In-pile tests at Karlsruhe of LWR fuel-rod behavior during the heatup phase of a LOCA

Journal Article · Tue Jan 01 00:00:00 EST 1980 · Nucl. Saf.; (United States)

OSTI ID:5744185

Karb, E H

In order to investigate the influence of a nuclar environment on the mechanisms of fuel-rod failure, in-pile tests simulating the heatup phase of a loss-of-coolant accident in a pressurized-water reactor are being conducted with irradiated and unirradiated short-length single rods in the FR2 reactor at Kernforschungszentrum karlsruhe (Karlsruhe Nuclear Reasearch Center), Federal Republic of Germany, within the Project Nuclear Safety. With nearly 70% of the scheduled tests completed, no such influences have been found. The in-pile burst and deformation data are in good agreement with results from nonnuclear tests with electrically heated fuel-rod simulators. The phenomenon of pellet disintegration, which has been observed in all tests with previously irradiated rods, needs further investigation.

• Research Organization: Kernforschungszentrum, Karlsruhe, Germany
• OSTI ID: 5744185
• Journal Information: Nucl. Saf.; (United States), Vol. 21:1
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL ELEMENT FAILURE
PERFORMANCE TESTING
PWR TYPE REACTORS
DEFORMATION
KERNFORSCHUNGSZENTRUM KARLSRUHE
LOSS OF COOLANT
PRESSURE DEPENDENCE
SIMULATION
TEMPERATURE DEPENDENCE
ACCIDENTS
GERMAN FR ORGANIZATIONS
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTORS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled