Download or read book Corrosion and Corrosion Cracking of Materials for Water cooled Reactors written by and published by . This book was released on 1981 with total page 185 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Stress Corrosion Cracking of Nickel Based Alloys in Water cooled Nuclear Reactors written by Damien Feron and published by Woodhead Publishing. This book was released on 2016-01-30 with total page 386 pages. Available in PDF, EPUB and Kindle. Book 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

Download or read book Materials and Water Chemistry for Supercritical Water cooled Reactors written by David Guzonas and published by Woodhead Publishing. This book was released on 2017-10-31 with total page 280 pages. Available in PDF, EPUB and Kindle. Book excerpt: Materials and Water Chemistry for Supercritical Water-cooled Reactors is unique in that it brings together materials and water chemistry, their interrelationship, the historical perspective and their application to SCWR conceptual design. Written by world's leading experts, all active in the area of materials and chemistry R&D in support of GEN IV SCWR, this book presents for the first time a comprehensive reference on these topics, and in particular, how these data relate to the SCWR design itself. This book is an essential text for researchers in the areas of supercritical water-cooled reactor materials and chemistry, working in industry or academia. It will also give newcomers to the field a survey of all of the available literature and a clear understanding of how these studies relate to the design of the SCWR concept. The material presented is at a specialist's level in materials or corrosion science, or in water chemistry of power plants. - Provides comprehensive coverage of the chemistry and materials of SCWR - Presents the latest research and results condensed into one book - Covers the differences in use of SCW in nuclear reactors and fossil plants, and the resulting differences in materials requirements

Download or read book Assessment of Stress corrosion Cracking in a Water cooled ITER written by and published by . This book was released on 1989 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Water-cooled, near-term reactors will operate under conditions at which SCC is possible; however, control of material purity and processing and coolant chemistry can either eliminate or greatly reduce the probability of this type of structural failure. This evaluation has focused on an assessment of water impurity effects on SCC of austenitic stainless steel at temperatures below 100°C and on the conditions controlling sensitization in the fusion heat of Type 316 SS and the fusion materials heat of modified Type 316 SS designated as PCA. This assessment identifies the dominant effect of small concentrations of impurities in high-purity water on SCC such that crack growth rates at 25--75°C in water with as little as 5--15 ppM Cl− are equal to the crack growth rates at 200--300°C in high-purity water. These effects are primarily for sensitized Type 304 SS, so analysis of sensitization behavior of fusion austenitic alloys was also undertaken. An SSDOS model developed at PNL was used to make these assessments, and correlation to experimental results for Type 316 SS was very good. Both the fusion heat of Type 316 SS and PCA can be severely sensitized but with proper thermal treatment it should be possible to avoid sensitization. 14 refs., 8 figs.

Download or read book Corrosion and Stress Corrosion of Materials for Water cooled Reactors written by R.D. MacCright and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Corrosion and Wear Handbook for Water Cooled Reactors written by D. J. DePaul and published by . This book was released on 1957 with total page 308 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Advanced Course on Corrosion and Water Treatment Problems in Water Cooled Power Reactors written by Netherlands-Norwegian Reactor School and published by . This book was released on 1963 with total page 418 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Stress Corrosion Cracking in Light Water Reactors written by International Atomic Energy Agency and published by . This book was released on 2011 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Provides general descriptions of degradation mechanisms of different types of stress corrosion cracking (SCC) which are concerned with systems, structures and components in PWRs and BWRs. This publication includes examples of good practices in preventing, mitigating and repairing SCC damage and summarizes research and development programmes.

