Inscrição na biblioteca: Guest
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
Get accessGet access

RESUMO

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.

Portal Digital Begell Biblioteca digital da Begell eBooks Diários Referências e Anais Coleções de pesquisa Políticas de preços e assinaturas Begell House Contato Language English 中文 Русский Português German French Spain