
doi: 10.2172/752005 , 10.2172/911487
The SCDAP/RELAP5 computer code is a best-estimate analysis tool for performing nuclear reactor severe accident simulations. This report describes the justification, theory, implementation, and testing of a new modeling capability which will refine the analysis of the movement of molten material from the core region to the vessel lower head. As molten material moves from the core region through the core support structures it may encounter conditions which will cause it to freeze in the region of the lower core plate, delaying its arrival to the vessel head. The timing of this arrival is significant to reactor safety, because during the time span for material relocation to the lower head, the core may be experiencing steam-limited oxidation. The time at which hot material arrives in a coolant-filled lower vessel head, thereby significantly increasing the steam flow rate through the core region, becomes significant to the progression and timing of a severe accident. This report is a revision of a report INEEL/EXT-00707, entitled ``Preliminary Design Report for SCDAP/RELAP5 Lower Core Plate Model''.
Reactor Safety, Core Region, Vessel Lower Head, Accident Simulations, Mathematical Models, Supports, S Codes, Computing, Mass Transfer Scdap/Relap5, 22 Nuclear Reactor Technology, Reactor Cores, 99 Mathematics, Reactor Accidents, 620, 22 - General Studies Of Nuclear Reactors Accident Simulations, Molten Material, Nuclear Reactor, Scdap/Relap5, And Information Science, Oxidation, Corium, Core Support Structures, R Codes
Reactor Safety, Core Region, Vessel Lower Head, Accident Simulations, Mathematical Models, Supports, S Codes, Computing, Mass Transfer Scdap/Relap5, 22 Nuclear Reactor Technology, Reactor Cores, 99 Mathematics, Reactor Accidents, 620, 22 - General Studies Of Nuclear Reactors Accident Simulations, Molten Material, Nuclear Reactor, Scdap/Relap5, And Information Science, Oxidation, Corium, Core Support Structures, R Codes
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