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High-temperature oxidation and quenching of chromium-coated zirconium alloy ATF cladding tubes with and w/o pre-damage

Steinbrück, M. ORCID iD icon; Stegmaier, U.; Große, M.; Czerniak, L.; Lahoda, E.; Daum, R.; Yueh, K.

Abstract (englisch):

Chromium-coated zirconium alloys are one of the promising candidates for accident-tolerant fuel cladding (ATF) tubes for light water reactors (LWRs). In this study, the high temperature oxidation and degradation of two types of Cr coatings (cold spray and physical vapor deposition) with and without pre-damage by scratches were investigated on prototype rod segment samples filled with ZrO 2 pellets and tightly sealed with welded end caps. Isothermal tests at 1100 and 1200 °C were terminated by quenching with water; transient tests were performed up to 150 0–160 0 °C until complete coating failure. The positive effect of both types of Cr coatings was observed in all tests. Pre-damaged specimens showed only locally increased oxidation of the scratched zone, but no negative effects on the adjacent Cr coating. The behavior of the two types of coatings is compared and the degradation mechanisms are discussed based on hydrogen release data, extensive metallographic post-test examinations, and the current state of global research.


Postprint §
DOI: 10.5445/IR/1000141511
Veröffentlicht am 01.03.2023
Originalveröffentlichung
DOI: 10.1016/j.jnucmat.2021.153470
Scopus
Zitationen: 56
Web of Science
Zitationen: 47
Dimensions
Zitationen: 54
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Angewandte Materialien – Angewandte Werkstoffphysik (IAM-AWP)
Publikationstyp Zeitschriftenaufsatz
Publikationsmonat/-jahr 02.2022
Sprache Englisch
Identifikator ISSN: 0022-3115
KITopen-ID: 1000141511
HGF-Programm 32.12.02 (POF IV, LK 01) Beyond Design Basis and Emergency Management
Erschienen in Journal of nuclear materials
Verlag Elsevier
Band 559
Seiten 153470
Nachgewiesen in Web of Science
Dimensions
Scopus
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