corrosion issues in light water reactors

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Corrosion Issues in Light Water Reactors
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Publisher : Elsevier
Release Date :
ISBN 10 : 1845693469
Pages : 368 pages
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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

Corrosion Issues in Light Water Reactors

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

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Electrochemistry in Light Water Reactors

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

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Materials Ageing and Degradation in Light Water Reactors

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

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Light Water Reactor Safety

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

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Environmentally Assisted Cracking of Light water Reactor Materials

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

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Nuclear Corrosion Science and Engineering

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

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Accident Tolerant Materials for Light Water Reactor Fuels

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.

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Nuclear Corrosion

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

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Structural Alloys for Nuclear Energy Applications

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

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Zircaloy Performance in Light Water Reactors

The Zircaloys-2 and -4 are the principal metallic components of light-water reactor (LWR) fuel assemblies. This paper reviews progress in our understanding of Zircaloy behavior in the LWR environment. A significant body of data has been obtained on the characteristics of stress corrosion cracking pellet-cladding interaction (PCI) failures and on

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Multiphysics Modeling of Activity Transport and Evolution of CRUD and Steam Generator Oxides in Pressurized Water Reactors

Fouling deposits of corrosion products on fuel cladding, known as crud, in the core of light water reactors can cause a variety of operational issues. Buildup of radioactive crud and corrosion products on ex-core structures, such as steam generators and piping, can cause increased radiation fields and higher dose exposures

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Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in BWR Environments

The internal components of light water reactors are exposed to high-energy neutron irradiation and high-temperature reactor coolant. The exposure to neutron irradiation increases the susceptibility of austenitic stainless steels (SSs) to stress corrosion cracking (SCC) because of the elevated corrosion potential of the reactor coolant and the introduction of new

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

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

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

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

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An Overview of Environmental Degradation of Materials in Nuclear Power Plant Piping Systems

Piping in light water reactor (LWR) power systems is affected by several types of environmental degradation: intergranular stress corrosion cracking (IGSCC) of austenitic stainless steel piping in boiling water reactors (BWRs) has required research, inspection, and mitigation programs that will ultimately cost several billion dollars; erosion-corrosion of carbon steel piping

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