Thermo-Hydraulics of Nuclear Reactors PDF Download
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Author: Christopher Earls Brennen
Publisher: Cambridge University Press
ISBN: 1316682072
Category : Technology & Engineering
Languages : en
Pages : 173
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Book Description
This book provides a concise and up-to-date summary of the essential thermo-hydraulic analyses and design principles of nuclear reactors for electricity generation. Beginning with the basic nuclear physics, it leads through technical and quantitative analyses to descriptions of both the normal operation of the various modern nuclear reactor designs and the analyses of the possible departures from normal operation. It then describes both the postulated accident scenarios and summaries of the causes for the three major nuclear power generation accidents, Three Mile Island, Chernobyl and Fukushima, as well as the major improvements to reactor safety that grew out of those analyses and accidents.
Author: Owen C. Jones
Publisher:
ISBN:
Category : Heat
Languages : en
Pages : 360
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Book Description
Author: Owen C. Jones
Publisher:
ISBN:
Category : Heat
Languages : en
Pages : 348
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Book Description
Author: Christopher Earls Brennen
Publisher: Cambridge University Press
ISBN: 1316682072
Category : Technology & Engineering
Languages : en
Pages : 173
Get Book Here
Book Description
This book provides a concise and up-to-date summary of the essential thermo-hydraulic analyses and design principles of nuclear reactors for electricity generation. Beginning with the basic nuclear physics, it leads through technical and quantitative analyses to descriptions of both the normal operation of the various modern nuclear reactor designs and the analyses of the possible departures from normal operation. It then describes both the postulated accident scenarios and summaries of the causes for the three major nuclear power generation accidents, Three Mile Island, Chernobyl and Fukushima, as well as the major improvements to reactor safety that grew out of those analyses and accidents.
Author: Neil E. Todreas
Publisher: CRC Press
ISBN: 1351030485
Category : Science
Languages : en
Pages : 768
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Book Description
Nuclear Systems, Volume I: Thermal Hydraulic Fundamentals, Third Edition, provides an in-depth introduction to nuclear power, focusing on thermal hydraulic design and analysis of the nuclear core and other key nuclear plant components. The authors stress the integration of fluid flow and heat transfer as applied to all power reactor types and energy source distribution. They cover nuclear reactor concepts and systems, including GEN III+, GEN IV, and SMR reactors and new power cycles. The text includes new chapter examples and problems using concept parameters, full-color text and art, computer programs, figure slides, and a solutions manual. FEATURES Rigorous coverage of nuclear power generation fundamentals Description and analysis of the latest nuclear power plant designs and technologies Extensive examples in each chapter to illustrate the analysis methods which have been presented New full-color art and text features to enhance the presentation of topics Integration of fluid flow and heat transfer as applied to single- and two-phase coolants Readers will develop the knowledge and design skills needed to improve the next generation of nuclear reactors.
Author:
Publisher:
ISBN:
Category : Heat
Languages : en
Pages : 804
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Book Description
Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 860
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Book Description
Author: G.F. Hewitt
Publisher: Routledge
ISBN: 1351423312
Category : Science
Languages : en
Pages : 446
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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: Jason Chao
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 844
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Book Description
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 782
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Book Description
Author:
Publisher:
ISBN:
Category : Mechanics, Applied
Languages : en
Pages : 840
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Book Description
