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EVALUATION OF THERMAL CONDUCTION BETWEEN TWO SUBCHANNELS WITH A COMPUTATIONAL FLUID DYNAMICS CODE

Hae-yong Jeong
Korea Atomic Energy Research Institute P.O. Box 105, Yuseong, Daejeon, 305-600, Korea

Kwi-seok Ha
Korea Atomic Energy Research Institute P.O. Box 105, Yuseong, Daejeon, 305-600, Korea

Yong-bum Lee
Korea Atomic Energy Research Institute P.O. Box 105, Yuseong, Daejeon, 305-600, Korea

Dohee Hahn
Korea Atomic Energy Research Institute P.O. Box 105, Yuseong, Daejeon, 305-600, Korea

F. E. Dunn
Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois, U.S.A.

J. E. Cahalan
Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois, U.S.A.

Abstract

An accurate thermal conduction model is required to develop a detailed three-dimensional thermal-hydraulics model for the application to liquid metal-cooled reactors. We generate the data of conduction correction factor for the liquid sodium through the CFX calculations. The correction factor is defined as the ratio of the local conduction heat flux to the average heat flux. The dependency of the data on Re is very weak and they are nearly constant for the given geometry and temperature difference. The data are useful for the development of a general thermal conduction model applicable to the existing sub-channel codes. The correction factor between 1.6 and 1.7 is recommended for a sodium-cooled reactor.

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