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KAJET experiments on pressurized melt jets with view to their interaction with substratum materials = : KAJET-Experimente über Druckschmelzsträhle mit Hinblick auf deren Wechselwirkung mit Substratwerkstoffen

In the sequence of a core melt accident in a light water reactor it is assumed that, after melt-through of the reactor pressure vessel, the molten corium is released as a pressurized melt jet which causes erosion in the substratum material of the reactor pit. Melt jet behaviour under driving pressur... Full description

Kongresse: OECD Workshop on Ex-Vessel Debris Coolability 1999 1999.11.15-1999.11.18 Karlsruhe, DE
OECD Workshop on Ex-Vessel Debris Coolability 1999.11.15-1999.11.18 Karlsruhe, DE
Contained in: Forschungs-Zentrum Karlsruhe, Wissenschaftliche Berichte, Technik und Umwelt Vol. 6475 (2000), p. 54-65
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ISSN: 0947-8620
Additional Keywords: ALUMINIUMOXID
DRUCKEINFLUSS
DRUCKWASSERREAKTOR
DURCHGEHEN
EISEN
EROSION
FLUESSIGMETALLSTRAHL
FLUESSIGPHASE
GROESSTER-ANZUNEHMENDER-UNFALL
KERNENERGIE
KERNKRAFTWERK
KERNSCHMELZE
SCHMELZE
SICHERHEITSTECHNIK
SUBSTRAT
Notes: Copyright: Metadaten: TEMA, Copyright WTI-Frankfurt eG
Copyright: (C) Alle Rechte beim Herausgeber
Physical Description: 12 Seiten, 12 Bilder, 2 Tabellen, 6 Quellen
PPN (Catalogue-ID): WTI03780863X
Note: WTI TEMA DB
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Internes Format
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245 0 0 |a KAJET experiments on pressurized melt jets with view to their interaction with substratum materials =  |b KAJET-Experimente über Druckschmelzsträhle mit Hinblick auf deren Wechselwirkung mit Substratwerkstoffen 
300 |a 12 Seiten, 12 Bilder, 2 Tabellen, 6 Quellen 
500 |a Copyright: Metadaten: TEMA, Copyright WTI-Frankfurt eG 
500 |a Copyright: (C) Alle Rechte beim Herausgeber 
520 |a In the sequence of a core melt accident in a light water reactor it is assumed that, after melt-through of the reactor pressure vessel, the molten corium is released as a pressurized melt jet which causes erosion in the substratum material of the reactor pit. Melt jet behaviour under driving pressures of up to 2 MPa and corresponding erosion rates in various substratum materials are being investigated at Forschungszentrum Karlsruhe in so-called KAJET experiments using thermite melts (either iron or alumina) as simulant materials. Masses of up to 150 kilogrammes at temperatures of about 2100 deg C can be provided for ejection. A special feature of the tests is to prevent melt dispersal due to gas break-through by sharply reducing the driving pressure before the end of melt release. Performance tests carried out with both water and smaller melt masses (10-40 kg) prior to the erosion tests aimed at finding the material for and appropriate geometry of a nozzle to provide a compact melt jet. Zirconia proved to be a good material for the nozzle. Good results have been obtained with a nozzle having a length to diameter ratio of two and a contraction angle of 90 deg. This geometry is in good agreement with results from vessel-wall melt-through experiments at other laboratories. The first erosion test, conducted with a melt mass of 40 kg (iron and oxide in equal shares) ejected under a pressure of 0.3 MPa onto concrete plates, give information about erosion rates concerning the target as well as the nozzle. The erosion was larger in case of iron. 
653 4 |a SUBSTRAT 
653 4 |a EISEN 
653 4 |a SCHMELZE 
653 4 |a FLUESSIGMETALLSTRAHL 
653 4 |a FLUESSIGPHASE 
653 4 |a EROSION 
653 4 |a DRUCKEINFLUSS 
653 4 |a DRUCKWASSERREAKTOR 
653 4 |a KERNKRAFTWERK 
653 4 |a KERNENERGIE 
653 4 |a GROESSTER-ANZUNEHMENDER-UNFALL 
653 4 |a DURCHGEHEN 
653 4 |a SICHERHEITSTECHNIK 
653 4 |a ALUMINIUMOXID 
653 4 |a KERNSCHMELZE 
711 2 |a OECD Workshop on Ex-Vessel Debris Coolability  |n 1999  |d 1999.11.15-1999.11.18  |c Karlsruhe, DE 
711 2 |a OECD Workshop on Ex-Vessel Debris Coolability  |d 1999.11.15-1999.11.18  |c Karlsruhe, DE 
773 0 8 |i In  |t Forschungs-Zentrum Karlsruhe, Wissenschaftliche Berichte, Technik und Umwelt  |g Vol. 6475 (2000), p. 54-65  |q 6475<54-65  |x 0947-8620  |x 0947-8620 
912 |a GBV_WTI 
950 |a Substrat  |a Eisen  |a Schmelze  |a Flüssigmetallstrahl  |a flüssige Phase  |a Erosion  |a Düse  |a Druckeinfluss  |a Druckwasserreaktor  |a Kernkraftwerk  |a Kernenergie  |a größter anzunehmender Unfall  |a Durchgehen  |a Sicherheitstechnik  |a Aluminiumoxid  |a Kernschmelze  |2 DE-601 
951 |a AR 
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