Integrated TRAC/MELPROG analysis of core damage from a severe feedwater transient in the Oconee-1 PWR
Conference
·
OSTI ID:6255113
A postulated complete loss-of-feedwater event in the Oconee-1 pressurized water reactor has been analyzed. With an initial version of the lonked TRAC and MELPROG codes, we have modeled the loss-of-feedwater event from initiation to the time of complete disruption of the core, which was calculated to occur by 6800 s. The highest structure temperatures otuside the vessel are on the flow path from the vessel to the pressurizer relief valve. Temperatures in excess of 1200 K could result in failure and depressurization of the primary system before vessel failure.
- Research Organization:
- Los Alamos National Lab., NM (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 6255113
- Report Number(s):
- LA-UR-85-4173; CONF-860204-20; ON: TI86004723
- Country of Publication:
- United States
- Language:
- English
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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
220900* -- Nuclear Reactor Technology-- Reactor Safety
COMPUTERIZED SIMULATION
COOLING SYSTEMS
DAMAGE
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FEEDWATER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
MECHANICS
OCONEE-1 REACTOR
OXYGEN COMPOUNDS
POWER REACTORS
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SIMULATION
TEMPERATURE GRADIENTS
TRANSIENTS
VERY HIGH TEMPERATURE
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
COMPUTERIZED SIMULATION
COOLING SYSTEMS
DAMAGE
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FEEDWATER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
MECHANICS
OCONEE-1 REACTOR
OXYGEN COMPOUNDS
POWER REACTORS
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SIMULATION
TEMPERATURE GRADIENTS
TRANSIENTS
VERY HIGH TEMPERATURE
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS