Results and analysis of a loss-of-feedwater induced ATWS experiment in the LOFT facility. [PWR]
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 (USA); Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5492521
- Report Number(s):
- EGG-M-07083; CONF-830702-26; ON: DE84000562
- Country of Publication:
- United States
- Language:
- English
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Analysis of results from a loss-of-offsite-power-initiated ATWS experiment in the LOFT facility. [PWR]
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Related Subjects
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
COMPUTER CALCULATIONS
DATA
ENERGY SYSTEMS
ENERGY TRANSFER
EXPERIMENTAL DATA
FEEDWATER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
INFORMATION
LOFT REACTOR
MECHANICS
NUMERICAL DATA
OXYGEN COMPOUNDS
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
STEAM SYSTEMS
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
THEORETICAL DATA
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS