Uncertainty in predicted loft reflooding response: influence on cladding oxidation
Semiscale gravity feed reflood and FLECHT-SET tests have been reviewed to determine phenomena which may be important during LOFT reflood. FLOOD4 and RELAP4/MOD6 predictions for Semiscale and FLECHT-SET tests were compared to experimental data. Based on these comparisons, uncertainties were estimated for the LOFT reflood predictions; these uncertainties were then utilized to bound the extent of cladding oxidation expected for the LOFT L2-3 and L2-4 tests.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6074332
- Report Number(s):
- LTR-1111-58
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CHEMICAL REACTIONS
ENERGY TRANSFER
FLUID MECHANICS
LOFT REACTOR
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CHEMICAL REACTIONS
ENERGY TRANSFER
FLUID MECHANICS
LOFT REACTOR
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS