Download or read book Stress Corrosion Cracking of Ni Fe Cr Alloys Relevant to Nuclear Power Plants written by Suraj Yogindra Persaud and published by . This book was released on 2015 with total page 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 Investigation of Stress Corrosion Cracking Susceptibility of Fe Ni Cr Alloys in Nuclear Reactor Water Environments written by W. L. CLARKE and published by . This book was released on 1973 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Supercritical Fluids as Solvents and Reaction Media written by Gerd H. Brunner and published by Elsevier. This book was released on 2004-06-11 with total page 651 pages. Available in PDF, EPUB and Kindle. Book excerpt: Supercritical fluids behave either like a gas or a liquid, depending on the values of thermodynamic properties. This tuning of properties, and other advantageous properties of supercritical fluids led to innovative technologies. More than 100 plants of production size are now in operation worldwide in the areas of process and production technology, environmental applications, and particle engineering. New processes are under research and development in various fields. This book provides an overview of the research activities in the field of Supercritical Fluids in Germany. It is based on the research program "Supercritical fluids as solvents and reaction media" on the initiative of the "GVC-Fachausschuß Hochdruckverfahrenstechnik" (i.e. the German working party on High Pressure Chemical Engineering of the Society of Chemical Engineers).This research program provided an immensely valuable platform for exchange of knowledge and experience. More than 50 young researchers were involved contributing with their expertise, their new ideas, and the motivation of youth. The results of this innovative research are described in this book.- This book provides an overview of the research activities in the field of Supercritical Fluids in Germany- Contains results of projects within the research program on "Supercritical fluids as solvents and reaction media" on the initiative of the German working party on High Pressure Chemical Engineering of the Society of Chemical Engineers.- More than 50 young researchers were involved in contributing with their expertise, their new ideas, and the motivation of youth.

Download or read book Stress Corrosion Cracking of Fe cr ni Alloys in Caustic Environments written by R. W. STAEHLE and published by . This book was released on 1970 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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 Exploring De alloying in Fe Ni Cr Alloys and Its Relationship to Stress Corrosion Cracking in Nuclear High Temperature Water Environments written by Zoe Lewis Coull and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Most stress corrosion cracking (SCC) mechanisms initiate from localised corrosion (pitting, intergranular attack, de-alloying), which provides local stress concentration. Alloys are generally more susceptible to SCC than pure metals because selective dissolution or oxidation is possible. De-alloying involves the selective dissolution of the less noble (LN) component from an alloy. The more noble (MN) component enriches on the surface forming a brittle, metallic, nanoporous layer. In noble metal alloys and brass, SCC shows correlation with the threshold LN content below which de-alloying stops (the parting limit). In Fe-Ni-Cr engineering alloys de-alloying may be responsible for Cl-SCC, although this has not been proven explicitly. Initial indications show that de-alloying causes SCC in hot, caustic environments. In some cases, Ni enrichment and porosity are associated with cracks in stainless steel after long-term service in nuclear high temperature water environments, but it is unclear if this plays a causal role in cracking. Here the de-alloying mechanism (primarily the effect of Ni (MN) content) and its relationship to SCC in Fe-Ni-Cr materials (Fe10Ni, 310SS and Alloy 800) is examined using a hot caustic environment, and compared to classical de-alloying systems. De-alloyed layers formed on all materials, although Alloy 800 required a higher temperature. Increasing Ni content improved de-alloying resistance according to classical theory. Unlike classical systems, de-alloying occurred with concurrent MN dissolution and, at open circuit potential (OCP), the layers retained significant Fe and Cr (LN) instead of being 'almost pure' MN. Layers formed with applied anodic potential were friable and highly LN depleted. This behaviour was successfully modelled in Kinetic Monte Carlo simulations. Recently, it has been shown that SCC in noble element alloys depends on the mechanical integrity (quality) of the de-alloyed layer; a finding that was reflected here. At 140 °C at OCP the layer on 310SS was too thin to promote SCC and Alloy 800 did not de-alloy significantly. Layers formed with anodic potential did not result in SCC. In 50% NaOH at 280 °C, severely stressed 310SS cracked where thick de-alloyed layers formed. However, the thin layer formed on Alloy 800 was associated with SCC, even with low residual stress.

