Overview of TUF Code for CANDU Reactors

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W.S. Liu
R.K. Leung
J.C. Luxat

Abstract

An overview of the TUF code is presented. The important physical parameters used in the following code modules are briefly discussed: reactor control and safety systems, thermal-hydraulics, heat conduction, reactor physics and system components. The approach for code qualification as an analytical tool for CANDU reactors is described.

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