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Results of Severe Fuel Damage Experiment QUENCH-14 with Advanced Rod Cladding M5®. (KIT Scientific Reports ; 7549)

Stuckert, J. ORCID iD icon; Große, M.; Stegmaier, U.; Steinbrück, M. ORCID iD icon

Abstract:

The QUENCH experiments are to investigate the hydrogen release resulting from the water injection into an uncovered core of a Light Water Reactor as well as the high-temperature behavior of core materials. The QUENCH-14 experiment investigated the effect of M5® cladding material on bundle oxidation and core reflood, in comparison with the tests QUENCH-06 that used standard Zircaloy-4 and QUENCH-12 that used VVER E110-claddings.


Volltext §
DOI: 10.5445/KSP/1000018823
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Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Materialforschung (IMF)
Karlsruher Institut für Technologie (KIT)
Publikationstyp Forschungsbericht/Preprint
Publikationsjahr 2010
Sprache Englisch
Identifikator ISBN: 978-3-86644-535-2
urn:nbn:de:0072-188233
KITopen-ID: 1000018823
Reportnummer: KIT-SR 7549
HGF-Programm 32.22.11 (POF II, LK 01) Kernunfallanalysen(QUENCH, LIVE, DISCO)
Verlag KIT Scientific Publishing
Umfang XII, 164 S.
Schlagwörter severe accident management, reflood, bundle test, fuel element cladding oxidation, quenching
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