Anticipated transient without scram experiments at LOFT. [PWR]

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:6016333

Grush, W H; Varacalle, Jr, D J; Harvego, E A; Koizumi, Y

Two Anticipated Transient Without Scram (ATWS) experiments Experiments L9-3 and L9-4, were conducted in the Loss-of-Fluid Test (LOFT) pressurized water reactor (PWR). Experiment L9-3 simulated a loss-of-feedwater ATWS in a commercial PWR and Experiment L9-4 simulated a loss-of-offsite power ATWS. The system transient behavior in each experiment was dominated by interaction between the primary-to-secondary heat removal rate in the steam generator and reactor kinetics in the core. The results of the experiments showed that ATWS events can be controlled by properly sized automatic safety systems and that plant recovery can be accomplished (without inserting the control rods) with recovery procedures involving power-operated relief valve (PORV) cycling, secondary system feed and bleed, and boron injection. 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)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6016333
• Report Number(s): EGG-M-06983; CONF-830489-1; ON: DE83013673
• Resource Relation: Conference: 45. annual meeting of the American Power Conference, Houston, TX, USA, 18 Apr 1983; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ATWS
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
EXPERIMENTAL DATA
FLUID FLOW
LOFT REACTOR
PRESSURE GRADIENTS
REACTOR SAFETY
TEMPERATURE GRADIENTS
ACCIDENTS
DATA
ENERGY TRANSFER
FLUID MECHANICS
INFORMATION
MECHANICS
NUMERICAL DATA
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors