Thermal-Hydraulics of Water Cooled Nuclear Reactors
Thermal-Hydraulics of Water Cooled Nuclear Reactors

Author: Francesco D'Auria

Publisher: Woodhead Publishing

Published: 2017-05-18

Total Pages: 1200

ISBN-13: 0081006799

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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

Thermal Hydraulic Analysis of a Pressurized Water Reactor During Transient Conditions
Thermal Hydraulic Analysis of a Pressurized Water Reactor During Transient Conditions

Author: Edmund Page Coomes

Publisher:

Published: 1980

Total Pages: 282

ISBN-13:

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In this study a method has been demonstrated by which the departure from nucleate boiling ratio (DNBR) can be readily determined for nuclear transients through application of the COBRA-IIIC/MIT computer code. For input, boundary conditions were specified relating the time-dependent variations of core inlet coolant temperature, system pressure, core heat flux, and coolant flow. A model of the reactor core was developed for the computer code which was simple enough to be fast executing yet sufficiently detailed to provide DNBR results to within 1% of values reported in the Final Safety Analysis Report (FSAR) for the TROJAN nuclear power plant. Three transients were selected from the TROJAN FSAR for detailed analysis. The three cases involved transients of 20 seconds duration or less. Two transients, with incomplete information on the boundary conditions, resulted in minimum DNBR variations of 5% compared to the values in the FSAR. In these cases the time dependence of the calculated DNBR beyond the minimum point displayed significant deviation from the FSAR values. The third transient, with complete information, resulted in a minimum DNBR within 0.3% of the FSAR value. The time dependence of the calculated DNBR displayed no significant variation from the FSAR values.

The Thermal-hydraulics of a Boiling Water Nuclear Reactor
The Thermal-hydraulics of a Boiling Water Nuclear Reactor

Author: Richard T. Lahey

Publisher:

Published: 1993

Total Pages: 658

ISBN-13:

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This edition of the classic monograph gives a comprehensive overview of the thermal-hydraulic technology underlying the design, operation, and safety assessment of boiling water reactors. In addition, new material on pressure suppression containment technology is presented.

Thermal Analysis of Pressurized Water Reactors
Thermal Analysis of Pressurized Water Reactors

Author: Long-sun Tong

Publisher:

Published: 1996

Total Pages: 776

ISBN-13:

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The basic objective of this book is to present the principles underlying the thermal and hydraulic design of pressurized water reactors. In addition, the empirical data, engineering properties, and computer techniques required for design, but not available in conventional handbooks, are presented or referenced. Because of the many advances and changes that have occurred since the second edition, extensive improvements in both understanding the phenomena involved and in calculational techniques are reflected in the substantial additions to this third edition. Also, an additional chapter has been added to accommodate the many developments in the area of safety analysis.

Thermal-Hydraulic Analysis of Nuclear Reactors
Thermal-Hydraulic Analysis of Nuclear Reactors

Author: Bahman Zohuri

Publisher: Springer

Published: 2017-05-23

Total Pages: 845

ISBN-13: 3319538292

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This revised text covers the fundamentals of thermodynamics required to understand electrical power generation systems and the application of these principles to nuclear reactor power plant systems. The book begins with fundamental definitions of units and dimensions, thermodynamic variables and the Laws of Thermodynamics progressing to sections on specific applications of the Brayton and Rankine cycles for power generation and projected reactor systems design issues. It is not a traditional general thermodynamics text, per se, but a practical thermodynamics volume intended to explain the fundamentals and apply them to the challenges facing actual nuclear power plants systems, where thermal hydraulics comes to play. There have been significant new findings for intercooled systems since the previous edition published and they will be included in this volume. New technology plans for using a Nuclear Air-Brayton as a storage system for a low carbon grid are presented along with updated component sizes and performance criteria for Small Modular Reactors. Written in a lucid, straight-forward style while retaining scientific rigor, the content is accessible to upper division undergraduate students and aimed at practicing engineers in nuclear power facilities and engineering scientists and technicians in industry, academic research groups, and national laboratories. The book is also a valuable resource for students and faculty in various engineering programs concerned with nuclear reactors.