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COTELS project (1): overview of project to study FCI and MCCI during a severe accident = : COTELS-Projekt (1): Ein Überblick über das Projekt zur Untersuchung von FCI und MCCI während eines schweren Kernreaktorunfalles

Fuel coolant interaction (FCI) and molten core concrete interaction (MCCI) have been studied experimentally within the framework of COTELS project from 1995 as a joint study between NUPEC (Japan) and NNC (Republic of Kazakhstan) using one of the testing complex at NNC. The testing complex includes t... 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. 285-292
Journal Title: Forschungs-Zentrum Karlsruhe, Wissenschaftliche Berichte, Technik und Umwelt
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ISSN: 0947-8620
Additional Keywords: BETON
DURCHGEHEN
ERSTARRUNGSDAUER
GROESSTER-ANZUNEHMENDER-UNFALL
KERNENERGIE
KERNKRAFTWERK
KERNREAKTOR
KERNSCHMELZE
KUEHLUNG
NICHTROSTENDER-STAHL
SCHMELZE
SICHERHEITSTECHNIK
URANOXID
ZIRKONIUM
Notes: Copyright: Metadaten: TEMA, Copyright WTI-Frankfurt eG
Copyright: (C) Alle Rechte beim Herausgeber
Physical Description: 8 Seiten, 8 Bilder, 2 Tabellen, 6 Quellen
PPN (Catalogue-ID): WTI037808524
Note: WTI TEMA DB
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Internes Format
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245 0 0 |a COTELS project (1): overview of project to study FCI and MCCI during a severe accident =  |b COTELS-Projekt (1): Ein Überblick über das Projekt zur Untersuchung von FCI und MCCI während eines schweren Kernreaktorunfalles 
300 |a 8 Seiten, 8 Bilder, 2 Tabellen, 6 Quellen 
500 |a Copyright: Metadaten: TEMA, Copyright WTI-Frankfurt eG 
500 |a Copyright: (C) Alle Rechte beim Herausgeber 
520 |a Fuel coolant interaction (FCI) and molten core concrete interaction (MCCI) have been studied experimentally within the framework of COTELS project from 1995 as a joint study between NUPEC (Japan) and NNC (Republic of Kazakhstan) using one of the testing complex at NNC. The testing complex includes three experimental facilities 'SLAVA', 'LAVA' and 'LAVA-M' for debris coolability tests. Three types of experiments were carried out. To get the molten corium, the electric induction melting frunace (EMF) was used. The EMF produced nearly equal 60 kg of corium containing UO2, stainless steel, Zr and ZrO2. The temperature of the produced melt was about 3200 K. The melt was discharged into the water pool in Test A or onto the concrete trap in Test B/C. The corium in the concrete trap was heated in Test B/C by another induction melt heater. Prior to main Test A and Test B/C, several supporting experiments were conducted. Integrity of graphite crucible with TaC sheet during producing UO2 corium was confirmed experimentally. The induction melt heater was calibrated and the efficiency for the induction heater of 'LAVA-M' facility was determined as 47 %. The thermal conductivity and thermal diffusivity of concrete up to about 1073 K, and melting-solidification points of eutectics generated from corium components were determined experimentally. Discharge corium behavior, using UO2 corium, was also observed by speed cameras in Test 01. 
653 4 |a SCHMELZE 
653 4 |a KERNENERGIE 
653 4 |a GROESSTER-ANZUNEHMENDER-UNFALL 
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653 4 |a KUEHLUNG 
653 4 |a URANOXID 
653 4 |a ZIRKONIUM 
653 4 |a NICHTROSTENDER-STAHL 
653 4 |a ERSTARRUNGSDAUER 
653 4 |a SICHERHEITSTECHNIK 
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. 285-292  |q 6475<285-292  |x 0947-8620  |x 0947-8620 
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950 |a Schmelze  |a Kernenergie  |a GAU (größter anzunehmender Unfall)  |a Durchgehen  |a Kernkraftwerk  |a Kernreaktor  |a Beton  |a Abkühlung  |a Uranoxid  |a Zirkonium  |a rostfreier Stahl  |a Erstarrungsdauer  |a Sicherheitstechnik  |a Kernschmelze  |2 DE-601 
951 |a AR 
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