A Heat Transfer Model for a Stratified Corium-Metal Pool in the Lower Plenum of a Nuclear Reactor

Technical Report · Sun Aug 01 00:00:00 EDT 1999

DOI:https://doi.org/10.2172/761806· OSTI ID:761806

Sohal, M S; Siefken, L J

This preliminary design report describes a model for heat transfer in a corium-metal stratified pool. It was decided to make use of the existing COUPLE model. Currently available correlations for natural convection heat transfer in a pool with and without internal heat generation were obtained. The appropriate correlations will be incorporated in the existing COUPLE model. Heat conduction and solidification modeling will be done with existing algorithms in the COUPLE. Assessment of the new model will be done by simple energy conservation problems.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: N/A (US)
• DOE Contract Number: AC07-94ID13223
• OSTI ID: 761806
• Report Number(s): INEEL/EXT-99-00763; TRN: US0004911
• Resource Relation: Other Information: PBD: 1 Aug 1999
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
20 FOSSIL-FUELED POWER PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
MATHEMATICAL MODELS
HEAT TRANSFER
C CODES
CORIUM
REACTOR ACCIDENTS
STRATIFICATION
SOLIDIFICATION
MODEL
CORIUM-METAL
POOL
COUPLE
NATURAL CONVECTION
REACTOR CORE