Results and analysis of a loss-of-feedwater induced ATWS experiment in the LOFT Facility
An anticipated transient without scram (ATWS), initiated by a loss of feedwater, was experimentally simulated in the Loss-of-Fluid Test (LOFT) pressurized water reactor (PWR). Primary system pressure was controlled using a two-position actuator relief valve to simulate a scaled power-operated relief valve (PORV) and safety relief valve (SRV) representative of those in a commercial PWR. Auxiliary feedwater injection was delayed during the experiment until the plant recovery phase where long-term shutdown was achieved by an operator-controlled plant recovery procedure without inserting the control rods. The system transient response predicted by the RELAP5/MOD1 computer code showed good agreement with the experimental data.
- Research Organization:
- EG and G Idaho Inc., Idaho Falls, ID
- OSTI ID:
- 6693595
- Journal Information:
- Am. Soc. Mech. Eng., (Pap.); (United States), Vol. 83-HT-15
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ATWS
HEAT TRANSFER
HYDRAULICS
PRESSURE GRADIENTS
TEMPERATURE GRADIENTS
PWR TYPE REACTORS
AUXILIARY WATER SYSTEMS
COMPUTER CALCULATIONS
COMPUTER CODES
EXPERIMENTAL DATA
FEEDWATER
FORECASTING
LOFT REACTOR
LOSS OF COOLANT
LOSS OF FLOW
PERFORMANCE TESTING
PRIMARY COOLANT CIRCUITS
R CODES
REACTOR SHUTDOWN
ACCIDENTS
AUXILIARY SYSTEMS
COOLING SYSTEMS
DATA
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HYDROGEN COMPOUNDS
INFORMATION
MECHANICS
NUMERICAL DATA
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
SHUTDOWNS
TANK TYPE REACTORS
TEST REACTORS
TESTING
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled