MELCOR analyses of severe accident scenarios in Oconee, a B W PWR plant
- Brookhaven National Lab., Upton, NY (United States)
- Nuclear Regulatory Commission, Washington, DC (United States)
This paper presents the results and insights gained from MELCOR analyses of two severe accident scenarios, a Loss of Coolant Accident (LOCA) and a Station Blackout (TMLB) in Oconee, a Babcock Wilcox (B W) designed PWR with a large dry containment, and comparisons with Source Term Code Package (STCP) calculations of the same sequences. Results include predicted timing of key events, thermal-hydraulic response in the reactor coolant system and containment, and environmental releases of fission products. The paper also explores the impact of varying concrete type, vessel failure temperature, and break location on the accident progression, containment pressurization, and environmental releases of radionuclides.
- Research Organization:
- Brookhaven National Lab., Upton, NY (United States)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6656939
- Report Number(s):
- BNL-NUREG-47994; CONF-930116-41; ON: DE93009539
- Resource Relation:
- Conference: Probabilistic safety assessment international topical meeting (PSA 93), Clearwater Beach, FL (United States), 27-29 Jan 1993
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
OCONEE-1 REACTOR
LOSS OF COOLANT
OCONEE-2 REACTOR
OCONEE-3 REACTOR
COMPUTER CALCULATIONS
CONTAINMENT
FISSION PRODUCT RELEASE
HEAT TRANSFER
HYDRAULICS
M CODES
PRESSURIZATION
REACTOR COOLING SYSTEMS
REACTOR SAFETY
S CODES
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
MECHANICS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
990200 - Mathematics & Computers