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Thermal Safety Margins in Nuclear Reactors

Thermal Safety Margins in Nuclear Reactors PDF Author: Henryk Anglart
Publisher:
ISBN: 9781032185316
Category : Science
Languages : en
Pages : 0

Book Description
"This book presents an overview of state-of-the art approaches to determine thermal safety margins in nuclear reactors. It presents both the deterministic and probabilistic aspects of thermal safety margins of nuclear reactors to facilitate the understanding of these two difficult topics at various academic levels, from undergraduates to researchers in nuclear engineering. It first sets out the theoretical background before exploring how to determine thermal safety margins in nuclear reactors, through examples, problems and advanced state-of-the-art approaches. This will help undergraduate students better understand the most fundamental aspects of nuclear reactor safety. For researchers and practitioners, this book provides a comprehensive overview of most recent achievements in the field, offering an excellent starting point to develop new methods for the assessment of the thermal safety margins. This book is written to bridge the gap between deterministic and probabilistic methods to assess safety margins in nuclear reactors, presenting these approaches as complementary to each other. Even though these two approaches are frequently used in parallel in real-world applications (as risk-informed safety analyses), there has been a lack of a consistent teaching approach in this area. This book is suitable for readers with a background in calculus, thermodynamics, fluid mechanics, and heat transfer. It is assumed that readers have previous exposure to such concepts as laws of thermodynamics, enthalpy, entropy, and conservation equations used in fluid mechanics and heat transfer"--

Thermal Safety Margins in Nuclear Reactors

Thermal Safety Margins in Nuclear Reactors PDF Author: Henryk Anglart
Publisher:
ISBN: 9781032185316
Category : Science
Languages : en
Pages : 0

Book Description
"This book presents an overview of state-of-the art approaches to determine thermal safety margins in nuclear reactors. It presents both the deterministic and probabilistic aspects of thermal safety margins of nuclear reactors to facilitate the understanding of these two difficult topics at various academic levels, from undergraduates to researchers in nuclear engineering. It first sets out the theoretical background before exploring how to determine thermal safety margins in nuclear reactors, through examples, problems and advanced state-of-the-art approaches. This will help undergraduate students better understand the most fundamental aspects of nuclear reactor safety. For researchers and practitioners, this book provides a comprehensive overview of most recent achievements in the field, offering an excellent starting point to develop new methods for the assessment of the thermal safety margins. This book is written to bridge the gap between deterministic and probabilistic methods to assess safety margins in nuclear reactors, presenting these approaches as complementary to each other. Even though these two approaches are frequently used in parallel in real-world applications (as risk-informed safety analyses), there has been a lack of a consistent teaching approach in this area. This book is suitable for readers with a background in calculus, thermodynamics, fluid mechanics, and heat transfer. It is assumed that readers have previous exposure to such concepts as laws of thermodynamics, enthalpy, entropy, and conservation equations used in fluid mechanics and heat transfer"--

Thermal Safety Margins in Nuclear Reactors

Thermal Safety Margins in Nuclear Reactors PDF Author: Henryk Anglart
Publisher: CRC Press
ISBN: 1040034969
Category : Science
Languages : en
Pages : 502

