Published September 1978 | Version v1
Report Restricted

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