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RELAP4/MOD6 predictions comparisons with LOFT LOCE L2-2 data. [PWR]

Technical Report ·
OSTI ID:6042640
;
Comparisons are made between RELAP4/MOD6 predicted and experimental measured quantities for Loss-of-Fluid Test Loss-of-Coolant Experiment L2-2. These data comparisons provide a detailed record for subsequent analysis. Comparisons indicate that the trends in the system hydraulic response were generally predicted well. However, the broken cold leg break flow was probably overpredicted in subcooled and saturated critical flow which led to an incorrect core flow which resulted in overpredicting the fuel rod cladding surface temperature response.
Research Organization:
Idaho National Engineering Lab., Idaho Falls (USA)
DOE Contract Number:
EY-76-C-07-1570
OSTI ID:
6042640
Report Number(s):
LTR-20-100
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
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS