The document presents an assessment of the severe accident phenomena observed from four Full-Length High-Temperature (FLHT) tests that were performed by the Pacific Northwest Laboratory (PNL) in the National Research Universal (NRU) reactor at Chalk River, Ontario, Canada. These tests were conducted for the U.S. Nuclear Regulatory Commission (NRC) as part of the Severe Accident Research Program. The objectives of the test were to simulate conditions and provide information on the behavior of full-length fuel rods during hypothetical, small-break, loss-of-coolant severe accidents, in commercial light water reactors.
Full-Length Fuel Rod Behavior under Severe Accident Conditions
1992
71 pages
Report
Keine Angabe
Englisch
Reactor Fuels & Fuel Processing , Reactor Engineering & Nuclear Power Plants , Reactor accidents , Fuel rods , Accident investigations , Fuel-coolant interactions , High temperature tests , Water cooled reactors , Loss of coolant , Hydrogen , Computerized simulation , Fission product release , Full length high temperature tests
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