Contact
schliessen

Filtern

 

Bibliotheken

Logo der Bibliothek

Siegel TU Braunschweig Universitätsbibliothek Braunschweig
You do not seem to be within the network of Braunschweig University.
As student, researcher or staff member of Braunschweig University you can use the VPN service to gain access to electronic publications.
Alternatively, you can use your university username and password via Shibboleth to gain access to electronic publications with certain publishers. You can find more details in our Blog (in German).

Estimates of corium viscosity for PWR and BWR core melt compositions based on spreading rate = : Bestimmung der Kernschmelzenviskosität für PWR- und BWR-Kernschmelzenzusammensetzungen, basierend auf der Ausbreitungsgeschwindigkeit

Viscosity estimates have been made for various corium compositions based on the spreading rate. The corium used in the measurements was a mixture of UO2, ZrO2, and Zr, with the oxygen content being a parameter to reflect different stages of zirconium oxidation. The mixtures used in these tests span... 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. 394-407
Fulltext access:
Availability is being checked...
Interlibrary loan: Check possibility for interlibrary loan
ISSN: 0947-8620
Additional Keywords: AUSBREITUNGSGESCHWINDIGKEIT
CHEMISCHE-ZUSAMMENSETZUNG
DRUCKWASSERREAKTOR
DURCHGEHEN
ERSTARREN
GROESSTER-ANZUNEHMENDER-UNFALL
KERNENERGIE
KERNKRAFTWERK
KERNSCHMELZE
SCHMELZE
SICHERHEITSTECHNIK
URANOXID
VISKOSITAET
WASSERKUEHLUNG
ZIRKONIUM
ZIRKONIUM:IV:OXID
Notes: Copyright: Metadaten: TEMA, Copyright WTI-Frankfurt eG
Copyright: (C) Alle Rechte beim Herausgeber
Physical Description: 14 Seiten, 9 Bilder, 4 Tabellen, 7 Quellen
PPN (Catalogue-ID): WTI037808443
Note: WTI TEMA DB
more publication details ...

Associated Publications/Volumes

  • Associated records are being queried...
more (+)
Internes Format
LEADER 03288naa a2200469 c 4500
001 WTI037808443
003 DE-601
005 20190330041952.0
008 171222s2000 000 0 und d
028 5 2 |a TEMA2001_wti_pica 
035 |a (DE-599)WTI20001105960 
040 |b ger  |c GBVCP 
084 |a E  |2 FIZTtc 
084 |a 3EE  |a 3IFS  |a 3KG  |2 FON2006 
245 0 0 |a Estimates of corium viscosity for PWR and BWR core melt compositions based on spreading rate =  |b Bestimmung der Kernschmelzenviskosität für PWR- und BWR-Kernschmelzenzusammensetzungen, basierend auf der Ausbreitungsgeschwindigkeit 
300 |a 14 Seiten, 9 Bilder, 4 Tabellen, 7 Quellen 
500 |a Copyright: Metadaten: TEMA, Copyright WTI-Frankfurt eG 
500 |a Copyright: (C) Alle Rechte beim Herausgeber 
520 |a Viscosity estimates have been made for various corium compositions based on the spreading rate. The corium used in the measurements was a mixture of UO2, ZrO2, and Zr, with the oxygen content being a parameter to reflect different stages of zirconium oxidation. The mixtures used in these tests span the range of U/Zr molar ratios representative of both PWR and BWR melt compositions. The test facility consisted of a one-dimensional (3 m long by 15 cm wide), refractory lined spreading channel. The core melts were generated using exothermic chemical reactions. Spreading was initiated using a 'dam break' approach (i.e., spreading was initiated following meltout of a thin stainless steel barrier). The leading edge penetration as a function of time was measured. Based on the spreading rate, the corresponding corium viscosity was estimated from a well-known analytical solution which relates spreading rate to melt mass, channel width, and viscosity for viscous flows. Tests were conducted with compositions representative of Zr oxidation of 30, 50, and 70 % both BWR and PWR melts. The data indicates that at a roughly constant temperature of 2500 C, the viscosity varies by as much as three orders of magnitude over this range of cladding oxidation. 
653 4 |a VISKOSITAET 
653 4 |a SCHMELZE 
653 4 |a URANOXID 
653 4 |a ZIRKONIUM 
653 4 |a ZIRKONIUM:IV:OXID 
653 4 |a CHEMISCHE-ZUSAMMENSETZUNG 
653 4 |a KERNKRAFTWERK 
653 4 |a SICHERHEITSTECHNIK 
653 4 |a DRUCKWASSERREAKTOR 
653 4 |a KERNENERGIE 
653 4 |a GROESSTER-ANZUNEHMENDER-UNFALL 
653 4 |a DURCHGEHEN 
653 4 |a WASSERKUEHLUNG 
653 4 |a AUSBREITUNGSGESCHWINDIGKEIT 
653 4 |a ERSTARREN 
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. 394-407  |q 6475<394-407  |x 0947-8620  |x 0947-8620 
912 |a GBV_WTI 
950 |a Viskosität  |a Schmelze  |a Uranoxid  |a Zirkonium  |a Zirkoniumdioxid  |a chemische Zusammensetzung  |a Kernkraftwerk  |a Sicherheitstechnik  |a Druckwasserreaktor  |a Kernenergie  |a GAU (größter anzunehmender Unfall)  |a Durchgehen  |a Wasserkühlung  |a Ausbreitungsgeschwindigkeit  |a Erstarrung  |a Kernschmelze  |2 DE-601 
951 |a AR 
952 |d 6475  |j 2000  |h 394-407