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), Journal Name: Am. Soc. Mech. Eng., (Pap.); (United States) Vol. 83-HT-14; ISSN ASMSA
- Country of Publication:
- United States
- Language:
- English
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Light-Water Moderated
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
CIRCULATING SYSTEMS
COMPUTER CALCULATIONS
COMPUTER CODES
CONTROL EQUIPMENT
COOLING SYSTEMS
DATA
ENERGY LOSSES
ENERGY SYSTEMS
ENERGY TRANSFER
EQUIPMENT
EXPERIMENTAL DATA
FEEDWATER
FLOW REGULATORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
INFORMATION
LOFT REACTOR
LOSS OF FLOW
LOSSES
MECHANICS
NUMERICAL DATA
OXYGEN COMPOUNDS
POWER LOSSES
PRESSURE GRADIENTS
PRIMARY COOLANT CIRCUITS
PUMPS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RELIEF VALVES
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
VALVES
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS