Quick look report for semiscale MOD-2C Test S-FS-11
Results of a preliminary analysis of the fifth test performed in the Semiscale MOD-2C Steam Generator Feedwater and Steam Line Break (FS) experiment series are presented. Test S-FS-11 simulated a pressurized water reactor transient initiated by a 50% break in a steam generator bottom feedwater line downstream of the check valve. With the exception of primary pressure, the initial conditions represented the initial conditions used for the C-E System 80 Final Safety Analysis Report (FSAR) Appendix 15B calculations. The transient included an initial 600 s period in which only automatic plant protection systems responded to the initiating event. This period was followed by a series of operator actions necessary to stabilize the plant followed by break isolation and affected loop steam generator refill with auxiliary feedwater. The test results provided a measured evaluation of the effectiveness of the automatic responses in minimizing primary system overpressurization and operator actions in stabilizing the plant. Test data also provided a basis for comparison with other tests in the series of the effects of break size on primary overpressurization and primary-to-secondary heat transfer. 64 figs.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6255242
- Report Number(s):
- EGG-RTH-7103; ON: TI86005308
- Country of Publication:
- United States
- Language:
- English
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ACCIDENTS
ANALOG SYSTEMS
BLOWDOWN
BOILERS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FAILURES
FEEDWATER
FLUID MECHANICS
FUNCTIONAL MODELS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
LOSS OF COOLANT
MECHANICS
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PIPES
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SIMULATORS
REACTORS
SECONDARY COOLANT CIRCUITS
SIMULATORS
STEAM
STEAM GENERATORS
TEST FACILITIES
TESTING
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS