Experiment prediction for LOFT nuclear experiments L5-1/L8-2. [PWR]

Conference · Fri Jan 01 00:00:00 EST 1982

OSTI ID:6733810

Chen, T H; Modro, S M

The LOFT Experiments L5-1 and L8-2 simulated intermediate break loss-of-coolant accidents with core uncovery. This paper compares the predictions with the measured data for these experiments. The RELAP5 code was used to perform best estimate double-blind and single-blind predictions. The double-blind calculations are performed prior to the experiment and use specified nominal initial and boundary conditions. The single-blind calculations are performed after the experiment and use measured initial and boundary conditions while maintaining all other parameters constant, including the code version. Comparisons of calculated results with experimental results are discussed; the possible causes of discrepancies are explored and explained. RELAP5 calculated system pressure, mass inventory, and fuel cladding temperature agree reasonably well with the experiment results, and only slight changes are noted between the double-blind and single-blind predictions.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6733810
• Report Number(s): EGG-M-15382; CONF-820802-34; ON: DE83000547; TRN: 82-026886
• Resource Relation: Conference: International meeting on thermal nuclear reactor safety, Chicago, IL, USA, 29 Aug 1982; Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
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COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
LOFT REACTOR
REACTOR SAFETY
TEMPERATURE GRADIENTS
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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220600 - Nuclear Reactor Technology- Research
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