Corrosion Issues in Light Water Reactors Book

Corrosion Issues in Light Water Reactors


  • Author : D Féron
  • Publisher : Elsevier
  • Release Date : 2007-06-22
  • Genre: Technology & Engineering
  • Pages : 368
  • ISBN 10 : 9781845693466

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Corrosion Issues in Light Water Reactors Excerpt :

Stress corrosion cracking is a major problem in light water nuclear reactors, whether pressurised water reactors (PWRs) or boiling water reactors (BWRs). The nuclear industry needs to be able to predict the service life of these power plants and develop appropriate maintenance and repair practices to ensure safe long term operation. This important book sums up key recent research on corrosion in light water reactors and its practical applications. The book is divided into four parts. It begins with an overview of materials degradation due to stress corrosion, corrosion potential monitoring and passivation. Part two summarises research on susceptibility of materials to stress corrosion cracking and the ways it can be initiated. The third part of the book considers stress corrosion crack propagation processes whilst the final part includes practical case studies of corrosion in particular plants. The book reviews corrosion in a range of materials such as low alloy steels, stainless steels and nickel-based alloys. With its distinguished editor and team of contributors, Corrosion issues in light water reactors is a standard work for the nuclear industry. Summarises key recent research on corrosion in light water reactors Includes practical case studies

Electrochemistry in Light Water Reactors Book

Electrochemistry in Light Water Reactors


  • Author : R-W Bosch
  • Publisher : Elsevier
  • Release Date : 2007-04-30
  • Genre: Technology & Engineering
  • Pages : 240
  • ISBN 10 : 9781845693022

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Electrochemistry in Light Water Reactors Excerpt :

There has long been a need for effective methods of measuring corrosion within light water nuclear reactors. This important volume discusses key issues surrounding the development of high temperature reference electrodes and other electrochemical techniques. The book is divided into three parts with part one reviewing the latest developments in the use of reference electrode technology in both pressurised water and boiling water reactors. Parts two and three cover different types of corrosion and tribocorrosion and ways they can be measured using such techniques as electrochemical impedance spectroscopy. Topics covered across the book include in-pile testing, modelling techniques and the tribocorrosion behaviour of stainless steel under reactor conditions. Electrochemistry in light water reactors is a valuable reference for all those concerned with corrosion problems in this key technology for the power industry. Discusses key issues surrounding the development of high temperature reference eletrodes A valuable reference for all concerned with corrosion problems in this key technology

Corrosion Issues in Light Water Reactors Book

Corrosion Issues in Light Water Reactors


  • Author : D. Féron
  • Publisher : Unknown
  • Release Date : 2007
  • Genre: Light water reactors
  • Pages : 340
  • ISBN 10 : 1439824088

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Corrosion Issues in Light Water Reactors Excerpt :

Stress corrosion cracking is a major problem in light water nuclear reactors, whether pressurised water reactors (PWRs) or boiling water reactors (BWRs). The nuclear industry needs to be able to predict the service life of these power plants and develop appropriate maintenance and repair practices to ensure safe long term operation. This important book sums up key recent research on corrosion in light water reactors and its practical applications. The book is divided into four parts. It begins with an overview of materials degradation due to stress corrosion, corrosion potential monitoring and passivation. Part two summarises research on susceptibility of materials to stress corrosion cracking and the ways it can be initiated. The third part of the book considers stress corrosion crack propagation processes whilst the final part includes practical case studies of corrosion in particular plants. The book reviews corrosion in a range of materials such as low alloy steels, stainless steels and nickel-based alloys. With its distinguished editor and team of contributors, Corrosion issues in light water reactors is a standard work for the nuclear industry. Summarises key recent research on corrosion in light water reactorsIncludes practical case studies.

