Discussion of different analytical approaches to predicting rewet phenomena in loss-of-coolant experiments. RELAP4/MOD6 and TRAC-P1A predictions of LOFT Experiment L2-3. [PWR]
The objective of this discussion is to provide an understanding of why RELAP4/MOD6 and TRAC-P1A predictions of LOFT LOCE L2-3 did not predict the observed fuel rod cladding rewet while TRAC-P1A plus the Iloeje minimum film boiling correlation prediction did. To obtain this understanding, the initial process is to determine how the post-critical heat flux (CHF) boiling curves are constructed from convective heat transfer correlations in the two computer codes. This knowledge can then be used to explain what physical processes must be accounted for in the analytical modeling to accurately represent the physically observed rewet phenomena.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 5837419
- Report Number(s):
- IDO-1570-T27
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
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220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
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FLUID MECHANICS
HEAT FLUX
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HYDRAULICS
LOFT REACTOR
LOSS OF COOLANT
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PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
CRITICAL HEAT FLUX
ENERGY TRANSFER
FLUID MECHANICS
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
LOFT REACTOR
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS