Download or read book Evaluation on the Effect of Composition on Radiation Hardening and Embrittlement in Model FeCrAl Alloys written by and published by . This book was released on 2015 with total page 41 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report details the findings of post-radiation mechanical testing and microstructural characterization performed on a series of model and commercial FeCrAl alloys to assist with the development of a cladding technology with enhanced accident tolerance. The samples investigated include model alloys with simple ferritic grain structure and two commercial alloys with minor solute additions. These samples were irradiated in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL) up to nominal doses of 7.0 dpa near or at Light Water Reactor (LWR) relevant temperatures (300-400 C). Characterization included a suite of techniques including small angle neutron scattering (SANS), atom probe tomography (APT), and transmission based electron microscopy techniques. Mechanical testing included tensile tests at room temperature on sub-sized tensile specimens. The goal of this work was to conduct detailed characterization and mechanical testing to begin establishing empirical and/or theoretical structure-property relationships for radiation-induced hardening and embrittlement in the FeCrAl alloy class. Development of such relationships will provide insight on the performance of FeCrAl alloys in an irradiation environment and will enable further development of the alloy class for applications within a LWR environment. A particular focus was made on establishing trends, including composition and radiation dose. The report highlights in detail the pertinent findings based on this work. This report shows that radiation hardening in the alloys is primarily composition dependent due to the phase separation in the high-Cr FeCrAl alloys. Other radiation induced/enhanced microstructural features were less dependent on composition and when observed at low number densities, were not a significant contributor to the observed mechanical responses. Pre-existing microstructure in the alloys was found to be important, with grain boundaries and pre-existing dislocation networks acting as defect sinks, resulting in variations in the observed microstructures after irradiation. Dose trends were also observed, with increasing radiation dose promoting changes in the size and number density of the Cr-rich ' precipitates. Based on the microstructural analysis, performed tensile testing, and prior knowledge from FeCr literature it was hypothesized that the formation of the Cr-rich ' precipitates could lead to significant radiation-induced embrittlement in the alloys, and this could be composition dependent, a result which would mirror the trends observed for radiation-induced hardening. Due to the limited database on embrittlement in the FeCrAl alloy class after irradiation, a series of radiation experiments have been implemented. The overarching point of view within this report is the radiation tolerance of FeCrAl is complex, with many mechanisms and factors to be considered at once. Further development of the FeCrAl alloy class for enhanced accident tolerant applications requires detailed, single (or at least limited) variable experiments to fully comprehend and predict the performance of this alloy in LWRs. This report has been submitted as fulfillment of milestone M2FT-15OR0202321 titled, Summary report on the effect of composition on the irradiation embrittlement of Gen 1 ATF FeCrAl for the Department of Energy Office of Nuclear Energy, Advanced Fuel Campaign of the Fuel Cycle R & D program.

Download or read book Energy Materials 2017 written by Xingbo Liu and published by Springer. This book was released on 2017-03-06 with total page 440 pages. Available in PDF, EPUB and Kindle. Book excerpt: This collection highlights materials research and innovations for a wide breadth of energy systems and technologies. The volume includes papers organized into the following sections:Energy and Environmental Issues in Materials Manufacturing and ProcessingMaterials in Clean PowerMaterials for Coal-Based PowerMaterials for Energy Conversion with Emphasis on SOFCMaterials for Gas TurbinesMaterials for Nuclear EnergyMaterials for Oil and Gas