Book Description
This book presents an overview of state-of-the art approaches to determine thermal safety margins in nuclear reactors. It presents both the deterministic and probabilistic aspects of thermal safety margins of nuclear reactors to facilitate the understanding of these two difficult topics at various academic levels, from undergraduates to researchers in nuclear engineering. It first sets out the theoretical background before exploring how to determine thermal safety margins in nuclear reactors, through examples, problems and advanced state-of-the-art approaches. This will help undergraduate students better understand the most fundamental aspects of nuclear reactor safety. For researchers and practitioners, this book provides a comprehensive overview of most recent achievements in the field, offering an excellent starting point to develop new methods for the assessment of the thermal safety margins. This book is written to bridge the gap between deterministic and appropriate treatment of uncertainties to assess safety margins in nuclear reactors, presenting these approaches as complementary to each other. Even though these two approaches are frequently used in parallel in real-world applications, there has been a lack of a consistent teaching approach in this area. This book is suitable for readers with a background in calculus, thermodynamics, fluid mechanics, and heat transfer. It is assumed that readers have previous exposure to such concepts as laws of thermodynamics, enthalpy, entropy, and conservation equations used in fluid mechanics and heat transfer. Key Features: • Covers the theory, principles, and assessment methods of thermal safety margins in nuclear reactors whilst presenting the state-of-the-art technology in the field • Combines the deterministic thermal safety considerations with a comprehensive treatment of uncertainties, offering a framework that is applicable to all current and future commercial nuclear reactor types • Provides numerous examples and problems to be solved Henryk Anglart is Professor Emeritus of Nuclear Engineering at the KTH Royal Institute of Technology, Stockholm, Sweden, and at the Warsaw University of Technology (WUT), Warsaw, Poland. He received his MSc from WUT and his PhD from the Rensselaer Polytechnic Institute, Troy, NY. After his eighteen year career as a research and development engineer at Westinghouse in Sweden, he accepted a tenure position at KTH, where he has supervised many PhD students and post-doctoral fellows, and has taught several courses in nuclear engineering. In addition to research and teaching, Prof. Henryk Anglart was serving for a long time as head of Reactor Technology Division, Deputy Director of the Physics Department, and Director of Nuclear Technology Center at KTH. Prof. Henryk Anglart authored and coauthored over 200 journals, conference and other scientific publications. He is also an author of three textbooks used in teaching of nuclear engineering courses at WUT and KTH, and two CRC Press books: Multilingual Dictionary of Nuclear Reactor Physics and Engineering, and Introduction to Sustainable Energy Transformation.

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

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.

Safety Analysis of Nuclear Reactor Thermal-Hydraulics

Safety Analysis of Nuclear Reactor Thermal-Hydraulics PDF Author: Liangming Pan
Publisher: Frontiers Media SA
ISBN: 2889668703
Category : Technology & Engineering
Languages : en
Pages : 106

Book Description


Implications of Power Uprates on Safety Margins of Nuclear Power Plants

Implications of Power Uprates on Safety Margins of Nuclear Power Plants PDF Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 188

Book Description
Dated September 2004

Design of the Reactor Core for Nuclear Power Plants

Design of the Reactor Core for Nuclear Power Plants PDF Author: IAEA
Publisher: International Atomic Energy Agency
ISBN: 9201076223
Category : Technology & Engineering
Languages : en
Pages : 87

Book Description
The reactor core is the central part of a nuclear reactor where nuclear fission occurs. It consists of four basic systems and components: the fuel (including fuel rods and the fuel assembly structure), the coolant, the moderator and the control rods, as well as additional structures such as reactor pressure vessel internals, core support plates, and the lower and upper internal structure in light water reactors. This Safety Guide provides recommendations on meeting the safety requirements established in IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), Safety of Nuclear Power Plants: Design, applied to the design of the reactor core for nuclear power plants. The publication addresses the safety aspects of the core design and includes neutronic, thermohydraulic, thermomechanical and structural mechanical aspects. Other aspects considered are those relating to reactor core control, shutdown and monitoring, and core management.

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

Light Water Reactor Sustainability Program Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor Demonstration Case Study

Light Water Reactor Sustainability Program Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor Demonstration Case Study PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about LWR design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the RISMC Pathway R & D is to support plant decisions for risk-informed margins management with the aim to improve economics, reliability, and sustain safety of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced?RISMC toolkit? that enables more accurate representation of NPP safety margin. This report describes the RISMC methodology demonstration where the Advanced Test Reactor (ATR) was used as a test-bed for purposes of determining safety margins. As part of the demonstration, we describe how both the thermal-hydraulics and probabilistic safety calculations are integrated and used to quantify margin management strategies.

Reactor Safety Study: an Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants

Reactor Safety Study: an Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants PDF Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category :
Languages : en
Pages : 814

Book Description


Heat Transfer in Nuclear Reactor Safety

Heat Transfer in Nuclear Reactor Safety PDF Author: S. George Bankoff
Publisher: McGraw-Hill Companies
ISBN:
Category : Heat
Languages : en
Pages : 984

Book Description