Nuclear Corrosion Science and Engineering Book

Nuclear Corrosion Science and Engineering


  • Author : Damien FERON
  • Publisher : Elsevier
  • Release Date : 2012-02-21
  • Genre: Technology & Engineering
  • Pages : 1072
  • ISBN 10 : 9780857095343

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Nuclear Corrosion Science and Engineering Excerpt :

Corrosion of nuclear materials, i.e. the interaction between these materials and their environments, is a major issue for plant safety as well as for operation and economic competitiveness. Understanding these corrosion mechanisms, the systems and materials they affect, and the methods to accurately measure their incidence is of critical importance to the nuclear industry. Combining assessment techniques and analytical models into this understanding allows operators to predict the service life of corrosion-affected nuclear plant materials, and to apply the most appropriate maintenance and mitigation options to ensure safe long term operation. This book critically reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities. Initial sections introduce the complex field of nuclear corrosion science, with detailed chapters on the different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them. This is complemented by reviews of monitoring and control methodologies, as well as modelling and lifetime prediction approaches. Given that corrosion is an applied science, the final sections review corrosion issues across the range of current and next-generation nuclear reactors, and across such nuclear applications as fuel reprocessing facilities, radioactive waste storage and geological disposal systems. With its distinguished editor and international team of expert contributors, Nuclear corrosion science and engineering is an invaluable reference for nuclear metallurgists, materials scientists and engineers, as well as nuclear facility operators, regulators and consultants, and researchers and academics in this field. Comprehensively reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities Chapters assess different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them Considers monito

Nuclear Corrosion Book

Nuclear Corrosion


  • Author : Stefan Ritter
  • Publisher : Woodhead Publishing
  • Release Date : 2020-08-14
  • Genre: Technology & Engineering
  • Pages : 496
  • ISBN 10 : 9780128237205

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Nuclear Corrosion Excerpt :

Nuclear Corrosion: Research, Progress and Challenges, part of the “Green Book series of the EFC, builds upon the foundations of the very first book published in this series in 1989 (“Number 1 - Corrosion in the Nuclear Industry ). This newest volume provides an overview on state-of-the-art research in some of the most important areas of nuclear corrosion. Chapters covered include aging phenomena in light water reactors, reprocessing plants, nuclear waste disposal, and supercritical water and liquid metal systems. This book will be a vital resource for both researchers and engineers working within the nuclear field in both academic and industrial environments. Discusses industry related aspects of materials in nuclear power generation and how these materials react with the environment Provides comprehensive coverage of the topic as written by noted experts in the field Includes coverage of nuclear waste corrosion

Accident Tolerant Materials for Light Water Reactor Fuels Book

Accident Tolerant Materials for Light Water Reactor Fuels


  • Author : Raul B. Rebak
  • Publisher : Unknown
  • Release Date : 2020-01-06
  • Genre: Technology & Engineering
  • Pages : 236
  • ISBN 10 : 9780128175033

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Accident Tolerant Materials for Light Water Reactor Fuels Excerpt :

Accident Tolerant Materials for Light Water Reactor Fuels provides a description of what an accident tolerant fuel is and the benefits and detriments of each concept. The book begins with an introduction to nuclear power as a renewable energy source and the current materials being utilized in light water reactors. It then moves on to discuss the recent advancements being made in accident tolerant fuels, reviewing the specific materials, their fabrication and implementation, environmental resistance, irradiation behavior, and licensing requirements. The book concludes with a look to the future of new power generation technologies. It is written for scientists and engineers working in the nuclear power industry and is the first comprehensive work on this topic. Introduces the fundamental description of accident tolerant fuel, including fabrication and implementation Describes both the benefits and detriments of the various Accident Tolerant Fuel concepts Includes information on the process of materials selection with a discussion of how and why specific materials were chosen, as well as why others failed

Light Water Reactor Safety Book

Light Water Reactor Safety


  • Author : B. Pershagen
  • Publisher : Elsevier
  • Release Date : 2013-10-22
  • Genre: Technology & Engineering
  • Pages : 480
  • ISBN 10 : 9781483286747

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Light Water Reactor Safety Excerpt :

This book describes the principles and practices of reactor safety as applied to the design, regulation and operation of light water reactors, combining a historical approach with an up-to-date account of the safety, technology and operating experience of both pressurized water reactors and boiling water reactors. The introductory chapters set out the basic facts upon which the safety of light water reactors depend. The central section is devoted to the methods and results of safety analysis. The accidents at Three Mile Island and Chernobyl are reviewed and their implications for light water reactor safety are discussed. The concluding chapters examine selected safety issues and their resolution, and highlight results of reactor safety research. The book is amply illustrated, with numerous cross references and a comprehensive index.

