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Advanced Course in Heat Transfer in Nuclear Reactor Safety
September, 1-5, 1980, Dubrovnik, Yugoslavia

DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf


ISBN Print: 978-0-89116-223-0

1.2 Fundamental Studies on Heavy Water Reactor Thermalhydraulics

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

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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