9781439808870

Book Description: Florence, Kentucky, U.S.A.: Taylor & Francis, 2011. Hardcover. Book Condition: New. BRAND NEW US edition / [hardcover] [2nd edition] / FREE UPGRADE to FedEx Express, UPS Express or Priority Mail / receive your book within 1-4 business days! / [clean wrapped, well protected] [Authentic edition exactly the same as the Official Listing] [ships out within 1 business day] / Comes with free tracking number / Genuine US Bookstore / Definitely in stock! Get your book in perfect condition! We also ship international! International orders ship via FedEx, UPS, or USPS Express!. Bookseller Inventory # ABE-10034412505

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Book Description: Taylor & Francis. Book Condition: New. 1439808872 HARDCOVER. NEW. Never used. We do not ship to PO Box/APO/FPO addresses. Bookseller Inventory # 1439808872-11

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Book Description: Florence, Kentucky, U.S.A.: Taylor & Francis, 2011. Hardcover. Book Condition: New. Ship out 1-2 business day,Brand new,US edition, Free tracking number usually 2-4 biz days delivery to worldwide Same shipping fee with US, Canada,Europe country, Australia, item will ship out from either LA or Asia ht. Bookseller Inventory # ABE-9901849409

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Book Description: Taylor and Francis, 2011. Hardback. Book Condition: New. New Book. Shipped from UK. Bookseller Inventory # FT-9781439808870

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Book Description: Book Condition: Brand New. New. US edition. Customer Satisfaction guaranteed!!. Bookseller Inventory # SHUB22448

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Book Description: Book Condition: New. Bookseller Inventory # 12459668-n

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Book Description: Taylor and Francis, 2011. Hardback. Book Condition: New. New Book. Shipped from UK. Bookseller Inventory # FT-9781439808870

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Book Description: Taylor Francis Inc, United States, 2011. Hardback. Book Condition: New. 2nd Revised edition. 235 x 156 mm. Brand New Book. Nuclear power is in the midst of a generational change-with new reactor designs, plant subsystems, fuel concepts, and other information that must be explained and explored-and after the 2011 Japan disaster, nuclear reactor technologies are, of course, front and center in the public eye. Written by leading experts from MIT, Nuclear Systems Volume I: Thermal Hydraulic Fundamentals, Second Edition provides an in-depth introduction to nuclear power, with a focus on thermal hydraulic design and analysis of the nuclear core. A close examination of new developments in nuclear systems, this book will help readers-particularly students-to develop the knowledge and design skills required to improve the next generation of nuclear reactors.Includes a CD-ROM with Extensive Tables for Computation Intended for experts and senior undergraduate/early-stage graduate students, the material addresses: Different types of reactors Core and plant performance measures Fission energy generation and deposition Conservation equations Thermodynamics Fluid flow Heat transfer Imparting a wealth of knowledge, including their longtime experience with the safety aspects of nuclear installations, authors Todreas and Kazimi stress the integration of fluid flow and heat transfer, various reactor types, and energy source distribution. They cover recent nuclear reactor concepts and systems, including Generation III+ and IV reactors, as well as new power cycles. The book features new chapter problems and examples using concept parameters, and a solutions manual is available with qualifying course adoption. Bookseller Inventory # AA69781439808870

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Book Description: Book Condition: Brand New. Brand New Original US Edition, Perfect Condition. Printed in English. Excellent Quality, Service and customer satisfaction guaranteed!. Bookseller Inventory # USA-29393

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Book Description: Taylor and Francis(Taylor and Francis), 2011. Hardback. Book Condition: New. REV Edition Number is 2. 9.252 by 6.142 inches. (1034 pages) Nuclear power is in the midst of a generational change?with new reactor designs, plant subsystems, fuel concepts, and other information that must be explained and explored?and after the 2011 Japan disaster, nuclear reactor technologies are, of course, front and center in the public eye. Written by leading experts from MIT, Nuclear Systems Volume I: Thermal Hydraulic Fundamentals, Second Edition provides an in-depth introduction to nuclear power, with a focus on thermal hydraulic design and analysis of the nuclear core. A close examination of new developments in nuclear systems, this book will help readers?particularly students?to develop the knowledge and design skills required to improve the next generation of nuclear reactors. Includes a CD-ROM with Extensive Tables for Computation Intended for experts and senior undergraduate/early-stage graduate students, the material addresses: Different types of reactors Core and plant performance measures Fission energy generation and deposition Conservation equations Thermodynamics Fluid flow Heat transfer Imparting a wealth of knowledge, including their longtime experience with the safety aspects of nuclear installations, authors Todreas and Kazimi stress the integration of fluid flow and heat transfer, various reactor types, and energy source distribution. They cover recent nuclear reactor concepts and systems, including Generation III+ and IV reactors, as well as new power cycles. The book features new chapter problems and examples using concept parameters, and a solutions manual is available with qualifying course adoption. Principal Characteristics of Power Reactors Introduction Power Cycles Primary Coolant Systems Reactor Cores Fuel Assemblies Advanced Water- and Gas-Cooled Reactors (Generation III And III+) Advanced Thermal and Fast Neutron Spectrum Reactors (Generation IV) References Problems Thermal Design Principles and Application Introduction Overall Plant Characteristics Influenced by Thermal Hydraulic Considerations Energy Production and Transfer Parameters Thermal Design Limits Thermal Design Margin Figures of Merit for Core Thermal Performance The Inverted Fuel Array The Equivalent Annulus Approximation References Problems Reactor Energy Distribution Introduction Energy Generation and Deposition Fission Power and Calorimetric (Core Thermal) Power Power Profiles in Reactor Cores Energy Generation Rate within a Fuel Pin Energy Deposition Rate within The Moderator Shutdown Energy Generation Rate Stored Energy Sources References Problems Transport Equations for Single-Phase Flow Introduction Mathematical Relations Lumped Parameter Integral Approach Distributed Parameter Integral Approach Differential Conservation Equations Turbulent Flow References Problems Transport Equations for Two-Phase Flow Introduction Averaging Operators for Two-Phase Flow Volume-Averaged Properties Area-Averaged Properties Mixture Equations for One-Dimensional Flow Control-Volume Integral Transport Equations One-Dimensional Space-Averaged Transport Equations References Problems Thermodynamics of Nuclear Energy Conversion Systems: Nonflow and Steady Flow: First and Second Law Applications Introduction Nonflow Process Thermodynamic Analysis of Nuclear Power Plants Thermodynamic Analysis of a Simplified Pwr System More Complex Rankine Cycles: Superheat, Reheat, Regeneration, and Moisture Separation Simple Brayton Cycle More Complex Brayton Cycles Reference Problems Thermodynamics of Nuclear Energy Conversion Systems: Nonsteady Flow First Law Analysis Introduction Containment Pressurization Process Response of a PWR Pressurizer to Load Changes References Problems Thermal Analysis of Fuel Elements Introduction Heat Conduction in Fuel Elements Thermal Properties of UO 2 and MO x Temperature Distribution in Plate Fuel Elements Temperature Distribution in Cylindrical Fuel Pins Temperature Distribution in Restructured Fuel Elements Thermal Resistance Between Fuel and Coolant References Problems. Bookseller Inventory # AG1439808872

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