SCDAP/RELAP5 lower core plate model

Technical Report · Wed Sep 01 04:00:00 EDT 1999

DOI:https://doi.org/10.2172/752005· OSTI ID:752005

Coryell, E W ^[1]; Griffin, F P

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1. Lockheed Martin Idaho Technologies

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''.

• Research Organization: Idaho National Engineering and Environmental Lab., Idaho Falls, ID (US)
• Sponsoring Organization: N/A (US)
• DOE Contract Number: AC07-94ID13223
• OSTI ID: 752005
• Report Number(s): INEEL/EXT--99-01029
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS
ACCIDENT SIMULATIONS
CORE REGION
CORE SUPPORT STRUCTURES
CORIUM
MASS TRANSFER
MATHEMATICAL MODELS
MOLTEN MATERIAL
NUCLEAR REACTOR
OXIDATION
R CODES
REACTOR ACCIDENTS
REACTOR CORES
REACTOR SAFETY
S CODES
SCDAP/RELAP5
SUPPORTS
VESSEL LOWER HEAD