Author: Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 742
Book Description
Proceedings of the International Topical Meeting on Advanced Reactors Safety
Author: Proceedings of the ANS/ASME/NRC International Topical Meeting on Nuclear Reactor Thermal-Hydraulics: LMFBR and HTGR advanced reactor concepts and analysis methods
Author: Advanced Reactor Safety Research Division Quarterly Progress Report
Author: Brookhaven National Laboratory. Department of Nuclear EnergyPublisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 150
Book Description
Proceedings of the International ANS/ENS Topical Meeting on Thermal Reactor Safety, San Diego, California, U.S.A., February 2-6, 1986
Author: American Nuclear SocietyPublisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 434
Book Description
Proceedings of the International Topical Meeting on Fast Reactor Safety
Author: Fast Spectrum Reactors
Author: Alan E. WaltarPublisher: Springer Science & Business Media
ISBN: 1441995722
Category : Technology & Engineering
Languages : en
Pages : 717
Book Description
This book is a complete update of the classic 1981 FAST BREEDER REACTORS textbook authored by Alan E. Waltar and Albert B. Reynolds, which , along with the Russian translation, served as a major reference book for fast reactors systems. Major updates include transmutation physics (a key technology to substantially ameliorate issues associated with the storage of high-level nuclear waste ), advances in fuels and materials technology (including metal fuels and cladding materials capable of high-temperature and high burnup), and new approaches to reactor safety (including passive safety technology), New chapters on gas-cooled and lead-cooled fast spectrum reactors are also included. Key international experts contributing to the text include Chaim Braun, (Stanford University) Ronald Omberg, (Pacific Northwest National Laboratory, Massimo Salvatores (CEA, France), Baldev Raj, (Indira Gandhi Center for Atomic Research, India) , John Sackett (Argonne National Laboratory), Kevan Weaver, (TerraPower Corporation) ,James Seinicki(Argonne National Laboratory). Russell Stachowski (General Electric), Toshikazu Takeda (University of Fukui, Japan), and Yoshitaka Chikazawa (Japan Atomic Energy Agency).
Proceedings of the 1994 Topical Meeting on Advances in Reactor Physics
Author: Proceedings of the Third International Topical Meeting on Reactor Thermal Hydraulics, Newport, Rhode Island, U.S.A., October 15-18, 1985
Author: Chong ChiuPublisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 684
Book Description
Thermal-Hydraulics of Water Cooled Nuclear Reactors
Author: Francesco D'AuriaPublisher: Woodhead Publishing
ISBN: 0081006799
Category : Technology & Engineering
Languages : en
Pages : 1200
Book Description
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
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