Anticipated transient without SCRAM experiments at LOFT
This paper discusses the experimental results for two anticipated transients without scram (ATWS) experiments, and compares computer code predictions with the experimental data. Experiment L9-3 simulated an ATWS in a commercial pressurized water reactor (PWR) initiated by a complete loss of feedwater and Experiment L9-4 simulated a loss-of-offsite-power-initiated (loss of feedwater and trip of the primary coolant pumps) ATWS. The LOFT facility is uniquely suited for ATWS experiments because it is a volumetrically scaled (1/44) experimental PWR designed to simulate the major components and system responses of larger commercial PWRs during both hypothesized loss-of-coolant accidents and anticipated transients. In both of the examined experiments, the primary system transient behavior was dominated by the interactions between the steam generator primary-to-secondary heat removal, the reactor kinetics, and the relief valve actuation. It is demonstrated that the discussed ATWS events can be controlled by properly sized automatic safety systems.
- Research Organization:
- Idaho National Engineering Lab., EG and G Idaho, Inc., Idaho Falls
- OSTI ID:
- 6693023
- Report Number(s):
- CONF-830446-
- Journal Information:
- Proc. Am. Power Conf.; (United States), Journal Name: Proc. Am. Power Conf.; (United States) Vol. 45; ISSN PAPWA
- Country of Publication:
- United States
- Language:
- English
Similar Records
Experiment data report for LOFT anticipated transient without scram Experiment L9-4
Experiment data report for LOFT anticipated transient-without-scram Experiment L9-3. [PWR]
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ACCIDENTS
AFTER-HEAT REMOVAL
ATWS
BOILERS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTROL EQUIPMENT
CONTROL SYSTEMS
EQUIPMENT
FLOW REGULATORS
FORECASTING
KINETICS
LOFT REACTOR
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR KINETICS
REACTORS
RELIEF VALVES
REMOVAL
RESEARCH AND TEST REACTORS
SIMULATION
STEAM GENERATORS
TANK TYPE REACTORS
TEST REACTORS
VALVES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS