Physical modelling of the in-vessel phases of severe reactor accidents: The MELPROG/TRAC computer code
Conference
·
OSTI ID:5226073
The MELPROG/TRAC computer code is the USNRC's bes-estimate model for analysis of phenomena in the rector vessel and reactor coolant system associated with the progression of severe accidents in light water reactors. Although versions exist for both boiling water reactors and pressurized water reactors, we confine our discussion herein to the pressurized water reactor. The structure of MELPROG/TRAC will be briefly summarized, its capabilities will be outlined, and results from typical analyses will be noted. As a specific example, differences in the initiation phase of a station blackout accident caused by pump seal failures will be described. finally, the experimental and analytical efforts to assess the modelling basis for MELPROG/TRAC will be outlined.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA); Los Alamos National Lab., NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5226073
- Report Number(s):
- SAND-87-2522C; CONF-880309-3; IAEA-SM-296/97; ON: DE88008117
- Country of Publication:
- United States
- Language:
- English
Similar Records
Integrated MELPROG/TRAC analyses of a PWR station blackout
MELPROG-POW/MOD1: A two-dimensional, mechanistic code for analysis of reactor core melt progression and vessel attack under severe accident conditions
MELPROG-PWR/MOD0: A mechanistic code for analysis of reactor core melt progression and vessel attack under severe accident conditions
Conference
·
Sat Dec 31 23:00:00 EST 1988
·
OSTI ID:5910067
MELPROG-POW/MOD1: A two-dimensional, mechanistic code for analysis of reactor core melt progression and vessel attack under severe accident conditions
Technical Report
·
Mon May 01 00:00:00 EDT 1989
·
OSTI ID:6107175
MELPROG-PWR/MOD0: A mechanistic code for analysis of reactor core melt progression and vessel attack under severe accident conditions
Technical Report
·
Tue Mar 31 23:00:00 EST 1987
·
OSTI ID:6096786
Related Subjects
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Nonboiling Water Cooled
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REACTOR ACCIDENTS
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REACTOR VESSELS
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ACCIDENTS
BLACKOUTS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINERS
CONTROL EQUIPMENT
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EQUIPMENT
FLOW REGULATORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
M CODES
MECHANICS
PUMPS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTOR VESSELS
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RISK ASSESSMENT
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SEALS
SIMULATION
TRANSIENTS
VALVES
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WATER MODERATED REACTORS