Nuclear Thermal Hydraulics

This volume provides fundamentals of nuclear thermal–hydraulics for reactor design and safety assessment. It also describes the basis for assessing cooling performance of nuclear reactors under accidental conditions. The descriptions in this book are virtually self-contained, beyond the assumption t...

Πλήρης περιγραφή

Λεπτομέρειες βιβλιογραφικής εγγραφής
Κύριοι συγγραφείς: Akimoto, Hajime (Συγγραφέας), Anoda, Yoshinari (Συγγραφέας), Takase, Kazuyuki (Συγγραφέας), Yoshida, Hiroyuki (Συγγραφέας), Tamai, Hidesada (Συγγραφέας)
Συγγραφή απο Οργανισμό/Αρχή: SpringerLink (Online service)
Μορφή: Ηλεκτρονική πηγή Ηλ. βιβλίο
Γλώσσα:English
Έκδοση: Tokyo : Springer Japan : Imprint: Springer, 2016.
Σειρά:An Advanced Course in Nuclear Engineering, 4
Θέματα:
Διαθέσιμο Online:Full Text via HEAL-Link
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100 1 |a Akimoto, Hajime.  |e author. 
245 1 0 |a Nuclear Thermal Hydraulics  |h [electronic resource] /  |c by Hajime Akimoto, Yoshinari Anoda, Kazuyuki Takase, Hiroyuki Yoshida, Hidesada Tamai. 
264 1 |a Tokyo :  |b Springer Japan :  |b Imprint: Springer,  |c 2016. 
300 |a XVIII, 458 p. 197 illus.  |b online resource. 
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490 1 |a An Advanced Course in Nuclear Engineering,  |x 2195-3708 ;  |v 4 
505 0 |a The First Law of Thermodynamics -- Ideal gas and steam -- Second Law of Thermodynamics -- Gas Turbine Cycles and Steam Cycles -- Fundamental Equations of Flow -- Bernoulli's Equation (Mechanics of Ideal Fluids) -- Law of Momentum -- Motion of Viscous Fluid -- Laminar Flow and Turbulent Flow (The Similarity Rule) -- Pressure Propagation and Critical Flow(Compressible Fluid Flow) -- Two-phase Flow -- Flow Oscillations -- Reactor Heat Production -- Heat Conduction -- Convective Heat Transfer -- Boiling Heat Transfer and Critical Heat Flux -- Condensation Heat Transfer -- Radiative Heat Transfer -- Thermal Hydraulics inside the Reactor -- Reactor Thermal Design. . 
520 |a This volume provides fundamentals of nuclear thermal–hydraulics for reactor design and safety assessment. It also describes the basis for assessing cooling performance of nuclear reactors under accidental conditions. The descriptions in this book are virtually self-contained, beyond the assumption that readers are familiar with the introductory levels of nuclear engineering. This book helps readers understand the processes for nuclear reactor plant design and the most important factors in nuclear thermal-hydraulics. 
650 0 |a Energy. 
650 0 |a Nuclear energy. 
650 0 |a Thermodynamics. 
650 0 |a Heat engineering. 
650 0 |a Heat transfer. 
650 0 |a Mass transfer. 
650 0 |a Fluid mechanics. 
650 0 |a Nuclear engineering. 
650 1 4 |a Energy. 
650 2 4 |a Nuclear Energy. 
650 2 4 |a Nuclear Engineering. 
650 2 4 |a Engineering Thermodynamics, Heat and Mass Transfer. 
650 2 4 |a Engineering Fluid Dynamics. 
700 1 |a Anoda, Yoshinari.  |e author. 
700 1 |a Takase, Kazuyuki.  |e author. 
700 1 |a Yoshida, Hiroyuki.  |e author. 
700 1 |a Tamai, Hidesada.  |e author. 
710 2 |a SpringerLink (Online service) 
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830 0 |a An Advanced Course in Nuclear Engineering,  |x 2195-3708 ;  |v 4 
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