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High-temperature oxidation resistance and self-healing behavior of Cr2AlC MAX phase coating on Zircaloy-4

Tang, Chongchong; Steinbrueck, Martin ORCID iD icon; Grosse, Mirco; Ulrich, Sven; Stueber, Michael; Seifert, Hans Juergen

Abstract (englisch):

Zirconium-based alloys are currently utilized as fuel cladding and structural components in
commercial light water reactors due to their low thermal neutron absorption cross section, good
mechanical properties and reasonable corrosion resistance during operation conditions. One
undesirable feature of zirconium-based alloy cladding is their extremely fast oxidation kinetics with
high-temperature steam during loss of cooling accidents (LOCA). A considerable amount of heat and
hydrogen gas is produced by the reaction of zirconium and steam. The claddings undergo severe
degradation and hydrogen explosion can occur, followed by subsequent release of highly-radioactive
fission products to the environment like during the nuclear accidents at the Fukushima Daiichi
Nuclear Power Plant in 2011.
One strategy to improve the accident tolerance of the state-of-the-art zirconium-based alloy fuel
claddings is to coat the outer surface with an oxidation resistant coating. This solution promises the
elimination of corrosion degradation during normal operation, as well as significant reduced
oxidation kinetics with steam during off-normal conditions. ... mehr

Zugehörige Institution(en) am KIT Institut für Angewandte Materialien – Angewandte Werkstoffphysik (IAM-AWP)
Publikationstyp Vortrag
Publikationsjahr 2017
Sprache Englisch
Identifikator KITopen-ID: 1000076454
HGF-Programm 32.02.11 (POF III, LK 01) Auslegungsüberschreitende Störfälle
Veranstaltung 23rd International QUENCH Workshop, Karlsruhe Institute of Technology, Karlsruhe, Germany, 17.-19.10.2017
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