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Author: G.F. Hewitt Publisher: Routledge ISBN: 1351423312 Category : Science Languages : en Pages : 446
Book Description
The study of post-dryout heat transfer has generated great interest because of its importance in determining maximum clad temperature in nuclear reactor loss-of-coolant accidents (LOCAs). An associated phenomenon, the deterioration of heat transfer in boiling, is significant to other industrial sectors. This book provides comprehensive coverage of post-dryout heat transfer, discussing such essential topics as post-dryout heat transfer in dispersed flow, interpretation and use of transient data in surface rewetting by reinstatement of flow or by reducing heat flux, rod bundles, two-phase flow occurrences in the post-dryout region, various methods for predicting ""inverted annular flow,"" and new experiments for measuring thermodynamic nonequilibrium with probes in the channel. The book also presents a basis for independent safety assessment of nuclear reactors and chemical plant systems where post-dryout heat transfer may occur. Post-Dryout Heat Transfer will be a useful reference for researchers and professionals in the nuclear and chemical production industries.
Author: G.F. Hewitt Publisher: Routledge ISBN: 1351423312 Category : Science Languages : en Pages : 446
Book Description
The study of post-dryout heat transfer has generated great interest because of its importance in determining maximum clad temperature in nuclear reactor loss-of-coolant accidents (LOCAs). An associated phenomenon, the deterioration of heat transfer in boiling, is significant to other industrial sectors. This book provides comprehensive coverage of post-dryout heat transfer, discussing such essential topics as post-dryout heat transfer in dispersed flow, interpretation and use of transient data in surface rewetting by reinstatement of flow or by reducing heat flux, rod bundles, two-phase flow occurrences in the post-dryout region, various methods for predicting ""inverted annular flow,"" and new experiments for measuring thermodynamic nonequilibrium with probes in the channel. The book also presents a basis for independent safety assessment of nuclear reactors and chemical plant systems where post-dryout heat transfer may occur. Post-Dryout Heat Transfer will be a useful reference for researchers and professionals in the nuclear and chemical production industries.
Author: Mirza Mohammed Shah Publisher: John Wiley & Sons ISBN: 1119618665 Category : Science Languages : en Pages : 384
Book Description
A guide to two-phase heat transfer theory, practice, and applications Designed primarily as a practical resource for design and development engineers, Two-Phase Heat Transfer contains the theories and methods of two-phase heat transfer that are solution oriented. Written in a clear and concise manner, the book includes information on physical phenomena, experimental data, theoretical solutions, and empirical correlations. A very wide range of real-world applications and formulas/correlations for them are presented. The two-phase heat transfer systems covered in the book include boiling, condensation, gas-liquid mixtures, and gas-solid mixtures. The author—a noted expert in this field—also reviews the numerous applications of two-phase heat transfer such as heat exchangers in refrigeration and air conditioning, conventional and nuclear power generation, solar power plants, aeronautics, chemical processes, petroleum industry, and more. Special attention is given to heat exchangers using mini-channels which are being increasingly used in a variety of applications. This important book: Offers a practical guide to two-phase heat transfer Includes clear guidance for design professionals by identifying the best available predictive techniques Reviews the extensive literature on heat transfer in two-phase systems Presents information to aid in the design and analysis of heat exchangers. Written for students and research, design, and development engineers, Two-Phase Heat Transfer is a comprehensive volume that covers the theory, methods, and applications of two-phase heat transfer.
Author: Adrian Bejan Publisher: John Wiley & Sons ISBN: 0471390151 Category : Technology & Engineering Languages : en Pages : 1496
Book Description
Chapters contributed by thirty world-renown experts. * Covers all aspects of heat transfer, including micro-scale and heat transfer in electronic equipment. * An associated Web site offers computer formulations on thermophysical properties that provide the most up-to-date values.
Author: Lixin Cheng Publisher: Bentham Science Publishers ISBN: 1608050947 Category : Science Languages : en Pages : 316
Book Description
"Multiphase flow and heat transfer have found a wide range of applications in several engineering and science fields such as mechanical engineering, chemical and petrochemical engineering, nuclear engineering, energy engineering, material engineering, ocea"
Author: Brent J. Lewis Publisher: John Wiley & Sons ISBN: 1119271541 Category : Science Languages : en Pages : 984
Book Description
Fundamental of Nuclear Engineering is derived from over 25 years of teaching undergraduate and graduate courses on nuclear engineering. The material has been extensively class tested and provides the most comprehensive textbook and reference on the fundamentals of nuclear engineering. It includes a broad range of important areas in the nuclear engineering field; nuclear and atomic theory; nuclear reactor physics, design, control/dynamics, safety and thermal-hydraulics; nuclear fuel engineering; and health physics/radiation protection. It also includes the latest information that is missing in traditional texts, such as space radiation. The aim of the book is to provide a source for upper level undergraduate and graduate students studying nuclear engineering.
