A Heat Transfer Model for a Stratified Corium-Metal Pool in the Lower Plenum of a Nuclear Reactor
A Heat Transfer Model for a Stratified Corium-Metal Pool in the Lower Plenum of a Nuclear Reactor
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.
- University of North Texas United States
Design, Solidification Corium-Metal, Reactor Accidents, 510, Solidification, C Codes, Couple, Corium, Corium-Metal, Energy Conservation, 20 Fossil-Fueled Power Plants, Reactor Core, 22 General Studies Of Nuclear Reactors, Natural Convection, Safety Reports, Mathematical Models, Computing, Reactors, Heat Transfer, 99 General And Miscellaneous//Mathematics, 620, Solidification Model, And Information Science, 22 - General Studies Of Nuclear Reactors, Stratification, Pool, Simulation, Algorithms, Model
Design, Solidification Corium-Metal, Reactor Accidents, 510, Solidification, C Codes, Couple, Corium, Corium-Metal, Energy Conservation, 20 Fossil-Fueled Power Plants, Reactor Core, 22 General Studies Of Nuclear Reactors, Natural Convection, Safety Reports, Mathematical Models, Computing, Reactors, Heat Transfer, 99 General And Miscellaneous//Mathematics, 620, Solidification Model, And Information Science, 22 - General Studies Of Nuclear Reactors, Stratification, Pool, Simulation, Algorithms, Model
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