Author: American Nuclear Society. Topical Meeting
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 476
Book Description
ANS Topical Meeting
Author: American Nuclear Society. Topical Meeting
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 476
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 476
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 Society
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 414
Book Description
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 414
Book Description
Proceedings of the ANS ... Topical Meeting on Robotics and Remote Systems
Author:
Publisher:
ISBN:
Category : Hot laboratories (Radioactive substances)
Languages : en
Pages : 532
Book Description
Publisher:
ISBN:
Category : Hot laboratories (Radioactive substances)
Languages : en
Pages : 532
Book Description
Proceedings of the ANS Seventh Topical Meeting on Robotics and Remote Systems, April 27 to May 1, 1997, Radisson Riverfront Hotel and Conference Center, Augusta, Georgia
Author:
Publisher:
ISBN:
Category : Hot laboratories (Radioactive substances)
Languages : en
Pages : 580
Book Description
Publisher:
ISBN:
Category : Hot laboratories (Radioactive substances)
Languages : en
Pages : 580
Book Description
Proceedings of the ANS/ASME/NRC International Topical Meeting on Nuclear Reactor Thermal-Hydraulics: LMFBR and HTGR advanced reactor concepts and analysis methods
Author:
Publisher:
ISBN:
Category : Heat
Languages : en
Pages : 872
Book Description
Publisher:
ISBN:
Category : Heat
Languages : en
Pages : 872
Book Description
Proceedings, ANS Topical Meeting, Reactor Safety Aspects of Fuel Behavior, August 2-6, 1981, Sun Valley, Idaho
Author:
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 572
Book Description
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 572
Book Description
Proceedings of the ANS/ASME/NRC International Topical Meeting on Nuclear Reactor Thermal-Hydraulics: Fundamental aspects of two-phase flow and boiling heat transfer
Author:
Publisher:
ISBN:
Category : Heat
Languages : en
Pages : 804
Book Description
Publisher:
ISBN:
Category : Heat
Languages : en
Pages : 804
Book Description
Thermal-Hydraulics of Water Cooled Nuclear Reactors
Author: Francesco D'Auria
Publisher: 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
Publisher: 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
Proceedings of the Fourteenth Topical Meeting on the Technology of Fusion Energy, October 15-19, 2000, Park City, Utah
Author:
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 906
Book Description
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 906
Book Description
Proceedings of the American Nuclear Society International Topical Meeting on Computer Applications for Nuclear Power Plant Operation and Control
Author:
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 874
Book Description
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 874
Book Description