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Oxidation and hydrogen uptake during high-temperature reaction of zirconium alloys in steam-nitrogen mixtures

Steinbrück, Martin ORCID iD icon; Grosse, Mirco

Abstract (englisch):

Zirconium alloys are worldwide used as cladding materials for fuel in light water reactors with excellent performance during operation due to their low neutron absorption and very good mechanical and corrosion properties at operational conditions. However, at higher temperatures relevant for nuclear accident scenarios the oxidation of zirconium becomes severe, thus impairing the barrier effect of the claddings against the release of fission products and being the main source for the release of hydrogen and chemical heat. A significantly accelerating effect of nitrogen on the oxidation kinetics has been observed in recent studies on air ingress scenarios during severe accidents in reactors and spent fuel pools over a wide range of boundary conditions [1-5].
The presented poster summarizes results on the oxidation of Zircaloy-4 in steam-nitrogen atmospheres at temperatures between 600°C and 1200°C. Experiments were conducted using thermo-gravimetry (TG) under gas compositions between 0 and 100 vol% nitrogen including 0.1 and 90 vol% and total gas flow rates of 0.278 mol/h. The strongest effect of nitrogen on the oxidation kinetics was seen at 800-1000°C with higher kinetics in all mixtures compared to the annealing in pure steam. ... mehr

Zugehörige Institution(en) am KIT Institut für Angewandte Materialien – Angewandte Werkstoffphysik (IAM-AWP)
Publikationstyp Poster
Publikationsjahr 2016
Sprache Englisch
Identifikator KITopen-ID: 1000062547
HGF-Programm 32.02.11 (POF III, LK 01) Auslegungsüberschreitende Störfälle
Veranstaltung 18th International Symposium on Zirconium in Nuclear Industry, 15-19 May 2016, Hilton Head Island, SC, USA
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