Results and analysis of a loss-of-feedwater induced ATWS experiment in the LOFT Facility
Journal Article
·
· Am. Soc. Mech. Eng., (Pap.); (United States)
OSTI ID:6693595
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), Journal Name: Am. Soc. Mech. Eng., (Pap.); (United States) Vol. 83-HT-15; ISSN ASMSA
- 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
ATWS
AUXILIARY SYSTEMS
AUXILIARY WATER SYSTEMS
COMPUTER CALCULATIONS
COMPUTER CODES
COOLING SYSTEMS
DATA
ENERGY SYSTEMS
ENERGY TRANSFER
EXPERIMENTAL DATA
FEEDWATER
FLUID MECHANICS
FORECASTING
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
INFORMATION
LOFT REACTOR
LOSS OF COOLANT
LOSS OF FLOW
MECHANICS
NUMERICAL DATA
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PRESSURE GRADIENTS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SHUTDOWN
REACTORS
RESEARCH AND TEST REACTORS
SHUTDOWNS
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
TESTING
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
AUXILIARY SYSTEMS
AUXILIARY WATER SYSTEMS
COMPUTER CALCULATIONS
COMPUTER CODES
COOLING SYSTEMS
DATA
ENERGY SYSTEMS
ENERGY TRANSFER
EXPERIMENTAL DATA
FEEDWATER
FLUID MECHANICS
FORECASTING
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
INFORMATION
LOFT REACTOR
LOSS OF COOLANT
LOSS OF FLOW
MECHANICS
NUMERICAL DATA
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PRESSURE GRADIENTS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SHUTDOWN
REACTORS
RESEARCH AND TEST REACTORS
SHUTDOWNS
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
TESTING
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS