Published June 1987 | Version v1
Report Restricted

Out-of-pile-experiments for the investigation of severe fuel damage

Creators

Description

As as consequence of the TMI-2 reactor incident an additional research program to investigate severe fuel damage (SFD) mechanisms was started in the Kernforschungszentrum Karlsruhe within the frame of the Nuclear Safety Project. An essential tool within this program is the CORA test facility. It is designed for the investigation of LWR fuel damage phenomena in the temperature range from 12000C through 22000C by out-of-pile single-rod and bundle experiments. In this report the conception and the actual design of the CORA facility are described. (orig./HP)

Abstract (German)

In der Folge des Stoerfalles am TMI-2 Reaktor wurde am Kernforschungszentrum Karlsruhe im Rahmen des PNS ein zusaetzliches Programm zur Untersuchung schwerer Kernschaeden (Severe Fuel Damage, SFD) begonnen. Als wesentliche Komponente dieses Programmes ist die Versuchsanlage CORA zu sehen, mit deren Hilfe an Einzelstab- und Buendelexperimenten der Schadensverlauf bei LWR-Brennelementen im Temperaturbereich von 12000C bis 22000C untersucht werden soll. Der Bericht beschreibt das Konzept und die Ausfuehrung der Versuchsanlage CORA. (orig./HP)

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Additional details

Additional titles

Subtitle (English)
Description of the CORA facility
Original title (German)
Out-of-pile-Experimente zur Untersuchung schwerer Kernschaeden
Original subtitle (German)
SFD-Versuchsanlage CORA - Anlagenbeschreibung.

Publishing Information

Imprint Pagination
77 p.
Report number
KFK--4274

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
19089431
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BWR TYPE REACTORS; FUEL CANS; FUEL RODS; MELTDOWN; PWR TYPE REACTORS; REACTOR CORES; REACTOR SAFETY EXPERIMENTS; TEST FACILITIES; ULTRAHIGH TEMPERATURE; VERY HIGH TEMPERATURE
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS