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Book Thermo Hydraulics of Nuclear Reactors

Download or read book Thermo Hydraulics of Nuclear Reactors written by Christopher Earls Brennen and published by Cambridge University Press. This book was released on 2016-04-13 with total page 173 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book

    Book Details:
  • Author : 国立国会図書館 (Japan)
  • Publisher :
  • Release : 1972
  • ISBN :
  • Pages : 672 pages

Download or read book written by 国立国会図書館 (Japan) and published by . This book was released on 1972 with total page 672 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Thermo Hydraulics of Nuclear Reactors

Download or read book Thermo Hydraulics of Nuclear Reactors written by Christopher Earls Brennen and published by Cambridge University Press. This book was released on 2016-04-13 with total page 173 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book provides a summary of thermo-hydraulic analyses and design principles of nuclear reactors for electricity generation. It includes summaries of the causes for the three major nuclear power generation accidents, Three Mile Island, Chernobyl and Fukushima, and the major improvements to reactor safety that grew out of those accidents.

Book Proceedings of the ANS ASME NRC International Topical Meeting on Nuclear Reactor Thermal Hydraulics  Fundamental aspects of two phase flow and boiling heat transfer

Download or read book Proceedings of the ANS ASME NRC International Topical Meeting on Nuclear Reactor Thermal Hydraulics Fundamental aspects of two phase flow and boiling heat transfer written by and published by . This book was released on 1980 with total page 804 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Safety

Download or read book Nuclear Safety written by and published by . This book was released on 1978-05 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Thermal Hydraulics of Water Cooled Nuclear Reactors

Download or read book Thermal Hydraulics of Water Cooled Nuclear Reactors written by Francesco D'Auria and published by Woodhead Publishing. This book was released on 2017-05-18 with total page 1200 pages. Available in PDF, EPUB and Kindle. Book excerpt: Thermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors. Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes. The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis. This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability. - Contains a systematic and comprehensive review of current approaches to the thermal-hydraulic analysis of water-cooled and moderated nuclear reactors - Clearly presents the relationship between system level (top-down analysis) and component level phenomenology (bottom-up analysis) - Provides a strong focus on nuclear system thermal hydraulic (SYS TH) codes - Presents detailed coverage of the applications of thermal-hydraulics to demonstrate the safety and acceptability of nuclear power plants

Book Proceedings of Second International Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations

Download or read book Proceedings of Second International Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations written by Jirō Wakabayashi and published by . This book was released on 1986 with total page 1270 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Post Dryout Heat Transfer

Download or read book Post Dryout Heat Transfer written by G.F. Hewitt and published by Routledge. This book was released on 2017-10-06 with total page 446 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book Catalog of Copyright Entries  Third Series

Download or read book Catalog of Copyright Entries Third Series written by Library of Congress. Copyright Office and published by Copyright Office, Library of Congress. This book was released on 1979 with total page 1914 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Systems Volume I

Download or read book Nuclear Systems Volume I written by Neil E. Todreas and published by CRC Press. This book was released on 2021-01-12 with total page 768 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book National Union Catalog

Download or read book National Union Catalog written by and published by . This book was released on 1978 with total page 1040 pages. Available in PDF, EPUB and Kindle. Book excerpt: Includes entries for maps and atlases.

Book Nuclear Reactor Safety Heat Transfer

Download or read book Nuclear Reactor Safety Heat Transfer written by Owen C. Jones and published by Taylor & Francis Group. This book was released on 1981 with total page 1004 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1994-06 with total page 544 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Paper

Download or read book Paper written by and published by . This book was released on 1979 with total page 630 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book ASME Technical Papers

Download or read book ASME Technical Papers written by and published by . This book was released on 1979 with total page 558 pages. Available in PDF, EPUB and Kindle. Book excerpt: