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1.8 Emergency Cooling Heat Transfer Problem of Nuclear Reactors

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

N. G. Rassohin
Moscow Power Engineering Institute, Moscow E-250, Krasnokazarmennaya Street, 14, USSR

要約

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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