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ISSN Online: 2377-424X

ISBN Print: 0-89116-299-2

International Heat Transfer Conference 7
September, 6-10, 1982, Munich, Germany

NUCLEAR SAFETY HEAT TRANSFER

Get access (open in a dialog) DOI: 10.1615/IHTC7.4320
pages 241-252

摘要

The coolability of the cores of nuclear reactors must be insured in any circumstances without significant pollution of the environment. The development of advanced safety computer codes describing the accidental behavior of the primary circuit nedds a better physical modeling of the coolant flows and heat transfers.
The part I is devoted to the Pressurized Water Reactors: a brief review is presented on transient burnout, post burnout heat transfer and boil-off phenomena.
In part II, the safety heat transfer problems of fast breeder reactors are presented. Boiling, clad melting, fuel-sodium interactions and post accident heat removal problem are described.