Download or read book Detecting Stress Corrosion Crack Initiating Conditions in Boiling Water Reactor Nuclear Power Plants written by David Jonathan Beard and published by . This book was released on 2004 with total page 154 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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 Corrosion Monitoring in Nuclear Systems EFC 56 written by Stefan Ritter and published by Routledge. This book was released on 2017-09-20 with total page 404 pages. Available in PDF, EPUB and Kindle. Book excerpt: Corrosion remains one of the key issues affecting the performance and availability of nuclear power plants. Therefore, reliable in-plant corrosion monitoring methods are essential both for the future operation of existing plants and to ensure the safety of future nuclear waste disposal systems. In two parts, this book was stimulated by a workshop organised by EFC Working Party 4 on Nuclear Corrosion and the European Cooperative Group on Corrosion Monitoring of Nuclear Materials (EGC-COMON). The first part deals mainly with research into the detection of stress corrosion crack initiation in nuclear power plant environments (essentially high temperature water at around 300 °C) by various methods, particularly the electrochemical noise technique but also including the electrochemical impedance, acoustic emission and direct current potential drop methods. The second part addresses the goal to develop in-situ techniques and includes examples of the application of electrochemical corrosion potential monitoring. This book will be of particular interest to scientists and engineers concerned with the mitigation of corrosion in nuclear systems.

Download or read book Stress Corrosion Cracking in Light Water Reactors written by International Atomic Energy Agency (IAEA) and published by . This book was released on 2011 with total page 115 pages. Available in PDF, EPUB and Kindle. Book 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.

Download or read book Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors written by and published by . This book was released on 1994 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Investigation and Evaluation of Stress corrosion Cracking in Piping of Boiling Water Reactor Plants written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Pipe Cracking Experience in Light water Reactors written by Louis Frank and published by . This book was released on 1980 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Environmental Factors Influencing Stress Corrosion Cracking in Boiling Water Reactors written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The mechanisms of intergranular stress corrosion cracking (IGSCC) of sensitized stainless steels in boiling water reactor (BWR) primary coolant are reviewed, with emphasis on the role the environment plays on both the initiation and propagation processes. Environmental factors discussed include oxygen (corrosion potential), temperature, and dissolved ions in the water and the range of strain rates at which IGSCC occurs. Both crack propagation rates and the range of strain rates at which IGSCC occurs decrease rapidly as temperature is increased above approximately 200°C, in essentially the same manner as the solubility of magnetite decreases in acidic solutions. A mechanism of crack propagation is presented base on this observation. To establish water chemistry guidelines for crack-free operation of BWR's containing sensitized stainless steel, more information is needed on the role of absorption of impurities in the surface and deposited oxides and on the interaction between the oxygen and impurity levels required to maintain an electrochemical potential in a range where IGSCC is unlikely to occur. The relative effects of short bursts of impurities and longer term lower concentrations of these same impurities also need to be evaluated.

Download or read book Nuclear Corrosion Science and Engineering written by Damien Feron and published by Elsevier. This book was released on 2012-02-21 with total page 1073 pages. Available in PDF, EPUB and Kindle. Book 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 monitoring and control methodologies, as well as modelling and lifetime prediction approaches

Download or read book Intergranular Stress Corrosion Cracking in Boiling Water Reactors written by Niagara Mohawk Power Corporation and published by . This book was released on 1997 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fatigue and Environmentally Assisted Cracking in Light Water Reactors written by and published by . This book was released on 1991 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fatigue and environmentally assisted cracking of piping, pressure vessels, and core components in light water reactors (LWRs) are important concerns as extended reactor lifetimes are envisaged. The degradation processes include intergranular stress corrosion cracking (IGSCC) of austenitic stainless steel (SS) piping in boiling water reactors (BWRs), and propagation of fatigue or SCC cracks (which initiate in sensitized SS cladding) into low-alloy ferritic steels in BWR pressure vessels. Similar cracking has also occurred in upper shell-to-transition cone girth welds in pressurized water reactor (PWR) steam generator vessels. Another concern is failure of reactor-core internal components after accumulation of relatively high fluence, which has occurred in both BWRs and PWRs. Research during the past year focused on (1) fatigue and SCC of ferritic steels used in piping and in steam generator and reactor pressure vessels, (2) role of chromate and sulfate in simulated BWR water in SCC of sensitized Type 304 SS, and (3) irradiation-assisted SCC in high- and commercial-purity Type 304 SS specimens from control-blade absorber tubes used in two operating BWRs. Failure after accumulation of relatively high fluence has been attributed to radiation-induced segregation (RIS) of elements such as Si, P, Ni, and Cr. This document provides a summary of research progress in these areas.