Download or read book Embrittlement Hardening and Grain Boundary Composition in an Fe P C Alloy After Irradiation Or Thermal Aging written by JC. Walmsley and published by . This book was released on 2000 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: An Fe-1200ppmP-30ppmC alloy has been examined after aging and irradiation exposure at 240°C. Thermal aging for 97 days reduced the yield stress by 10% but increased the 40J Charpy transition temperature by 50°C. Irradiation for a similar duration, in a highly thermalised neutron spectrum at 5.8 ± 1.7x10-11dpa/sec, increased both the yield stress by 15% and the transition temperature by 70°C. Longer irradiation, in spectra with or without the high thermal fraction, produced additional hardening but little extra embrittlement. Irradiation and aging gave a fivefold increase in the fraction of brittle intergranular fracture. Auger Spectroscopy showed that the P grain boundary monolayer coverage was virtually unchanged for all start-of-life, aging and irradiation conditions. In contrast, the C coverage reduced by 50% during the initial aging or irradiation, but changed little after longer irradiations. Grain boundary N increased initially but then stabilised. No grain boundary S occurred. Transmission microscopy revealed some dislocation loops and small regions of strain contrast in the grains after irradiation but no P-rich precipitates were seen. From this, and other published work, it is concluded that irradiation hardening arises from dislocation loops and possibly from P-rich cluster formation. Embrittlement developed due to loss of C from the grain boundaries, rather than from changes to the boundary P content. Loss of C reduced the boundary fracture stress but embrittlement was independent of the matrix strength. For the irradiation conditions examined, there was no evidence of irradiation-induced grain boundary P segregation.

Download or read book Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors written by John H. Jackson and published by Springer. This book was released on 2018-12-20 with total page 2532 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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 and the future. Contributions cover problems facing nickel-based alloys, stainless steels, pressure vessel and piping steels, zirconium alloys, and other alloys in water environments of relevance. Components covered include pressure boundary components, reactor vessels and internals, steam generators, fuel cladding, irradiated components, fuel storage containers, and balance of plant components and systems.

Download or read book Radiation Tolerance of Neutron Irradiated Model Fe Cr Al Alloys written by and published by . This book was released on 2015 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Fe Cr Al alloy system has the potential to form an important class of enhanced accident-tolerant cladding materials in the nuclear power industry owing to the alloy system's higher oxidation resistance in high-temperature steam environments compared with traditional zirconium-based alloys. However, radiation tolerance of Fe Cr Al alloys has not been fully established. In this study, a series of Fe Cr Al alloys with 10 18 wt % Cr and 2.9 4.9 wt % Al were neutron irradiated at 382 C to 1.8 dpa to investigate the irradiation-induced microstructural and mechanical property evolution as a function of alloy composition. Dislocation loops with Burgers vector of a/2 111 and a 100 were detected and quantified. Results indicate precipitation of Cr-rich is primarily dependent on the bulk chromium composition. Mechanical testing of sub-size-irradiated tensile specimens indicates the hardening response seen after irradiation is dependent on the bulk chromium composition. A structure property relationship was developed; it indicated that the change in yield strength after irradiation is caused by the formation of these radiation-induced defects and is dominated by the large number density of Cr-rich precipitates at sufficiently high chromium contents after irradiation.

Download or read book Hardening Characteristics of Ion Irradiated Iron Based Model Alloys written by Y. Arai and published by . This book was released on 1993 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fe-C-Cu, Fe-C-Ni, and Fe-C-Cu-Ni model alloys were prepared in order to investigate the effects of copper and nickel on radiation embrittlement. They were irradiated with 4 MeV Ni3+ ions at 563 K to introduce displacement damage, followed by a micro-Vickers hardness test employing low load (0.5 g). It was observed that greater hardening occurred for samples of larger copper content, and that hardening of the samples containing both copper and nickel was greater than hardening of the ones containing copper or nickel solely for samples irradiated to 10-2 and 10-1 dpa. Increased hardness after annealing occurred for Fe-0.1C-0.2Cu and Fe-0.lC-0.4Cu. Small defect clusters of approximately 3 nm in diameter were observed by transmission electron microscopy (TEM) of the irradiated Fe-0.1C and Fe-0.1C-0.4Cu samples, which cause hardening.

