Juri ORCID iD icon 1; Große, Mirco 1
1 Institut für Angewandte Materialien – Angewandte Werkstoffphysik (IAM-AWP), Karlsruher Institut für Technologie (KIT)

Abstract (englisch):

Hydrogen accumulates in zirconium alloy cladding tubes during reactor operation as a by-product of waterside corrosion. When its concentration exceeds the solid solubility (TSS), plate-like hydrides precipitate, which may lead to embrittlement. The severity of embrittlement depends on hydrogen concentration and hydride morphology, including orientation, characteristic length, and connectivity of the hydride network. While hydrogen uptake is mainly governed by alloy composition and operating conditions, hydride morphology is strongly influenced by the post-operation thermal and mechanical history. Thermomechanical cycles during handling and storage can cause repeated dissolution and reprecipitation, promoting long, radially oriented hydrides that facilitate brittle crack propagation. Consequently, hydride-induced embrittlement becomes critical during handling and dry storage of spent nuclear fuel. Accurate prediction of hydride morphology requires a proper description of nucleation kinetics. In our previous approach, nucleation was modeled using classical theory; however, validation against recent experimental data showed excessive sensitivity to uncertainties in hydrogen concentration and solubility under certain thermal conditions. ... mehr


Verlagsausgabe §
DOI: 10.5445/IR/1000198849
Veröffentlicht am 05.11.2026
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Angewandte Materialien – Angewandte Werkstoffphysik (IAM-AWP)
Publikationstyp Proceedingsbeitrag
Publikationsmonat/-jahr 10.2026
Sprache Englisch
Identifikator KITopen-ID: 1000198849
HGF-Programm 32.12.01 (POF IV, LK 01) Design Basis Accidents and Materials Research
Erschienen in Proceedings of TopFuel 2026: Nuclear Reactor Fuel Performance Conference
Veranstaltung TopFuel 2026: Nuclear Reactor Fuel Performance Conference (2026), Tokio, Japan, 12.10.2026 – 15.10.2026
Verlag Atomic Energy Society of Japan
Seiten 403–412
Projektinformation SPIZWURZ (BMWE, 1501609B)
Bemerkung zur Veröffentlichung Paper No. 141
Schlagwörter hydride embrittlement, zirconium alloys, hydride morphology, spent nuclear fuel, dry storage
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