Materials Ageing and Degradation in Light Water Reactors Book

Materials Ageing and Degradation in Light Water Reactors


  • Author : K L Murty
  • Publisher : Elsevier
  • Release Date : 2013-02-18
  • Genre: Technology & Engineering
  • Pages : 440
  • ISBN 10 : 9780857097453

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Materials Ageing and Degradation in Light Water Reactors Excerpt :

Light water reactors (LWRs) are the predominant class of nuclear power reactors in operation today; however, ageing and degradation can influence both their performance and lifetime. Knowledge of these factors is therefore critical to safe, continuous operation. Materials ageing and degradation in light water reactors provides a comprehensive guide to prevalent deterioration mechanisms, and the approaches used to handle their effects. Part one introduces fundamental ageing issues and degradation mechanisms. Beginning with an overview of ageing and degradation issues in LWRs, the book goes on to discuss corrosion in pressurized water reactors and creep deformation of materials in LWRs. Part two then considers materials’ ageing and degradation in specific LWR components. Applications of zirconium alloys in LWRs are discussed, along with the ageing of electric cables. Materials management strategies for LWRs are then the focus of part three. Materials management strategies for pressurized water reactors and VVER reactors are considered before the book concludes with a discussion of materials-related problems faced by LWR operators and corresponding research needs. With its distinguished editor and international team of expert contributors, Materials ageing and degradation in light water reactors is an authoritative review for anyone requiring an understanding of the performance and durability of this type of nuclear power plant, including plant operators and managers, nuclear metallurgists, governmental and regulatory safety bodies, and researchers, scientists and academics working in this area. Introduces the fundamental ageing issues and degradation mechanisms associated with this class of nuclear power reactors Considers materials ageing and degradation in specific light water reactor components, including properties, performance and inspection Chapters also focus on material management strategies

Stress Corrosion Cracking in Light Water Reactors Book

Stress Corrosion Cracking in Light Water Reactors


  • Author : International Atomic Energy Agency (IAEA)
  • Publisher : Unknown
  • Release Date : 2011
  • Genre: Uncategoriezed
  • Pages : 115
  • ISBN 10 : OCLC:1024280354

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Stress Corrosion Cracking in Light Water Reactors Excerpt :

The average operating age of existing nuclear power plants (NPPs) is increasing and safety and performance of these ageing NPPs must be achieved by effectively managing material degradations within an acceptable level. Stress corrosion cracking (SCC) is one of significant material degradations for major components of both pressurized water reactors (PWRs) and boiling water reactors (BWRs) and is still an important outstanding technical issue. This publication provides general descriptions of degradation mechanisms of different types of SCC which are concerned to systems, structures and compone.

Structural Alloys for Nuclear Energy Applications Book

Structural Alloys for Nuclear Energy Applications


  • Author : Robert Odette
  • Publisher : Newnes
  • Release Date : 2019-08-15
  • Genre: Technology & Engineering
  • Pages : 673
  • ISBN 10 : 9780123973498

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Structural Alloys for Nuclear Energy Applications Excerpt :

High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors’ unique personal insight from decades of frontline research, engineering and management. Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.

Environmentally Assisted Cracking of Light water Reactor Materials Book

Environmentally Assisted Cracking of Light water Reactor Materials


  • Author : Anonim
  • Publisher : Unknown
  • Release Date : 1996
  • Genre: Uncategoriezed
  • Pages : 7
  • ISBN 10 : OCLC:68374132

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Environmentally Assisted Cracking of Light water Reactor Materials Excerpt :

