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U.S. Department of Energy
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Nuclear fuel rod behavior during LOFT experiment L2-2

Conference ·
OSTI ID:6016730
The Loss-of-Fluid Test (LOFT) Program is providing data to evaluate analytical models used to predict the thermal-hydraulic and fuel rod response of a pressurized water reactor (PWR) under loss-of-coolant accident (LOCA) conditions. The fuel rod response for the first nuclear loss-of-coolant experiment (LOCE), LOCE L2-2, is summarized.
Research Organization:
Idaho National Engineering Lab., Idaho Falls (USA)
Sponsoring Organization:
USDOE
DOE Contract Number:
EY-76-C-07-1570
OSTI ID:
6016730
Report Number(s):
CONF-790646--3
Country of Publication:
United States
Language:
English