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Liquidus/solidus and Zr solubility measurements for PWR and BWR core melt compositions = : Liquidus/Solidus- und Zr-Löslichkeitsmessungen für PWR- und BWR-Kernschmelzenzusammensetzungen

Measurements have been made of the solidus and liquidus temperatures of various corium compositions using a Differential Thermal Analysis (DTA) technique. The corium in these experiments consisted of mixtures of (U,Zr)O(2-x), with the oxygen content of the mixtures varied to reflect various stages o... 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. 380-393
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ISSN: 0947-8620
Additional Keywords: CHEMISCHE-ZUSAMMENSETZUNG
DRUCKWASSERREAKTOR
DURCHGEHEN
GROESSTER-ANZUNEHMENDER-UNFALL
KERNENERGIE
KERNKRAFTWERK
KERNSCHMELZE
LIQUIDUSLINIE
LOESLICHKEIT
SCHMELZE
SICHERHEITSTECHNIK
SOLIDUSLINIE
URANOXID
ZIRKONIUMOXID
ZIRKONIUMZUSATZ
Notes: Copyright: Metadaten: TEMA, Copyright WTI-Frankfurt eG
Copyright: (C) Alle Rechte beim Herausgeber
Physical Description: 14 Seiten, 6 Bilder, 6 Tabellen, 6 Quellen
PPN (Catalogue-ID): WTI037808451
Note: WTI TEMA DB
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Internes Format
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245 0 0 |a Liquidus/solidus and Zr solubility measurements for PWR and BWR core melt compositions =  |b Liquidus/Solidus- und Zr-Löslichkeitsmessungen für PWR- und BWR-Kernschmelzenzusammensetzungen 
300 |a 14 Seiten, 6 Bilder, 6 Tabellen, 6 Quellen 
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520 |a Measurements have been made of the solidus and liquidus temperatures of various corium compositions using a Differential Thermal Analysis (DTA) technique. The corium in these experiments consisted of mixtures of (U,Zr)O(2-x), with the oxygen content of the mixtures varied to reflect various stages of zirconium oxidation. The melts are representative of typical in-vessel core melt sequences. For most of the tests conducted, the UO2/Zr mass ratio was fixed at 4.86 (U/Zr molar ratio of 1.64), which is representative of most US PWRs. A few tests were also conducted with a UO2/Zr mass ratio of 2.05 (U/Zr molar ratio 0.69), which is representative of US BWRs, as well as Russian VVERs. Information on the solubility of unoxidized Zr in the oxide phase was obtained from both chemical and metallographic analysis of solidus/liquidus melt samples. For PWR compositions, the solidus temperature was found to increase from 2005 C to 2105 C as the extent of Zr oxidation was increased from 30 to 70 %. Similarly, the liquidus temperature was found to increase from 2465 C to 2520 LC over the same oxidation range. For BWR melt compositions in the range of 30 to 70 % cladding oxidation, the solidus was found to increase from 1930 C to 2042 C, while the liquidus was found to vary more substantially from 2198 C to 2475 C. From microstructure examinations it was determined that there was no global segregation into distinct metal and oxide phases during cooldown of the samples. Therefore, it is concluded that Zr metal is soluble in the oxide phase under molten conditions for both BWR and PWR core compositions in the range of 30-70 % oxidation. 
653 4 |a SCHMELZE 
653 4 |a URANOXID 
653 4 |a ZIRKONIUMOXID 
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653 4 |a KERNKRAFTWERK 
653 4 |a GROESSTER-ANZUNEHMENDER-UNFALL 
653 4 |a DURCHGEHEN 
653 4 |a SICHERHEITSTECHNIK 
653 4 |a LIQUIDUSLINIE 
653 4 |a SOLIDUSLINIE 
653 4 |a LOESLICHKEIT 
653 4 |a ZIRKONIUMZUSATZ 
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653 4 |a DRUCKWASSERREAKTOR 
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. 380-393  |q 6475<380-393  |x 0947-8620  |x 0947-8620 
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