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 Stacking Fault Energy Ordering and Transgranular Stress Corrosion Cracking in Fe Cr Ni Alloys written by Walter Ray Roser and published by . This book was released on 1963 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Stress Corrosion Cracking of Fe Cr Ni Alloys in Caustic Environments Period Covered written by and published by . This book was released on 1970 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Exploring De alloying in Iron Nickel Chromium Alloys and Its Relationship to Stress Corrosion Cracking in Nuclear High Temperature Water Environments written by Zoe Lewis Coull and published by . This book was released on 2010 with total page 462 pages. Available in PDF, EPUB and Kindle. Book excerpt: Most stress corrosion cracking (SCC) mechanisms initiate from localised corrosion (pitting, intergranular attack, de-alloying), which provides local stress concentration. Alloys are generally more susceptible to SCC than pure metals because selective dissolution or oxidation is possible. De-alloying involves the selective dissolution of the less noble (LN) component from an alloy. The more noble (MN) component enriches on the surface forming a brittle, metallic, nanoporous layer. In noble metal alloys and brass, SCC shows correlation with the threshold LN content below which de-alloying stops (the parting limit).In Fe-Ni-Cr engineering alloys de-alloying may be responsible for Cl-SCC, although this has not been proven explicitly. Initial indications show that de-alloying causes SCC in hot, caustic environments. In some cases, Ni enrichment and porosity are associated with cracks in stainless steel after long-term service in nuclear high temperature water environments, but it is unclear if this plays a causal role in cracking.Recently, it has been shown that SCC in noble element alloys depends on the mechanical integrity (quality) of the de-alloyed layer; a finding that was reflected here. At 140 °C at OCP the layer on 310SS was too thin to promote SCC and Alloy 800 did not de-alloy significantly. Layers formed with anodic potential did not result in SCC. In 50% NaOH at 280 °C, severely stressed 310SS cracked where thick de-alloyed layers formed. However, the thin layer formed on Alloy 800 was associated with SCC, even with low residual stress.Here the de-alloying mechanism (primarily the effect of Ni (MN) content) and its relationship to SCC in Fe-Ni-Cr materials (Fe10Ni, 310SS and Alloy 800) is examined using a hot caustic environment, and compared to classical de-alloying systems.De-alloyed layers formed on all materials, although Alloy 800 required a higher temperature. Increasing Ni content improved de-alloying resistance according to classical theory. Unlike classical systems, de-alloying occurred with concurrent MN dissolution and, at open circuit potential (OCP), the layers retained significant Fe and Cr (LN) instead of being 'almost pure' MN. Layers formed with applied anodic potential were friable and highly LN depleted. This behaviour was successfully modelled in Kinetic Monte Carlo simulations.

