Provides an examination of nuclear systems focusing on thermal hydraulic design and analysis of the nuclear core. The coverage includes fluid flow and heat transfer, various reactor types and energy source distribution.
Sprache
Verlagsort
Zielgruppe
Für höhere Schule und Studium
Für Beruf und Forschung
Gewicht
ISBN-13
978-0-89116-935-2 (9780891169352)
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Schweitzer Klassifikation
Thermal hydraulic characteristics of power reactors; thermal design principles; reactor heat generation; transport equations for single-phase flow; transport equations for two-phase flow; thermodynamics of nuclear energy conversion systems - non flow and steady-flow first and second law applications; thermal analysis of fuel elements; single-phase fluid mechanics; single-phase heat transfer; two-phase heat transfer.
