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Advances in Heat Transfer Engineering

ISSN:
1-56700-198-1 (Print)

MODELLING OF CRITICAL HEAT FLUX IN LONG TUBES AND TUBE BUNDLES WITH VIPRE02 AND RELAP5 CODES

Audrius Jasiulevicius
Paul Scherrer Institut, 5232 Villigen PSI, Switzerland; and Vattenfall Nuclear Fuel AB, 16287 Stockholm, Sweden

Bal Raj Sehgal
Nuclear Power Safety, Royal Institute of Technology, 100 44 STOCKHOLM, Sweden

Abstract

The paper describes the modelling of CHF and post-CHF heat transfer experiments. The series of wall temperature measurements in approximately 7.0 m long channels of 10 and 14.9 mm diameter were carried out during the 1970−1980 at the Royal Institute of Technology (RIT) in Stockholm, Sweden. The measurements were carried out under various pressures and flow conditions. In addition to the single channel experiments, a series of experiments on CHF occurrence in a rod bundles, placed in a 7.0 m long channel were carried out at the Kurchatov Institute (KI) in Moscow, Russia. These experimental data were used to validate the predictions of the CHF and post-CHF heat transfer obtained using thermal hydraulic code VIPRE02. Additional CHF correlations were implemented into the VIPRE02 code in order to allow better predictions of the CHF occurrence in long channels (RRC KI correlation) and under low-flow conditions (Khabenski correlation). The code calculation results were compared to the experimental data from the RIT and KI experiments. The VIPRE02 calculation results were benchmarked against the results, obtained using RELAP5/MOD3.3 code.