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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

1.8 Emergency Cooling Heat Transfer Problem of Nuclear Reactors

pages 203-222
DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf.90
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Краткое описание

Main heat transfer problems of emergency core cooling of pressurized water reactors and pressure tube graphite moderated reactors and their differences are considered. The results of some Soviet researches on the poet dry-out and the revet heat transfer for both types of reactors are presented.

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