作者: R.W. Graham , Y.Y. Hsu
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摘要: The book includes an appendix that describes advances made in two-phase flow as applicable to reactor safety code modeling. It is considered by many be the definitive work field. Current theories on boiling and well supercritical heat transfer are presented. Also examined similarities dissimilarities mechanism of two modes transfer. Research has demonstrated behavior highly affected stability dynamics entire system. Interest study a increasing, possibly due increased interest high pressure water nuclear reactors. Introductions summaries included for each chapter.