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The Quench-Debris test - Experimental results and modeling

  • In the framework of the SARNET-2 WP5.1 the QUENCH-DEBRIS test was conducted as the 17th severe accident test using the QUENCH facility at KIT to investigate the formation and coolability of a prototypic debris bed. The test scenario was defined by pre-test calculations using the MELCOR code. This code was used also for post-test analysis. The test bundle with length of about 2 m contains the hafnium shroud tube and 12 heated peripheral rods with claddings made of hafnium. Hafnium was chosen because of its much higher melting temperature and the about one order of magnitude lower oxidation rate compared to zirconium. The claddings of the inner nine rods were made from Zry-4. They were filled with pre-fragmented zirconia pellets. The test started with an oxidation phase of 20 h at peek cladding temperature about 1800 K to reach complete oxidation of the Zry-4 claddings over a height of 500 mm. The temperatures expected from the pre-test simulation fitted well the experimentally observedIn the framework of the SARNET-2 WP5.1 the QUENCH-DEBRIS test was conducted as the 17th severe accident test using the QUENCH facility at KIT to investigate the formation and coolability of a prototypic debris bed. The test scenario was defined by pre-test calculations using the MELCOR code. This code was used also for post-test analysis. The test bundle with length of about 2 m contains the hafnium shroud tube and 12 heated peripheral rods with claddings made of hafnium. Hafnium was chosen because of its much higher melting temperature and the about one order of magnitude lower oxidation rate compared to zirconium. The claddings of the inner nine rods were made from Zry-4. They were filled with pre-fragmented zirconia pellets. The test started with an oxidation phase of 20 h at peek cladding temperature about 1800 K to reach complete oxidation of the Zry-4 claddings over a height of 500 mm. The temperatures expected from the pre-test simulation fitted well the experimentally observed evolution of the bundle conditions. The possibly surviving inner Zry-4 claddings were destroyed by the application of an axial mechanical force resulting in material relocation and formation of a heterogeneous debris bed consisting of segmented pellets and larger cladding tube fragments at the grid spacer 2 (350 mm elevation) and in a smaller amount at grid spacer 3 (1050 mm elevation). The so destroyed bundle was quenched with 10 g/s water. The evaporation rate generally showed an increasing trend during the reflood, except at the time of water penetration through the debris bed at spacer 2 when stagnation was observed. All peripheral hafnium claddings survived the whole test. During the oxidation phase about 100 g hydrogen was released. The time dependence of the hydrogen release predicted in the pre-test calculations fits well the measured one. The post-test examinations comprise videoscope inspections, high energy X-ray-tomography and metallographic investigations of the debris bed.zeige mehrzeige weniger

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  • Paper 2.6 KIT.pdf
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Metadaten
Autor*innen:J. Stuckert, J. Birchley, M. Große, L. Fernandez-Moguel, Yener Onel, C. Rössger, M. Steinbrück
Dokumenttyp:Beitrag zu einem Tagungsband
Veröffentlichungsform:Graue Literatur
Sprache:Englisch
Titel des übergeordneten Werkes (Englisch):ERMSAR-2013 - 6th European review meeting on severe accident research
Jahr der Erstveröffentlichung:2013
Erste Seite:1
Letzte Seite:13 (Paper 2.6)
Freie Schlagwörter:Hochenergie-Computertomographie; Nukleare Sicherheitsforschung
Veranstaltung:ERMSAR-2013 - 6th European review meeeting on severe accident research
Veranstaltungsort:Avignon, France
Beginndatum der Veranstaltung:02.10.2013
Enddatum der Veranstaltung:04.10.2013
Verfügbarkeit des Dokuments:Datei im Netzwerk der BAM verfügbar ("Closed Access")
Datum der Freischaltung:20.02.2016
Referierte Publikation:Nein
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