Download or read book Evaluation of Risk Associated with Intergranular Stress Corrosion Cracking in Boiling Water Reactor Internals written by A. G. Ware and published by . This book was released on 2000 with total page 200 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Corrosion Monitoring in Nuclear Systems EFC 56 written by Stefan Ritter and published by Routledge. This book was released on 2017-09-20 with total page 280 pages. Available in PDF, EPUB and Kindle. Book excerpt: Corrosion remains one of the key issues affecting the performance and availability of nuclear power plants. Therefore, reliable in-plant corrosion monitoring methods are essential both for the future operation of existing plants and to ensure the safety of future nuclear waste disposal systems. In two parts, this book was stimulated by a workshop organised by EFC Working Party 4 on Nuclear Corrosion and the European Cooperative Group on Corrosion Monitoring of Nuclear Materials (EGC-COMON). The first part deals mainly with research into the detection of stress corrosion crack initiation in nuclear power plant environments (essentially high temperature water at around 300 °C) by various methods, particularly the electrochemical noise technique but also including the electrochemical impedance, acoustic emission and direct current potential drop methods. The second part addresses the goal to develop in-situ techniques and includes examples of the application of electrochemical corrosion potential monitoring. This book will be of particular interest to scientists and engineers concerned with the mitigation of corrosion in nuclear systems.

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 Assuring Structural Integrity of Steel Reactor Pressure Boundary Components written by K. E. Stahlkopf and published by . This book was released on 1988 with total page 396 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Adaptation of Crack Growth Detection Techniques to US Material Test Reactors written by and published by . This book was released on 2014 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A key component in evaluating the ability of Light Water Reactors to operate beyond 60 years is characterizing the degradation of materials exposed to radiation and various water chemistries. Of particular concern is the response of reactor materials to Irradiation Assisted Stress Corrosion Cracking (IASCC). Some materials testing reactors (MTRs) outside the U.S., such as the Halden Boiling Water Reactor (HBWR), have deployed a technique to measure crack growth propagation during irradiation. This technique incorporates a compact loading mechanism to stress the specimen during irradiation. A crack in the specimen is monitored using the Direct Current Potential Drop (DCPD) method. A project is underway to develop and demonstrate the performance of a similar type of test rig for use in U.S. MTRs. The first year of this three year project was devoted to designing, analyzing, fabricating, and bench top testing a mechanism capable of applying a controlled stress to specimens while they are irradiated in a pressurized water loop (simulating PWR reactor conditions). During the second year, the mechanism will be tested in autoclaves containing high pressure, high temperature water with representative water chemistries. In addition, necessary documentation and safety reviews for testing in a reactor environment will be completed. In the third year, the assembly will be tested in the Massachusetts Institute of Technology Reactor (MITR) and Post Irradiation Examinations (PIE) will be performed.

Download or read book A Process Model for the Initiation of Stress Corrosion Crack Growth in BWR Plant Materials written by M. Akashi and published by . This book was released on 1997 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: The process of initiating the stress-corrosion crack growth comprises following six elementary processes; namely, (I) the incubation period, (II) the process of nucleating the corrosion pits (or corrosion crevices), (III) the process of the growth of pits (or crevices), (IV) the process of initiating microcracks, (V) the process of the propagation of microcracks, (VI) the process of coalescing the microcracks, leading into the process of steady propagation of the main crack. The processes I, III, and V fall into the category of the deterministic process, while the processes II, IV, and VI the stochastic process. This paper deals with the last three stochastic elementary processes by analyzing the stress-corrosion cracking behavior for each stage, and examines the models developed thereby to predict the initiation life of each. Following observations and conclu-sions have been made: (1) the critical pit depth to initiate the microcrack is approximately 20 ?m for the carbon steel, and the micro-cracks are non-propagative semicircular cracks of approximately 50 ?m in depth; (2) the processes II of the pit nucleation, IV of the microcrack initiation, and VI of the microcrack coalescence can all be represented to the Poissonian stochastic process; (3) inasmuch as the total crack-initiation life is determined by a stochastic process comprising these Poissonian processes concatenated in series, the probability distribution of the life leading to the onset of steady propagation of a main crack can be represented by the exponential distribution; (4) the applied stress exerts its influence mainly on the rate of proliferation of microcracks, but hardly on the propagation of microcrack, critical pit depth, and the probability of the pit's gener-ating microcracks; and (5) inasmuch as the proliferation rate of microcrack is represented by a linear function in applied stress, the distribution lower limit of the main-crack initiation life is in inverse proportion to the applied stress.