Download or read book Surface Hardening of Austenitic Fe Cr Ni Alloys for Accident tolerant Nuclear Fuel Cladding written by Zhen Li and published by . This book was released on 2018 with total page 155 pages. Available in PDF, EPUB and Kindle. Book excerpt: Three Fe–Cr–Ni alloys (AISI-316L, AL-6XN and IN-718) were surface-engineered by infusion of interstitial solutes (C and N) for potential application as nuclear fuel cladding. However, an ’activation’ process, which removes the Cr-rich oxide layer that blocks the infusion of interstitial solutes, is needed before these alloys can be successfully surface-engineered. An innovative and highly effective aqueous acid activation process was applied. The surfaces of these Fe–Cr–Ni alloys are successfully activated in 300 s to 600 s at room temperature compared to 21.6 ks at carburizing temperature with gaseous HCl activation. Moreover, the activated surface of Fe–Cr–Ni alloys can be well protected by immersing in ethanol before these specimens are transfered into the carburizing furnace. Specimens of the Fe–Cr–Ni alloy AISI-316L, IN-718 and AL6-XN were successfully surface-engineered by low-temperature carburization and low-temperature nitro-carburization. Near the alloy surface, up to 15 at% to 20 at% of carbon and 20 at% of nitrogen were observed in Fe–Cr–Ni alloys – without detectable carbides. This high carbon and nitrogen fraction results in a threefold increase of surface hardness, significantly improved wear resistance and corrosion resistance of Fe–Cr–Ni alloys. Cr depletion can be seen in all the surface-engineered Fe–Cr–Ni alloys. Low-temperature carburization and low-temperature nitro-carburization can induce ferromagnetism in the surface of IN-718 ni-based alloy. The ferromagnetism detected in low-temperature carburized and low-temperature nitro-carburized IN-718 may have interesting applications, independent of nuclear technology. Thermal stability of low-temperature carburized material was tested by post-carburization heat exposure. No observable difference of properties (i. e. no observable precipitates, no detectable diffusion of interstitial solutes and no obvious change of the shapes of X-ray diffraction peaks and Auger concentration profiles) appeared in surface-engineered Fe–Cr–Ni alloys after exposure at 620K in air in comparison with as-carburized Fe–Cr–Ni alloys. However, properties of low-temperature carburized and low-temperature nitro-carburized Fe–Cr–Ni alloys showed significant variation (i. e. metallography, X-ray diffractometry and scanning Auger microprobe profile) after exposure in the simulated loss of coolant accident environment (1070K for 3.6 ks) compared to those of as-carburized Fe–Cr–Ni alloys. Carbon depletion and infusion were observed in the low-temperature carburized and low-temperature nitro-carburized Fe–Cr–Ni alloys after exposure to 1070K for 3.6 ks. Among all these surface-engineered Fe–Cr–Ni alloys, low-temperature carburized IN-718 did not show observable oxidation after exposure to the simulated loss of coolant accident environment. Non-treated and low-temperature carburized AISI-316L have severe stress corrosion cracking on the surface after exposure in a boiling water reactor simulated environment. However, stress corrosion cracking is not observable in the carburized IN-718 specimen. Finally, exposure to 1.5MeV proton irradiation at elevated temperature (620K), as well as exposure in the simulated loss of coolant accident environment (with no radiation at 1070K for 3.6 ks), causes precipitation of nano-sized Cr-rich carbides in low-temperature carburized IN-718. These prevented the loss of Cr (as well as C) by evaporation under the loss of coolant accident. Among all the surface-engineered alloys, low-temperature carburized IN-718 has the most potential for nuclear cladding.

Download or read book Stress Corrosion Cracking of Fe cr ni Alloys in Caustic Environments written by and published by . This book was released on 1972 with total page 55 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book STRESS CORROSION CRACKING OF Fe Cr Ni ALLOYS IN CAUSTIC ENVIRONMENTS Period Covered written by and published by . This book was released on 1970 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Environment and Alloy Compositions on Stress Corrosion Cracking of Some Wrought Fe Cr Ni Alloys written by Richard Lawrence Beauchamp and published by . This book was released on 1963 with total page 550 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Corrosion Characteristics Mechanisms and Control Methods of Candidate Alloys in Sub and Supercritical Water written by Donghai Xu and published by Springer. This book was released on 2022-12-09 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book aims to provide comprehensive and systematic introduction and summary of corrosion characteristics, mechanisms, and control methods of candidate alloys in sub- and supercritical water environment. First of all, corrosion types of candidate alloys and the effects of major alloying elements on corrosion resistance of potential alloys in sub- and supercritical water are compared and analyzed. At the same time, research status of candidate materials, and development and application trends of several corrosion-resistant alloys are summarized. Then, corrosion characteristics of Ni-Cr, Ni-Cr-Mo, Ni-Fe-Cr and Ni-Fe-Cr-Mo-Cu corrosion-resistant alloys, FeCrAl alloy, and Zircaloy are discussed in detail, including the corrosion rate, the structure and composition of oxide film, and the effects of various surface treatment processes, etc. More specifically, it also investigates corrosion behavior of Ni-based alloy, Fe-Ni-based, and stainless steels in supercritical water. The effects of aggressive species on the corrosion behavior of Ni-base alloys are also explored in supercritical water. Readers will further discover the total corrosion processes and mechanisms of typical candidate alloys in sub- and supercritical water environment. Finally, the work explores the corrosion control methods such as ceramic coatings and passivation processes in supercritical water oxidation and in subcritical water, respectively. Future challenges and development trends of corrosion research of candidate materials in sub- and supercritical water environments are covered at the end of this book. It offers valuable reference for theoretically guiding material selection and design and operating parameter optimization of key equipment in the sub- and supercritical water technologies. The book is written for senior undergraduates, graduate students, scholars, and researchers who are interested in corrosion behavior of candidate materials of supercritical water oxidation system, supercritical water gasification system, and nuclear reactor.

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