Analysis of the late core melt progression phase of severe reactor accidents using the MELPROG code
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5781115
The two-dimensional (r-z) melt progression (MELPROG) computer code is being developed to analyze severe light water reactor accidents from accident initiation through vessel failure. The MELPROG code is comprised of several explicitly linked modules that analyze different aspects of an accident. If the fuel rods fragment, as happened at Three Mile Island (TMI), core melt progression is analyzed in the DEBRIS module (this module is also used to model rubble beds that can form in the lower plenum). Heat transfer, oxidation, melting, dissolution, melt relocation, and refreezing are all considered in the DEBRIS module. Vapor and coolant flow in the core and through the vessel are treated in the FLUIDS module. This module also models the relocation of solid and molten materials from the reactor core into the lower plenum. Detailed heat transfer and structural mechanics calculations are performed in the STRUCTURES module for the vessel walls, various support plates, the core baffle, the core barrel, core support columns, and other structures in the vessel. Three-dimensional, dynamic view factors are calculated in the RADIATION module that provides boundary conditions for the CORE, DEBRIS, and STRUCTURES modules. Results from a sample calculation are presented to demonstrate the capabilities of the code.
- OSTI ID:
- 5781115
- Report Number(s):
- CONF-881011-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 57
- Country of Publication:
- United States
- Language:
- English
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Light-Water Moderated
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
C CODES
CHEMICAL REACTIONS
COMPUTER CODES
CONTAINERS
CONTROL ELEMENTS
COOLING SYSTEMS
CORIUM
D CODES
DISSOLUTION
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
F CODES
FLUID MECHANICS
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
HYDRAULICS
M CODES
MECHANICS
MELTDOWN
OXIDATION
POROSITY
POWER REACTORS
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
S CODES
SAFETY
SHIELDS
TEMPERATURE DEPENDENCE
THERMAL REACTORS
THERMAL SHIELDS
THREE MILE ISLAND-2 REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS