Results of semiscale MOD-2C feedwater and steam line break (S-FS) experiment series: Bottom main feedwater line break accident experiments
This report presents the results of four experiments simulating 100, 50, and 14.3% bottom main feedwater line break accidents performed at high pressure and temperature in the Semiscale Mod-2C facility. The primary and secondary thermal-hydraulic responses are characterized (including local secondary convective heat transfer) and the influence of the break size on the responses is discussed. A definite deficiency is identified in existing forced convection boiling heat transfer correlations and the conservatism of FSAR heat transfer degradation assumptions is shown to be questionable. The effectiveness of the recovery operations in maintaining control of the system is addressed, and the system response (including local secondary convective heat transfer) to voided secondary refill operations are discussed. Feedwater line break issues are discussed and conclusions are drawn based on the results of the analysis. Finally, recommendations are made for further utilization of the data and considerations for future code calculations. 34 refs., 112 figs., 1 tab.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5456517
- Report Number(s):
- NUREG/CR-4898; EGG-2503; ON: TI88007079
- Country of Publication:
- United States
- Language:
- English
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ACCIDENTS
BOILERS
COOLING SYSTEMS
DATA
EMERGENCY PLANS
ENERGY SYSTEMS
ENERGY TRANSFER
EXPERIMENTAL DATA
FAILURES
FEEDWATER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
INFORMATION
LOSS OF COOLANT
MECHANICS
NUMERICAL DATA
OXYGEN COMPOUNDS
PRESSURE EFFECTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
RECOMMENDATIONS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
RUPTURES
SAFETY
SCALE MODELS
SCRAM
SHUTDOWNS
STEAM GENERATORS
STRUCTURAL MODELS
TEST FACILITIES
THERMAL ANALYSIS
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS