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Hydride morphology in zirconium cladding tubes after the SPIZWURZ bundle test. Part I: analysis of experimental data

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

Abstract (englisch):

The SPIZWURZ bundle test was carried out at the LICAS facility at Karlsruhe Institute of Technology. The test involved a bundle of 21 unirradiated hydrogenated cladding tubes (Zircaloy-4, opt. ZIRLO™ and Duplex DX-D4) which were subjected to an internal gas pressure and slow cooling for 250 days simulating the dry storage conditions of spent nuclear fuel. The following hydride morphology metrics were measured after the test: radial hydride fraction; hydride continuity coefficient; hydride length (mean and maximum, and their statistical distributions and densities); and number density. Hydrides in Zircaloy-4 have a higher tendency to reorientation, higher connectivity and are 2–3 times shorter (in both maximal and mean length) than those in opt. ZIRLO™. The evolution of hydride morphology in DX-D4 is mainly characterized by diffusional redistribution of hydrides from the substrate to the liner and the liner/substrate interface. Several samples exhibited local anomalies in hydride morphology, which can cause significant local embrittlement. The main experimental results are in good agreement with earlier published data. The supplementary materials include records of all the thermocouples and pressure sensors, which can be used to simulate the SPIZWURZ bundle test in detail.


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Originalveröffentlichung
DOI: 10.1016/j.jnucmat.2025.156250
Zugehörige Institution(en) am KIT Institut für Angewandte Materialien – Angewandte Werkstoffphysik (IAM-AWP)
Publikationstyp Zeitschriftenaufsatz
Publikationsmonat/-jahr 10.2026
Sprache Englisch
Identifikator ISSN: 0022-3115
KITopen-ID: 1000186349
HGF-Programm 32.11.01 (POF IV, LK 01) Nuclear Waste Disposal
Weitere HGF-Programme 32.12.01 (POF IV, LK 01) Design Basis Accidents and Materials Research
Erschienen in Journal of Nuclear Materials
Verlag Elsevier
Band 619
Seiten 156250
Vorab online veröffentlicht am 28.10.2025
Schlagwörter Zirconium alloys, Hydride morphology, Hydride embrittlement, Dry storage, Spent nuclear fuel, Hydride reorientation
Nachgewiesen in OpenAlex
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