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EXPERIMENTAL DETERMINATION OF CRITICAL HEAT FLUX

DOI: 10.1615/AnnualRevHeatTransfer.2020033345
pages 29-57

Arnab Dasgupta
Reactor Engineering Division, Bhabha Atomic Research Centre, Mumbai-400085, India

A. K. Vishnoi
Reactor Engineering Division, Bhabha Atomic Research Centre Mumbai, Maharashtra, India

Dinesh K. Chandraker
Reactor Engineering Division, Bhabha Atomic Research Centre, Mumbai-400085, India

Arun Kumar Nayak
Homi Bhabha National Institute, Anushakti Nagar, Mumbai 400094, Maharashtra, India; Reactor Engineering Division, Bhabha Atomic Research Centre, Mumbai-400085, India


KEY WORDS: CHF experiments, CHF detection, rod bundle

Abstract

Experiments have been, and still are, the cornerstone of critical heat flux (CHF) determination, especially for nuclear fuel rod bundles. The standard technique involves conducting experiments and using the experimental data to develop suitable correlations. Historically, the experiments have provided essential information, leading to better understanding of CHF mechanisms. This chapter gives an overview of the experimental techniques for CHF determination and introduces readers to tubular and rod bundle experiments through a detailed account. Classification of CHF correlations are also introduced in the chapter. It is further emphasized that although correlations are widely used, they have limitations. Such CHF experiments are also used to validate the analytical CHF models and develop closures for such models.

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