Analysis of a hypothetical core meltdown accident of a pressurized-water reactor
Creators
- 1. Kraftwerk Union A.G., Erlangen (Germany, F.R.). Bereich Brennelemente, Brennstoffkreislauf
- 2. Kraftwerk Union A.G., Erlangen (Germany, F.R.). Hauptbereich Reaktortechnik
- 3. Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.)
Description
The hypothetical core meltdown accident is being studied also under the aspect of risk analysis within the reactor safety program of the Bundesminister fuer Forschung und Technologie (BMFT). Zircaloy-clad fuel rods slump beyond 18000C and the fuel is liquefied at temperatures more than 24000C. RPV steel withstands molten Corium up to its melting point. The liquefaction of concrete occurs at 13000C to 14000C only by thermal degradation. Theoretical work is based upon the development of computer codes to analyze the sequence of a hypothetical core meltdown accident. An overpressure failure of the containment is not expected to occur before 2 1/2 days. The penetration of the concrete foundation by the molten core takes more than 13 days. (orig.)
Abstract (German)
Der hypothetische Kernschmelzunfall wird im Rahmen des vom BMFT gefoerderten Reaktorsicherheitsprogramms auch unter dem Aspekt der Risikoanalyse untersucht. Zircaloy-umhuellte Brennstaebe versagen durch Schmelzen bei Temperaturen ueber 18000C. Der Brennstoff ist bei Temperaturen ueber 24000C verfluessigt. Der RDB-Stahl widersteht fluessiger Kernschmelze bis zum Schmelzpunkt. Thermisches Versagen von Reaktorbeton beginnt bei 13000C bis 14000C. Die theoretischen Untersuchungen konzentrieren sich auf Unfallablaufanalysen. Ueberdruckversagen des Containments kann fruehestens nach 2 1/2 Tagen auftreten. Das Durchschmelzen des Fundaments dauert laenger als 13 Tage. (orig.)Additional details
Publishing Information
- Journal Title
- Siemens Forsch.- Entwicklungsber.
- Journal Volume
- 8
- Journal Issue
- 2
- Series
- Siemens Forsch.- Entwicklungsber.
- Journal Page Range
- 114-121
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 10470678
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- B CODES; C CODES; CHEMICAL EXPLOSIONS; CHEMICAL REACTION KINETICS; COMBUSTION; COMPARATIVE EVALUATIONS; CONCRETES; CONTAINMENT; CORIUM; HEATING; HYDROGEN; MELTDOWN; MELTING; PRESSURE DEPENDENCE; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR SAFETY EXPERIMENTS; WATER; WATER VAPOR
- Descriptors DEC
- ACCIDENTS; BUILDING MATERIALS; CHEMICAL REACTIONS; COMPUTER CODES; CONTAINERS; ELEMENTS; EXPLOSIONS; FLUIDS; GASES; HYDROGEN COMPOUNDS; KINETICS; NONMETALS; OXIDATION; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; REACTION KINETICS; REACTOR ACCIDENTS; REACTORS; VAPORS; WATER COOLED REACTORS; WATER MODERATED REACTORS