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ISSN Online: 2377-424X

ISBN Print: 0-89116-559-2

International Heat Transfer Conference 8
August, 17-22, 1986, San Francisco, USA

A TWO-PHASE FLOW HEAT TRANSFER CORRELATION PACKAGE SUITABLE FOR A PRESSURIZED WATER REACTOR SAFETY CODE

Get access (open in a dialog) DOI: 10.1615/IHTC8.3410
pages 2529-2534

Abstract

This paper is a review of the heat transfer constitutive laws used in the nuclear reactor safety Cathare code. The description of the different stages of a loss-of-coolant accident entails the account for mechanical and thermal non-equilibria. In addition, a set of specifically designed experiments is needed to cover the whole range of parameters. In this context, the heat transfer modes encountered during blowdown and reflood are analysed. The agreement between code prediction and experiment is seen to be generally satisfactory.