Proceedings of Nuclear Thermal Hydraulics

Proceedings of Nuclear Thermal Hydraulics PDF Author: American Nuclear Society. Thermal Hydraulics Division. Meeting
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 704

Book Description


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

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

Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors

Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors PDF Author: Francesco D'Auria
Publisher: Elsevier
ISBN: 0323856071
Category : Business & Economics
Languages : en
Pages : 932

Book Description
Handbook on Thermal Hydraulics of Water-Cooled Nuclear Reactors, Volume 1, Foundations and Principles includes all new chapters which delve deeper into the topic, adding context and practical examples to help readers apply learnings to their own setting. Topics covered include experimental thermal-hydraulics and instrumentation, numerics, scaling and containment in thermal-hydraulics, as well as a title dedicated to good practices in verification and validation. This book will be a valuable reference for graduate and undergraduate students of nuclear or thermal engineering, as well as researchers in nuclear thermal-hydraulics and reactor technology, engineers working in simulation and modeling of nuclear reactors, and more. In addition, nuclear operators, code developers and safety engineers will also benefit from the practical guidance provided. - Presents a comprehensive analysis on the connection between nuclear power and thermal hydraulics - Includes end-of-chapter questions, quizzes and exercises to confirm understanding and provides solutions in an appendix - Covers applicable nuclear reactor safety considerations and design technology throughout

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

Book Description


Thermo-Hydraulics of Nuclear Reactors

Thermo-Hydraulics of Nuclear Reactors PDF Author: Christopher Earls Brennen
Publisher: Cambridge University Press
ISBN: 1107139600
Category : Science
Languages : en
Pages : 173

Book Description
This book provides a summary of thermo-hydraulic analyses and design principles of nuclear reactors for electricity generation. It includes summaries of the causes for the three major nuclear power generation accidents, Three Mile Island, Chernobyl and Fukushima, and the major improvements to reactor safety that grew out of those accidents.

Thorium—Energy for the Future

Thorium—Energy for the Future PDF Author: A.K. Nayak
Publisher: Springer
ISBN: 9811326584
Category : Technology & Engineering
Languages : en
Pages : 533

Book Description
This book comprises selected proceedings of the ThEC15 conference. The book presents research findings on various facets of thorium energy, including exploration and mining, thermo-physical and chemical properties of fuels, reactor physics, challenges in fuel fabrication, thorium fuel cycles, thermal hydraulics and safety, material challenges, irradiation experiences, and issues and challenges for the design of advanced thorium fueled reactors. Thorium is more abundant than uranium and has the potential to provide energy to the world for centuries if used in a closed fuel cycle. As such, technologies for using thorium for power generation in nuclear reactors are being developed worldwide. Since there is a strong global thrust towards designing nuclear reactors with thorium-based fuel, this book will be of particular interest to nuclear scientists, reactor designers, regulators, academics and policymakers.

Nuclear Systems Volume I

Nuclear Systems Volume I PDF Author: Neil E. Todreas
Publisher: CRC Press
ISBN: 1351030485
Category : Science
Languages : en
Pages : 768

Book Description
Nuclear Systems, Volume I: Thermal Hydraulic Fundamentals, Third Edition, provides an in-depth introduction to nuclear power, focusing on thermal hydraulic design and analysis of the nuclear core and other key nuclear plant components. The authors stress the integration of fluid flow and heat transfer as applied to all power reactor types and energy source distribution. They cover nuclear reactor concepts and systems, including GEN III+, GEN IV, and SMR reactors and new power cycles. The text includes new chapter examples and problems using concept parameters, full-color text and art, computer programs, figure slides, and a solutions manual. FEATURES Rigorous coverage of nuclear power generation fundamentals Description and analysis of the latest nuclear power plant designs and technologies Extensive examples in each chapter to illustrate the analysis methods which have been presented New full-color art and text features to enhance the presentation of topics Integration of fluid flow and heat transfer as applied to single- and two-phase coolants Readers will develop the knowledge and design skills needed to improve the next generation of nuclear reactors.

Nuclear Power Plant Engineering

Nuclear Power Plant Engineering PDF Author: James H. Rust
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 522

Book Description


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

Book Description


Nuclear Thermal Hydraulics

Nuclear Thermal Hydraulics PDF Author: Hajime Akimoto
Publisher: Springer
ISBN: 4431556036
Category : Technology & Engineering
Languages : en
Pages : 464

Book Description
This volume provides fundamentals of nuclear thermal–hydraulics for reactor design and safety assessment. It also describes the basis for assessing cooling performance of nuclear reactors under accidental conditions. The descriptions in this book are virtually self-contained, beyond the assumption that readers are familiar with the introductory levels of nuclear engineering. This book helps readers understand the processes for nuclear reactor plant design and the most important factors in nuclear thermal-hydraulics.