Environmentally assisted cracking (EAC) of lightwater reactor (LWR) materials has affected nuclear reactors from the very introduction of the technology. Corrosion problems have afflicted steam generators from the very introduction of pressurized water reactor (PWR) technology. Shippingport, the first commercial PWR operated in the United States, developed leaking cracks in two Type 304 stainless steel (SS) steam generator tubes as early as 1957, after only 150 h of operation. Stress corrosion cracks were observed in the heat-affected zones of welds in austenitic SS piping and associated components in boiling-water reactors (BRWs) as early as 1965. The degradation of steam generator tubing in PWRs and the stress corrosion cracking (SCC) of austenitic SS piping in BWRs have been the most visible and most expensive examples of EAC in LWRs, and the repair and replacement of steam generators and recirculation piping has cost hundreds of millions of dollars. However, other problems associated with the effects of the environment on reactor structures and components am important concerns in operating plants and for extended reactor lifetimes. Cast duplex austenitic-ferritic SSs are used extensively in the nuclear industry to fabricate pump casings and valve bodies for LWRs and primary coolant piping in many PWRs. Embrittlement of the ferrite phase in cast duplex SS may occur after 10 to 20 years at reactor operating temperatures, which could influence the mechanical response and integrity of pressure boundary components during high strain-rate loading (e.g., seismic events). The problem is of most concern in PWRs where slightly higher temperatures are typical and cast SS piping is widely used.

Stress Corrosion Cracking of Nickel Based Alloys in Water cooled Nuclear Reactors Book

Stress Corrosion Cracking of Nickel Based Alloys in Water cooled Nuclear Reactors


  • Author : Damien Feron
  • Publisher : Woodhead Publishing
  • Release Date : 2016-01-30
  • Genre: Technology & Engineering
  • Pages : 384
  • ISBN 10 : 9780081000625

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Stress Corrosion Cracking of Nickel Based Alloys in Water cooled Nuclear Reactors Excerpt :

Stress Corrosion Cracking of Nickel Based Alloys in Water-Cooled Nuclear Reactors: The Coriou Effect presents the latest information on brittle failure of metals in corrosive chemical environments under the influence of tensile stresses. Nickel alloys are more resistant to SCC as well as high temperatures and have been widely used in more challenging environments such as nuclear power plants. However, these alloys can suffer SCC under certain conditions, resulting in component failure. A key figure in understanding the mechanisms of SCC in nickel alloys in water-cooled nuclear reactors is Henri Coriou of the CEA, France’s leading center for nuclear research. This book assesses his work in the context of the latest research on SCC in nickel alloys in nuclear power plants. Up-to-date reviews of recent research findings from leading experts in the field Authoritative and comprehensively reviewed by the Working Party 4 on Nuclear Corrosion Showcases the excellent quality and technical accomplishments of Henri Coriou and CEA

Structural Materials for Generation IV Nuclear Reactors Book

Structural Materials for Generation IV Nuclear Reactors


  • Author : Pascal Yvon
  • Publisher : Woodhead Publishing
  • Release Date : 2016-08-27
  • Genre: Technology & Engineering
  • Pages : 684
  • ISBN 10 : 9780081009123

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Structural Materials for Generation IV Nuclear Reactors Excerpt :

Operating at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost, generation IV nuclear reactors promise enhanced features to an energy resource which is already seen as an outstanding source of reliable base load power. The performance and reliability of materials when subjected to the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors are essential areas of study, as key considerations for the successful development of generation IV reactors are suitable structural materials for both in-core and out-of-core applications. Structural Materials for Generation IV Nuclear Reactors explores the current state-of-the art in these areas. Part One reviews the materials, requirements and challenges in generation IV systems. Part Two presents the core materials with chapters on irradiation resistant austenitic steels, ODS/FM steels and refractory metals amongst others. Part Three looks at out-of-core materials. Structural Materials for Generation IV Nuclear Reactors is an essential reference text for professional scientists, engineers and postgraduate researchers involved in the development of generation IV nuclear reactors. Introduces the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors and implications for structural materials Contains chapters on the key core and out-of-core materials, from steels to advanced micro-laminates Written by an expert in that particular area

Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems     Water Reactors Book

Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors


  • Author : John H. Jackson
  • Publisher : Springer
  • Release Date : 2018-12-20
  • Genre: Technology & Engineering
  • Pages : 2532
  • ISBN 10 : 9783030046392

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Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors Excerpt :

This two-volume set represents a collection of papers presented at the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The purpose of this conference series is to foster an exchange of ideas about problems and their remedies in water-cooled nuclear power plants of today and the future. Contributions cover problems facing nickel-based alloys, stainless steels, pressure vessel and piping steels, zirconium alloys, and other alloys in water environments of relevance. Components covered include pressure boundary components, reactor vessels and internals, steam generators, fuel cladding, irradiated components, fuel storage containers, and balance of plant components and systems.