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:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 10141910
- 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; Other Information: PBD: [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
HEAT TRANSFER
HYDRAULICS
REACTOR SAFETY
REACTOR COOLING SYSTEMS
COMPUTER CALCULATIONS
M CODES
S CODES
CONTAINMENT
PRESSURIZATION
FISSION PRODUCT RELEASE
220900
210200
990200
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
MATHEMATICS AND COMPUTERS