Author: Richard W. Johnson Publisher: CRC Press ISBN: 1439849579 Category : Science Languages : en Pages : 1544
Book Description
Handbook of Fluid Dynamics offers balanced coverage of the three traditional areas of fluid dynamics—theoretical, computational, and experimental—complete with valuable appendices presenting the mathematics of fluid dynamics, tables of dimensionless numbers, and tables of the properties of gases and vapors. Each chapter introduces a different fluid dynamics topic, discusses the pertinent issues, outlines proven techniques for addressing those issues, and supplies useful references for further research. Covering all major aspects of classical and modern fluid dynamics, this fully updated Second Edition: Reflects the latest fluid dynamics research and engineering applications Includes new sections on emerging fields, most notably micro- and nanofluidics Surveys the range of numerical and computational methods used in fluid dynamics analysis and design Expands the scope of a number of contemporary topics by incorporating new experimental methods, more numerical approaches, and additional areas for the application of fluid dynamics Handbook of Fluid Dynamics, Second Edition provides an indispensable resource for professionals entering the field of fluid dynamics. The book also enables experts specialized in areas outside fluid dynamics to become familiar with the field.
Author: Neil E. Todreas Publisher: CRC Press ISBN: 0415802873 Category : Science Languages : en Pages : 1037
Book Description
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.
Author: Warren M. Rohsenow Publisher: McGraw-Hill ISBN: Category : Technology & Engineering Languages : en Pages : 1528
Book Description
This wholly revised edition of a classic handbook reference, written by some of the most eminent practitioners in the field, is designed to be your all-in-one source book on heat transfer issues and problem-solving. It includes the latest advances in the field, as well as covering subjects from microscale heat transfer to thermophysical properties of new refrigerants. An invaluable guide to this most crucial factor in virtually every industrial and environmental process.
Author: Henryk Anglart Publisher: CRC Press ISBN: 1040034969 Category : Science Languages : en Pages : 502
Book Description
This book presents an overview of state-of-the art approaches to determine thermal safety margins in nuclear reactors. It presents both the deterministic and probabilistic aspects of thermal safety margins of nuclear reactors to facilitate the understanding of these two difficult topics at various academic levels, from undergraduates to researchers in nuclear engineering. It first sets out the theoretical background before exploring how to determine thermal safety margins in nuclear reactors, through examples, problems and advanced state-of-the-art approaches. This will help undergraduate students better understand the most fundamental aspects of nuclear reactor safety. For researchers and practitioners, this book provides a comprehensive overview of most recent achievements in the field, offering an excellent starting point to develop new methods for the assessment of the thermal safety margins. This book is written to bridge the gap between deterministic and appropriate treatment of uncertainties to assess safety margins in nuclear reactors, presenting these approaches as complementary to each other. Even though these two approaches are frequently used in parallel in real-world applications, there has been a lack of a consistent teaching approach in this area. This book is suitable for readers with a background in calculus, thermodynamics, fluid mechanics, and heat transfer. It is assumed that readers have previous exposure to such concepts as laws of thermodynamics, enthalpy, entropy, and conservation equations used in fluid mechanics and heat transfer. Key Features: • Covers the theory, principles, and assessment methods of thermal safety margins in nuclear reactors whilst presenting the state-of-the-art technology in the field • Combines the deterministic thermal safety considerations with a comprehensive treatment of uncertainties, offering a framework that is applicable to all current and future commercial nuclear reactor types • Provides numerous examples and problems to be solved Henryk Anglart is Professor Emeritus of Nuclear Engineering at the KTH Royal Institute of Technology, Stockholm, Sweden, and at the Warsaw University of Technology (WUT), Warsaw, Poland. He received his MSc from WUT and his PhD from the Rensselaer Polytechnic Institute, Troy, NY. After his eighteen year career as a research and development engineer at Westinghouse in Sweden, he accepted a tenure position at KTH, where he has supervised many PhD students and post-doctoral fellows, and has taught several courses in nuclear engineering. In addition to research and teaching, Prof. Henryk Anglart was serving for a long time as head of Reactor Technology Division, Deputy Director of the Physics Department, and Director of Nuclear Technology Center at KTH. Prof. Henryk Anglart authored and coauthored over 200 journals, conference and other scientific publications. He is also an author of three textbooks used in teaching of nuclear engineering courses at WUT and KTH, and two CRC Press books: Multilingual Dictionary of Nuclear Reactor Physics and Engineering, and Introduction to Sustainable Energy Transformation.
Author: G.F. Hewitt
Author: G.F. Hewitt
Author: Mirza Mohammed Shah
Author: Adrian Bejan
Author: Lixin Cheng
Author: 
Author: Brent J. Lewis
Author: Richard W. Johnson
Author: Neil E. Todreas
Author: Warren M. Rohsenow
Author: Henryk Anglart