This book covers the basics behind thermal hydraulics. It explores the characteristics of power reactors, thermal design principles, and how reactors generate heat. The text also presents transport equations for single- and two-phase flows. The authors discuss the thermodynamics of nuclear energy conversion systems, including nuclear power plants and a simplified power system. They also consider the thermal analysis of fuel, single-phase fluid mechanics and heat transfer, and two-phase flow dynamics and heat transfer. The final chapter presents a steady-state analysis of a single heated channel. A solutions manual is available for qualifying instructors.
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6 of 6 people found the following review helpful:
5.0 out of 5 stars
Pretty much the base of everything you need to know,
This review is from: Nuclear Systems Volume I: Thermal Hydraulic Fundamentals (Paperback)
This book covers almost all aspects of thermal hydrolics in a nuclear reactor. It even has multiple correlations for flow through a core, and in general is totally dedicated to nuclear systems, unlike most heat transfer or fluid flow books. If you buy this book you would be smart to keep it over selling it back to the bookstore.
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Inside This Book
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First Sentence:
The energy source of a power reactor originates from the fission process within the fuel elements. Read the first page Key Phrases - Statistically Improbable Phrases (SIPs): (learn more)
fuel centerline temperature, nondeformable control volume, maximum fuel temperature, plant thermodynamic efficiency, separate flow model, fuel conductivity, linear heat rate, solid fuel pellet, thermal hydraulic characteristics, pressure drop components, acceleration pressure drop, friction pressure drop, pellet cracking, gap conductance, boiling length, friction pressure gradient, maximum useful work, churn flow, drop multiplier, moisture separation, equivalent annulus, integral transport equations, containment volume, friction multiplier, boiling heat flux Key Phrases - Capitalized Phrases (CAPs): (learn more)
New York, General Electric, Heat Mass Transfer, Department of Energy, Given Conditions, Multiphase Flow, Subchannel Mass Flowrate, Academic Press, American Nuclear Society, Derivation of Nusselt, Pergamon Press, The Control Mass Process Representation, Transport Phenomena New!
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Front Cover | Table of Contents | First Pages | Index | Back Cover | Surprise Me!
The energy source of a power reactor originates from the fission process within the fuel elements. Read the first page Key Phrases - Statistically Improbable Phrases (SIPs): (learn more)
fuel centerline temperature, nondeformable control volume, maximum fuel temperature, plant thermodynamic efficiency, separate flow model, fuel conductivity, linear heat rate, solid fuel pellet, thermal hydraulic characteristics, pressure drop components, acceleration pressure drop, friction pressure drop, pellet cracking, gap conductance, boiling length, friction pressure gradient, maximum useful work, churn flow, drop multiplier, moisture separation, equivalent annulus, integral transport equations, containment volume, friction multiplier, boiling heat flux Key Phrases - Capitalized Phrases (CAPs): (learn more)
New York, General Electric, Heat Mass Transfer, Department of Energy, Given Conditions, Multiphase Flow, Subchannel Mass Flowrate, Academic Press, American Nuclear Society, Derivation of Nusselt, Pergamon Press, The Control Mass Process Representation, Transport Phenomena New!
Books on Related Topics | Concordance | Text Stats Browse Sample Pages:
Front Cover | Table of Contents | First Pages | Index | Back Cover | Surprise Me!
Citations (learn more)
This book cites 33
books:
See all 33 books this book cites
- Transport Phenomena, 2nd Edition by R. Byron Bird on 5 pages
- Nuclear Heat Transport by Mohamed Mohamed El-Wakil on 5 pages
- Nuclear Systems Volume 2: Elements Of Thermal Design by Neil E. Todreas on page 338, and page 339
- Handbook of Heat Transfer by Warren Rohsenow on page 406, and page 572
- Convective Heat and Mass Transfer by William M. Kays on page 406, and page 458
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