Nuclear Corrosion

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 monitoring and control methodologies, as well as modelling and lifetime prediction approaches

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

Corrosion in nuclear power plants cause reductions in efficiency and increases in deposit build-up on plant surfaces, making for expensive maintentance and potential radiological health hazards. This book guides studies to predict and minimize corrosion, thus making nuclear power safer and more cost effective. Too often, reliance on empirical models and on-site testing of existing plants makes study and prediction of corrosive effects in nuclear reactors into a pricey and lengthy process. Introducing the experimental procedures, set up, sample preparation and computer modeling suggested in this book will save precious time and resources in a field where the significant time and expense to get and keep plants on-line are two of the chief concerns preventing broader commerical viability. * The only book to focus exclusively on preventing nuclear corrosion * Uses computer modelling to tie together chemical engineering, civil engineering, corrosion science, and nuclear engineering into a cohesive solution to a vexing nucelar problem * Includes all fundamental equations, example data sets and experimental techniques

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

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

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.

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

This book addresses structural material corrosion in coolant circuits, simulation of erosion corrosion of carbon and low-alloy steels, and simulation of stress corrosion. It also discusses corrosion of copper alloys, zirconium corrosion, optimization of water chemistry at operating nuclear power plants, coolant tendency to deposit hardness salts on heat-transfer surfaces, and inspection of metallic components. In addition, there are two appendixes, the first showing the chemical composition of steels, the second discussing solubility of iron, cobalt, zinc and copper corrosion products under conditions simulating power unit water chemistry.