Analysis of results from a loss-of-offsite-power-initiated ATWS experiment in the LOFT Facility
An anticipated transient without scram (ATWS), initiated by loss-of-offsite power, was experimentally simulated in the Loss-of-Fluid Test (LOFT) pressurized water reactor (PWR). Primary system pressure was controlled using a scaled safety relief valve (SRV) representative of those in a commercial PWR, while reactor power was reduced by moderator reactivity feedback in a natural circulation mode. The experiment showed that reactor power decreases more rapidly when the primary pumps are tripped in a loss-of-offsite-power ATWS than in a loss-of-feedwater induced ATWS when the primary pumps are left on. During the experiment, the SRV had sufficient relief capacity to control primary system pressure. Natural circulation was effective in removing core heat at high temperature, pressure, and core power. The system transient response predicted using the RELAPS/MOD1 computer code showed good agreement with the experimental data.
- Research Organization:
- EG and G Idaho Inc., Idaho Falls, ID
- OSTI ID:
- 6703417
- Journal Information:
- Am. Soc. Mech. Eng., (Pap.); (United States), Vol. 83-HT-14
- 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
CIRCULATING SYSTEMS
COMPUTER CALCULATIONS
COMPUTER CODES
EXPERIMENTAL DATA
FEEDWATER
LOFT REACTOR
LOSS OF FLOW
POWER LOSSES
PRIMARY COOLANT CIRCUITS
PUMPS
R CODES
REACTOR COOLING SYSTEMS
REACTOR SAFETY
RELIEF VALVES
SIMULATION
ACCIDENTS
CONTROL EQUIPMENT
COOLING SYSTEMS
DATA
ENERGY LOSSES
ENERGY SYSTEMS
ENERGY TRANSFER
EQUIPMENT
FLOW REGULATORS
FLUID MECHANICS
HYDROGEN COMPOUNDS
INFORMATION
LOSSES
MECHANICS
NUMERICAL DATA
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
VALVES
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled