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Nuclear thermal hydraulics

Akimoto, Hajime.

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Nuclear thermal hydraulics

紀錄類型:	書目-電子資源 : Monograph/item
正題名/作者:	Nuclear thermal hydraulics/ by Hajime Akimoto ... [et al.].
其他作者:	Akimoto, Hajime.
出版者:	Tokyo :Springer Japan : : 2016.,
面頁冊數:	xviii, 458 p. :ill., digital ;24 cm.
內容註:	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.
Contained By:	Springer eBooks
標題:	Nuclear reactors - Fluid dynamics. -
電子資源:	http://dx.doi.org/10.1007/978-4-431-55603-9
ISBN:	9784431556039

Nuclear thermal hydraulics
Genshiryoku Kyokasho.English

Nuclear thermal hydraulics[electronic resource] /by Hajime Akimoto ... [et al.]. - Tokyo :Springer Japan :2016. - xviii, 458 p. :ill., digital ;24 cm. - An advanced course in nuclear engineering,2195-3708. - An advanced course in nuclear engineering..

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.

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.

ISBN: 9784431556039

Standard No.: 10.1007/978-4-431-55603-9doiSubjects--Topical Terms:

649459
Nuclear reactors
--Fluid dynamics.

LC Class. No.: TK9202

Dewey Class. No.: 621.483

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