MELCOR analyses of severe accident scenarios in Oconee, a B&W PWR plant

Conference · Mon Mar 01 04:00:00 EST 1993

OSTI ID:10141910

Madni, I K; Nimnual, S ^[1]; Foulds, R ^[2]

---

1. Brookhaven National Lab., Upton, NY (United States)
2. 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
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
COMPUTER CALCULATIONS
CONTAINMENT
FISSION PRODUCT RELEASE
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
M CODES
MATHEMATICS AND COMPUTERS
OCONEE-1 REACTOR
OCONEE-2 REACTOR
OCONEE-3 REACTOR
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PRESSURIZATION
REACTOR COOLING SYSTEMS
REACTOR SAFETY
S CODES