Results of Severe Fuel Damage Experiment QUENCH-14 with Advanced Rod Cladding M5®. (KIT Scientific Reports ; 7549)
Stuckert, J.
; Große, M.; Stegmaier, U.; Steinbrück, M.
; Große, M.; Stegmaier, U.; Steinbrück, M.
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.
| 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 |
| Nachgewiesen in | OpenAlex |
| Globale Ziele für nachhaltige Entwicklung |