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1.2 Fundamental Studies on Heavy Water Reactor Thermalhydraulics

DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf.30
pages 49-85

S. Banerjee
Department of Engineering Physics, McMaster University, Hamilton, Ontario L85 4M1 Canada

R. E. Nieman
Thermalhydraulics Research Branch, Whiteshell Nuclear Research Establishment, Atomic Energy of Canada Limited, Pinawa, Manitoba ROE 1LO Canada

Abstract

The status of thermalhydraulics research associated with heavy-water-moderated, pressure tube reactors is reviewed and the motivation for some of the research is discussed in the context of the CANDU system. Results of the application of simple homogeneous flow boiling models to various experiments are presented and systematic deviations from the experimental data are attributed to mechanical and thermal non-equilibrium. A two-fluid model which incorporates these effects is presented and applied to fundamental experiments involving rewetting, wave propagation and critical flow. Requirements for new experiments and further model developments are outlined.

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