In-Reactor LOCA Tests of Zircaloy Sheathed UO2 Fuel at Chalk River

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P.J. Fehrenbach
J.A. Walsworth
R.C. Spencer
W.R. Chase
R.D. Delaney

Abstract

Two in-reactor LOCA tests have been completed at Chalk River Nuclear Laboratories (CRNL) as part of a program to provide a well-characterized database against which transient fuel behaviour codes can be assessed. Maximum fuel sheath heat-up rates were 80 degrees C/s to a maximum temperature of 971 degrees C. Fuel heat-up rates were in the range of 10 to 50 degrees C/s to a maximum central fuel temperature of about 2250 degrees C. The tests were terminated with a cold water quench. On-line measurements, post-test strain measurements, and metallographic analyses are reported. Maximum sheath strains were less than 5% and the fuel elements survived the MCA transients without failure.

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