Proceedings of the Topical Meeting on Safety of Operating Reactors

Proceedings of the Topical Meeting on Safety of Operating Reactors PDF Author:
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 870

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Proceedings of the Topical Meeting on Safety of Operating Reactors

Proceedings of the Topical Meeting on Safety of Operating Reactors PDF Author:
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 870

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Book Description


Proceedings of the International Topical Meeting on Safety of Operating Reactors, San Francisco, California, October 11-14, 1998

Proceedings of the International Topical Meeting on Safety of Operating Reactors, San Francisco, California, October 11-14, 1998 PDF Author:
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 560

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Safety Margins of Operating Rectors

Safety Margins of Operating Rectors PDF Author: M. Antila
Publisher: International Atomic Energy Agency
ISBN: 9789201181022
Category : Business & Economics
Languages : en
Pages : 145

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Book Description
This TECDOC deals with a basic concept of safety margins and their role in assuring safety of nuclear Installations. The document describes capabilities of thermal hydraulic computer codes used to determine safety margins, evaluation of uncertainties, methods for safety margin evaluation and utilization of safety margins in operation and modifications of nuclear power plants.

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 : 1200

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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 International Topical Meeting on Advanced Reactors Safety

Proceedings of the International Topical Meeting on Advanced Reactors Safety PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 652

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Proceedings of the 15th Biennial Reactor Operations Division Topical Meeting on Reactor Operating Experience

Proceedings of the 15th Biennial Reactor Operations Division Topical Meeting on Reactor Operating Experience PDF Author:
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 496

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Proceedings of the International Topical Meeting on Fast Reactor Safety

Proceedings of the International Topical Meeting on Fast Reactor Safety PDF Author:
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 560

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Proceedings of the Sixteenth Reactor Operations International Topical Meeting

Proceedings of the Sixteenth Reactor Operations International Topical Meeting PDF Author:
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 402

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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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Safety Classification of Structures, Systems and Components in Nuclear Power Plants

Safety Classification of Structures, Systems and Components in Nuclear Power Plants PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201154132
Category : Reference
Languages : en
Pages : 34

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Book Description
This Safety Guide provides recommendations and guidance on how to meet the requirements established in Specific Safety Requirements No. SSR-2/1 and in General Safety Requirements No. GSR Part 4 for the identification of structures, systems and components (SSCs) important to safety in nuclear power plants and for their classification on the basis of their function and safety significance. This Safety Guide is intended primarily for use by organizations involved in the design of nuclear power plants, as well as by regulatory bodies and their technical support organizations. The Safety Guide can also be applied to other nuclear installations subject to appropriate adjustments relevant to the specific design of the type of the facility being considered.