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

Proceedings of International Nuclear Power Plant Thermal Hydraulics and Operations Topical Meeting PDF Author:
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ISBN:
Category : Nuclear power plants
Languages : en
Pages :

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

Proceedings of International Nuclear Power Plant Thermal Hydraulics and Operations Topical Meeting PDF Author:
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages :

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

Proceedings of International Nuclear Power Plant Thermal Hydraulics and Operations Topical Meeting PDF Author: Jason Chao
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 844

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

Proceedings of Second International Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations PDF Author: Jirō Wakabayashi
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 1270

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Thermal-Hydraulics of Water Cooled Nuclear Reactors

Thermal-Hydraulics of Water Cooled Nuclear Reactors PDF Author: Francesco D'Auria
Publisher: Woodhead Publishing
ISBN: 0081006799
Category : Technology & Engineering
Languages : en
Pages : 1198

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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

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 464

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Proceedings of the 1999 Nureth-9 Conference

Proceedings of the 1999 Nureth-9 Conference PDF Author:
Publisher:
ISBN: 9780894486500
Category : Technology & Engineering
Languages : en
Pages :

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Proceedings of the ANS/ASME/NRC International Topical Meeting on Nuclear Reactor Thermal-Hydraulics: LMFBR and HTGR advanced reactor concepts and analysis methods

Proceedings of the ANS/ASME/NRC International Topical Meeting on Nuclear Reactor Thermal-Hydraulics: LMFBR and HTGR advanced reactor concepts and analysis methods PDF Author:
Publisher:
ISBN:
Category : Heat
Languages : en
Pages : 872

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

Proceedings of the ANS/ASME/NRC International Topical Meeting on Nuclear Reactor Thermal-Hydraulics: Fundamental aspects of two-phase flow and boiling heat transfer PDF Author:
Publisher:
ISBN:
Category : Heat
Languages : en
Pages : 804

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Proceedings of the Third International Topical Meeting on Reactor Thermal Hydraulics, Newport, Rhode Island, U.S.A., October 15-18, 1985

Proceedings of the Third International Topical Meeting on Reactor Thermal Hydraulics, Newport, Rhode Island, U.S.A., October 15-18, 1985 PDF Author: Chong Chiu
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 684

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Proceedings of the U.S. Nuclear Regulatory Commission ... Water Reactor Safety Research Information Meeting

Proceedings of the U.S. Nuclear Regulatory Commission ... Water Reactor Safety Research Information Meeting PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 518

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