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
- Resource Relation:
- Conference: 21. ASME/AIChE national heat transfer conference, Seattle, WA, USA, 24 Jul 1983; Other Information: Portions are illegible in microfiche products
- 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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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ATWS
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
COMPUTER CALCULATIONS
EXPERIMENTAL DATA
FEEDWATER
LOFT REACTOR
PRESSURE GRADIENTS
REACTOR SAFETY
STEAM SYSTEMS
TEMPERATURE GRADIENTS
THEORETICAL DATA
ACCIDENTS
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ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HYDROGEN COMPOUNDS
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NUMERICAL DATA
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SAFETY
TANK TYPE REACTORS
TEST REACTORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
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Light-Water Moderated
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