Download or read book Corrosion Issues in Light Water Reactors written by D Féron and published by Woodhead Publishing. This book was released on 2007-06-22 with total page 378 pages. Available in PDF, EPUB and Kindle. Book 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

Download or read book Corrosion of Reactor Materials written by Valentin Vladimirovich Gerasimov and published by . This book was released on 1962 with total page 324 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Experience with Stainless Steel as a Fuel Cladding Material in Water cooled Power Reactor Applications written by T. J. Pashos and published by . This book was released on 1963 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book A Working Party Report on Corrosion in the Nuclear Industry EFC 1 written by European Federation Corrosion Working Party on Nuclear Corrosion and published by CRC Press. This book was released on 2020-03-09 with total page 78 pages. Available in PDF, EPUB and Kindle. Book excerpt: First published in 1989. The EFC, incorporated in Belgium, was founded in 1955 with the purpose of promoting European co-operation in the fields of research into corrosion and corrosion prevention. In 1986 the EFC Working Party on Nuclear Corrosion was reorganised with the objective of concentrating on nine topics of relevance to the nuclear power industry. The group of experts in the Working Party. The new structure of the Working Party is based on the following topics: - Pressurised Water Reactors - Boiling Water Reactors - Fuel Elements (Cladding) - Advanced Gas Reactors - High Temperature Reactors - Liquid Metal Fast Breeders - Fusion Reactors - Reprocessing - Waste Management (Disposal). The first meeting of the Working Party following the restructuring was on the occasion of EUROCORR '87 in Frankfurt. The present volume has therefore been prepared and represents Number One in the series of EFC publications.

Download or read book Investigation and Evaluation of Stress corrosion Cracking in Piping of Light Water Reactor Plants written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1979 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Corrosion written by Stefan Ritter and published by Woodhead Publishing. This book was released on 2020-08-29 with total page 496 pages. Available in PDF, EPUB and Kindle. Book 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

Download or read book Methodologies for Assessing Pipe Failure Rates in Advanced Water Cooled Reactors written by IAEA and published by International Atomic Energy Agency. This book was released on 2023-06-20 with total page 183 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication, which draws upon the outcome of an IAEA coordinated research project, presents methodologies for assessing pipe failure rates in advanced water cooled reactors (WCRs), including a comprehensive review of good practices for the assessment of piping reliability parameters for advanced WCRs. Good practices are those processes and analytical tasks that would be expected in piping reliability analysis in order for the results to be realistic representations of piping structural integrity. This publication builds on technical insights that have been obtained using different methodologies when applied in multiple analytical contexts and responding to the requirements of different national codes and standards. It provides Member States with a strong technical basis for establishing design and plant centric piping reliability parameters for input into probabilistic safety assessment studies, in-service inspection programme development, and operational support. Additionally, an objective evaluation and inter-comparison of methods used in participating Member States is outlined leading to a harmonization of the practices relevant to newly deployable advanced WCRs.

Download or read book Stress Corrosion Cracking written by V S Raja and published by Elsevier. This book was released on 2011-09-22 with total page 817 pages. Available in PDF, EPUB and Kindle. Book excerpt: The problem of stress corrosion cracking (SCC), which causes sudden failure of metals and other materials subjected to stress in corrosive environment(s), has a significant impact on a number of sectors including the oil and gas industries and nuclear power production. Stress corrosion cracking reviews the fundamentals of the phenomenon as well as examining stress corrosion behaviour in specific materials and particular industries.The book is divided into four parts. Part one covers the mechanisms of SCC and hydrogen embrittlement, while the focus of part two is on methods of testing for SCC in metals. Chapters in part three each review the phenomenon with reference to a specific material, with a variety of metals, alloys and composites discussed, including steels, titanium alloys and polymer composites. In part four, the effect of SCC in various industries is examined, with chapters covering subjects such as aerospace engineering, nuclear reactors, utilities and pipelines.With its distinguished editors and international team of contributors, Stress corrosion cracking is an essential reference for engineers and designers working with metals, alloys and polymers, and will be an invaluable tool for any industries in which metallic components are exposed to tension, corrosive environments at ambient and high temperatures. - Examines the mechanisms of stress corrosion cracking (SCC) presenting recognising testing methods and materials resistant to SCC - Assesses the effect of SCC on particular metals featuring steel, stainless steel, nickel-based alloys, magnesium alloys, copper-based alloys and welds in steels - Reviews the monitoring and management of SCC and the affect of SCC in different industries such as petrochemical and aerospace

Download or read book Structural Materials for Generation IV Nuclear Reactors written by Pascal Yvon and published by Woodhead Publishing. This book was released on 2016-08-27 with total page 686 pages. Available in PDF, EPUB and Kindle. Book 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