Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors PDF Download

Author: Francesco D'Auria
Publisher: Elsevier
ISBN: 0323856098
Category : Technology & Engineering
Languages : en
Pages : 818

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Book Description
Handbook on Thermal Hydraulics of Water-Cooled Nuclear Reactors, Volume 3, Procedures and Applications 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

Author: Donna Guillen
Publisher: BoD – Books on Demand
ISBN: 9535109871
Category : Technology & Engineering
Languages : en
Pages : 204

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Book Description
This book includes contributions from researchers around the world on numerical developments and applications to predict fluid flow and heat transfer, with an emphasis on thermal hydraulics computational fluid dynamics. Our ability to simulate larger problems with greater fidelity has vastly expanded over the past decade. The collection of material presented in this book augments the ever-increasing body of knowledge concerning the important topic of thermal hydraulics. Featured topics include coolant channel analysis, thermal hydraulic transport and mixing, as well as hydrodynamics and heat transfer processes. The contents of this book will interest researchers, scientists, engineers and graduate students.

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

Author: Jürgen Schmidt
Publisher: John Wiley & Sons
ISBN: 3527330275
Category : Technology & Engineering
Languages : en
Pages : 407

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Book Description
The safe operation of plants is of paramount importance in the chemical, petrochemical and pharmaceutical industries. Best practice in process and plant safety allows both the prevention of hazards and the mitigation of consequences. Safety Technology is continuously advancing to new levels and Computational Fluid Dynamics (CFD) is already successfully established as a tool to ensure the safe operation of industrial plants. With CFD tools, a great amount of knowledge can be gained as both the necessary safety measures and the economic operation of plants can be simultaneously determined. Young academics, safety experts and safety managers in all parts of the industry will henceforth be forced to responsibly judge these new results from a safety perspective. This is the main challenge for the future of safety technology. This book serves as a guide to elaborating and determining the principles, assumptions, strengths, limitations and application areas of utilizing CFD in process and plant safety, and safety management. The book offers recommendations relating to guidelines, procedures, frameworks and technology for creating a higher level of safety for chemical and petrochemical plants. It includes modeling aids and concrete examples of industrial safety measures for hazard prevention.

Author: Ferry Roelofs
Publisher: Woodhead Publishing
ISBN: 0081019815
Category : Science
Languages : en
Pages : 464

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Book Description
Thermal Hydraulics Aspects of Liquid Metal cooled Nuclear Reactors is a comprehensive collection of liquid metal thermal hydraulics research and development for nuclear liquid metal reactor applications. A deliverable of the SESAME H2020 project, this book is written by top European experts who discuss topics of note that are supplemented by an international contribution from U.S. partners within the framework of the NEAMS program under the U.S. DOE. This book is a convenient source for students, professionals and academics interested in liquid metal thermal hydraulics in nuclear applications. In addition, it will also help newcomers become familiar with current techniques and knowledge. - Presents the latest information on one of the deliverables of the SESAME H2020 project - Provides an overview on the design and history of liquid metal cooled fast reactors worldwide - Describes the challenges in thermal hydraulics related to the design and safety analysis of liquid metal cooled fast reactors - Includes the codes, methods, correlations, guidelines and limitations for liquid metal fast reactor thermal hydraulic simulations clearly - Discusses state-of-the-art, multi-scale techniques for liquid metal fast reactor thermal hydraulics applications

Author: IAEA
Publisher: International Atomic Energy Agency
ISBN: 9201004214
Category : Business & Economics
Languages : en
Pages : 121

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Book Description
This publication documents the results of an IAEA coordinated research project (CRP)on the application of computational fluid dynamics (CFD) codes for nuclear power plant design. The main objective was to benchmark CFD codes, model options and methods against CFD experimental data under single phase flow conditions. This publication summarizes the current capabilities and applications of CFD codes, and their present qualification level, with respect to nuclear power plant design requirements. It is not intended to be comprehensive, focusing instead on international experience in the practical application of these tools in designing nuclear power plant components and systems. The guidance in this publication is based on inputs provided by international nuclear industry experts directly involved in nuclear power plant design issues, CFD applications, and in related experimentation and validation highlighted during the CRP.

Author: Jovica Riznic
Publisher: Elsevier
ISBN: 0323853838
Category : Business & Economics
Languages : en
Pages : 587

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Book Description
Pressurized Heavy Water Reactors: Atucha-II, the eighth volume in the JSME Series on Thermal and Nuclear Power Generation, provides a comprehensive and complete review of a single type of reactor in a very accessible and practical way. The book presents a close analysis of the Atucha reactor, covering reactor physics, aging management of major components, and the role of codes in PHWR and Nuclear Regulation and Licensing. Including contemporary capabilities and challenges of nuclear technology, the book offers solutions and advice on common problems faced, guiding the reader through safe and approved processes that will help them reach suitable solutions. Professionals involved in lifecycle assessments and researchers interested in the development and improvement of nuclear energy technologies will gain a deep understanding of PHWR nuclear reactor physics, design and licensing. - A comprehensive reference on the latest research on Atucha Pressurized Heavy Water Reactors and their impact on sustainability goals - Analyzes The Atucha-2 BEPU and LBLOCA - Considers the licensing of Atucha-2, its physics and aging management of major components

Author:
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 216

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Book Description
Deterministic safety analysis is an important tool for confirming the adequacy and efficiency of provisions within the defence in depth concept for the safety of nuclear power plants (NPPs). IAEA Safety Standards Series No. NS-R-1.2 and Safety Reports Series No. 23 recommend, as one of the options for demonstrating the inclusion of adequate safety margins, the use of best estimate computer codes with realistic input data in combination with the evaluation of uncertainties in the calculation results. The evaluation of uncertainties is an issue of considerable complexity, and this Safety Report has been developed to complement the existing publications. It provides more detailed information on the methods available for the evaluation of uncertainties in deterministic safety analysis of NPPs and practical guidance in the use of these methods.

Author: Robert Martin
Publisher: World Scientific
ISBN: 9813275677
Category : Technology & Engineering
Languages : en
Pages : 717

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Book Description
This book captures the principles of safety evaluation as practiced in the regulated light-water reactor nuclear industry, as established and stabilized over the last 30 years. It is expected to serve both the current industry and those planning for the future. The work's coverage of the subject matter is the broadest to date, including not only the common topics of modeling and simulation, but also methods supporting the basis for the underlying assumptions, the extension to radiological safety, what to expect in a licensing review, historical perspectives and the implication for new designs.This text is an essential resource for practitioners and students, on the current best-practices in nuclear power plant safety and their basis. Contributors of this work are subject matter experts in their specialties, much of which was nurtured and inspired by Prof. Larry Hochreiter, a prominent nuclear safety pioneer.Related Link(s)

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.