MELCOR simulation of long-term station blackout at Peach Bottom
Conference
·
OSTI ID:6340478
This paper presents the results from MELCOR (Version 1.8BC) calculations of the Long-Term Station Blackout Accident Sequence, with failure to depressurize the reactor vessel, at the Peach Bottom (BWR Mark I) plant, and presents comparisons with Source Term Code Package (STCP) calculations of the same sequence. This sequence assumes that batteries are available for six hours following loss of all power to the plant. Following battery failure, the reactor coolant system (RCS) inventory is boiled off through the relief valves by continued decay heat generation. This leads to core uncovery, heatup, clad oxidation, core degradation, relocation, and, eventually, vessel failure at high pressure. STCP has calculated the transient out to 13.5 hours after core uncovery. The results include the timing of key events, pressure and temperature response in the reactor vessel and containment, hydrogen production, and the release of source terms to the environment. 12 refs., 23 figs., 3 tabs.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6340478
- Report Number(s):
- BNL-NUREG-44993; CONF-9010185--18; ON: DE91006348
- Country of Publication:
- United States
- Language:
- English
Similar Records
Analysis of long-term station blackout at Peach Bottom using MELCOR
Analysis of Long-Term Station Blackout without automatic depressurization at Peach Bottom using MELCOR (Version 1.8)
Analysis of Peach Bottom station blackout with MELCOR
Conference
·
Sun Dec 31 23:00:00 EST 1989
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:7089057
Analysis of Long-Term Station Blackout without automatic depressurization at Peach Bottom using MELCOR (Version 1.8)
Technical Report
·
Sun May 01 00:00:00 EDT 1994
·
OSTI ID:10159734
Analysis of Peach Bottom station blackout with MELCOR
Conference
·
Tue Dec 31 23:00:00 EST 1985
·
OSTI ID:7227226
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
BLACKOUTS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINMENT
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FISSION PRODUCT RELEASE
FLUID MECHANICS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
HYDRAULICS
M CODES
MECHANICS
PEACH BOTTOM-1 REACTOR
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
POWER REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
S CODES
SAFETY
SIMULATION
SOURCE TERMS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
BLACKOUTS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINMENT
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FISSION PRODUCT RELEASE
FLUID MECHANICS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
HYDRAULICS
M CODES
MECHANICS
PEACH BOTTOM-1 REACTOR
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
POWER REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
S CODES
SAFETY
SIMULATION
SOURCE TERMS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS