Published September 1978
| Version v1
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Fuel element behavior during a loss-of-coolant accident and interaction with the emergency core cooling
Description
The process of emergency core cooling in a LOCA of a pressurized water reactor is summarized. The thermohydraulics in the reactor core and the loading of the fuel rod claddings during a LOCA are covered in more detail. Some recent experimental results on Zircaloy cladding deformation in a LOCA are discussed. They indicate that axial and azimuthal cladding temperature differences, which are enhanced by cooling during reflooding, are limiting the strains of the Zircaloy cladding tubes and the resulting coolant channel blockage in the fuel elements. (orig.)
Availability note (English)
MF available from INIS under the Report Number.Abstract (German)
Es wird zunaechst ein Ueberblick gegeben ueber die Kernnotkuehlung eines Druckwasserreaktors beim Kuehlmittelverluststoerfall. Die thermohydraulischen Vorgaenge im Reaktorkern sowie die Belastung der Brennstabhuellrohre werden beschrieben. Anhand ausgewaehlter neuer Forschungsergebnisse zum Deformationsverhalten der Zirkaloyhuellrohre beim Kuehlmittelverluststoerfall wird gezeigt, dass axiale und azimutale Huellrohrtemperaturdifferenzen, welche durch die Kuehlung beim Fluten verstaerkt werden, die Dehnungen der Zirkaloyhuellrohre sowie die entstehende Kuehlkanalversperrung im Brennelement begrenzen. (orig.)
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Additional details
Additional titles
- Original title (German)
- Verhalten der Brennelemente beim Kuehlmittelverluststoerfall und Wechselwirkung mit der Kernnotkuehlung
Publishing Information
- Imprint Pagination
- 24 p.
- Report number
- KFK--2691
Conference
- Title
- Advanced training seminar on thermo- and fluid-dynamic design of nuclear power plants with LWR reactors.
- Dates
- 10 - 12 May 1978.
- Place
- Offenbach am Main, Germany, F.R.
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 10449571
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORE FLOODING SYSTEMS; DEFORMATION; FLOW BLOCKAGE; FUEL CANS; FUEL ELEMENTS; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; STRAINS; THERMODYNAMICS
- Descriptors DEC
- ACCIDENTS; ECCS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS