Results of Severe Fuel Damage Experiment QUENCH-15 with ZIRLO cladding tubes. (KIT Scientific Reports ; 7576)
Stuckert, J.
; Große, M.; Stegmaier, U.; Steinbrück, M.
; Große, M.; Stegmaier, U.; Steinbrück, M.
Abstract:
The QUENCH-15 experiment investigated the effect of ZIRLO™ cladding material on bundle oxidation and core reflood from maximum bundle temperature of 2150 K. The molten cladding metal at the hottest elevation was localized between outer and inner oxide layers. The analyses of the QUENCH-15 test data indicate a similar global bundle behavior as of bundle experiments QUENCH-14 (M5® claddings) and QUENCH-06 (Zircaloy-4 claddings).
| Zugehörige Institution(en) am KIT | Institut für Angewandte Materialien – Angewandte Werkstoffphysik (IAM-AWP) Institut für Angewandte Materialien - Werkstoffprozesstechnik (IAM-WPT) Institut für Materialforschung (IMF) Karlsruher Institut für Technologie (KIT) |
| Publikationstyp | Forschungsbericht/Preprint |
| Publikationsjahr | 2011 |
| Sprache | Englisch |
| Identifikator | ISBN: 978-3-86644-670-0 urn:nbn:de:0072-227884 KITopen-ID: 1000022788 Reportnummer: KIT-SR 7576 |
| HGF-Programm | 32.22.11 (POF II, LK 01) Kernunfallanalysen(QUENCH, LIVE, DISCO) |
| Verlag | KIT Scientific Publishing |
| Umfang | XII, 147 S. |
| Schlagwörter | reflood of overheated reactor core, high temperature behavior of zirconium alloys, hydrogen source term |