Steam generator behavior during loss-of-feedwater and loss-of-offsite-power ATWS experiments in LOFT

Conference · Tue Nov 01 04:00:00 EST 1983 · Am. Soc. Mech. Eng., (Pap.); (United States)

OSTI ID:6930555

Koizumi, Y; Behling, S R; Grush, W H

Two Anticipated Transient Without Scram (ATWS) experiments, L9-3 and L9-4, were conducted in the Loss-of-Fluid Test (LOFT) facility. The LOFT facility is a volumetrically scaled (1/44) pressurized water reactor (PWR) system with a nuclear core and is designed for integral loss-of-coolant accident/emergency core cooling experiments. Experiment L9-3 simulated a loss-of-feedwater ATWS in a commercial PWR; 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 by reactor kinetics in the core. Comparisons of RELAP5/MOD1 calculational results to the measured test data show that the degradation of the primary-to-secondary heat transfer and the transient response of the primary coolant system in both experiments were calculated well.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, Idaho
• OSTI ID: 6930555
• Report Number(s): CONF-831111-
• Conference Information: Journal Name: Am. Soc. Mech. Eng., (Pap.); (United States) Journal Volume: 83-WA/NE-3
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
BOILERS
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
ENERGY LOSSES
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
KINETICS
LOFT REACTOR
LOSS OF COOLANT
LOSSES
MECHANICS
PERFORMANCE
POWER LOSSES
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTORS
RESEARCH AND TEST REACTORS
SIMULATION
STEAM GENERATORS
TANK TYPE REACTORS
TEST REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS