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Início Arquivos Thermal Letter Representantes Futuras reuniões Assembléia das Conferências Internacionais de Transferência de Calor
International Heat Transfer Conference 7

ISSN: 2377-424X (online)
ISSN: 2377-4371 (flashdrive)


R. Semeria
Centre d'Etudes Nucleaires, Service des Transferts ThermiquesGrrenoble, France

H. Courtaud
Centre d'Etudes Nucleaires, Service des Transferts Thermiques Grenoble, France

J. Costa
Departement de Transfert et Conversion d'Energie, Service des Transferts Thermiques, Centre d'Etudes Nuclèaires de Grenoble, 85 X - 38041 Grenoble Cedex, France

DOI: 10.1615/IHTC7.4320
pages 241-252


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.

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