Download or read book Effects of Irradiation on Low Activation Ferritic Alloys written by DS. Gelles and published by . This book was released on 1990 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: A broad composition range of ferritic alloys exists which satisfy the low activation requirement for fusion reactor materials five hundred years after decommissioning. Low activation bainitic alloys in the Fe-2Cr composition range, martensitic alloys in the Fe-7-to-9Cr range and stabilized martensitic alloys in the Fe-12Cr range have been successfully fabricated and are undergoing testing as demonstrated by efforts in Europe, Japan, and the United States. However, irradiation significantly degrades the properties of bainitic and stabilized martensitic alloys. Bainitic alloys containing vanadium develop severe hardening due to irradiation-induced precipitation at temperatures below 450°C and extreme softening due to carbide coarsening at temperatures above 500°C. Stabilized martensitic alloys which rely on manganese additions to provide a fully martensitic microstructure are embrittled at grain boundaries following irradiation leading to severe degradation of impact properties. The most promising composition regime appears to be the Fe-7-to-9Cr range with tungsten additions in the 2% range where high-temperature mechanical properties and microstructural stability are retained and impact properties are relatively unaffected by irradiation.

Download or read book Metals Abstracts written by and published by . This book was released on 1998 with total page 1042 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Comprehensive Nuclear Materials written by and published by Elsevier. This book was released on 2020-07-22 with total page 4871 pages. Available in PDF, EPUB and Kindle. Book excerpt: Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field

Download or read book TOP FUEL 2016 written by and published by . This book was released on 2016 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Translational Research in Cardio Oncology An Issue of Heart Failure Clinics written by Ragavendra R. Baliga and published by Elsevier Health Sciences. This book was released on 2022-06-23 with total page 217 pages. Available in PDF, EPUB and Kindle. Book excerpt: In this issue of Heart Failure Clinics, guest editors Drs. Ragavendra R Baliga and George A. Mensah bring their considerable expertise to the topic of Translational Research in Cardio-Oncology. Top experts in the field cover key topics such as radiation-induced cardiac dysfunction; training and career development; cardiovascular imaging; CAR-T cell therapy and cardiovascular disease; and more. Contains 12 relevant, practice-oriented topics including cardio-protection of high-risk individuals; myocardial metabolism; amyloidosis; arrhythmic complications associated with cancer therapies; and more. Provides in-depth clinical reviews on translational research in cardio-oncology, offering actionable insights for clinical practice. Presents the latest information on this timely, focused topic under the leadership of experienced editors in the field. Authors synthesize and distill the latest research and practice guidelines to create clinically significant, topic-based reviews.

Download or read book Atom Probe Tomography written by Michael K. Miller and published by Springer Science & Business Media. This book was released on 2012-12-06 with total page 247 pages. Available in PDF, EPUB and Kindle. Book excerpt: The microanalytical technique of atom probe tomography (APT) permits the spatial coordinates and elemental identities of the individual atoms within a small volume to be determined with near atomic resolution. Therefore, atom probe tomography provides a technique for acquiring atomic resolution three dimensional images of the solute distribution within the microstructures of materials. This monograph is designed to provide researchers and students the necessary information to plan and experimentally conduct an atom probe tomography experiment. The techniques required to visualize and to analyze the resulting three-dimensional data are also described. The monograph is organized into chapters each covering a specific aspect of the technique. The development of this powerful microanalytical technique from the origins offield ion microscopy in 1951, through the first three-dimensional atom probe prototype built in 1986 to today's commercial state-of-the-art three dimensional atom probe is documented in chapter 1. A general introduction to atom probe tomography is also presented in chapter 1. The various methods to fabricate suitable needle-shaped specimens are presented in chapter 2. The procedure to form field ion images of the needle-shaped specimen is described in chapter 3. In addition, the appearance of microstructural features and the information that may be estimated from field ion microscopy are summarized. A brief account of the theoretical basis for processes of field ionization and field evaporation is also included.

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

Download or read book Experimental Neutron Scattering written by B. T. M. Willis and published by Oxford University Press. This book was released on 2017-03-23 with total page 325 pages. Available in PDF, EPUB and Kindle. Book excerpt: The first systematic experiments in neutron scattering were carried out in the late 1940s using fission reactors built for the nuclear power programme. Crystallographers were amongst the first to exploit the new technique, but they were soon followed by condensed matter physicists and chemists. Engineers and biologists are the most recent recruits to the club of neutron users. The aim of the book is to provide a broad survey of the experimental activities of all these users. There are many specialist monographs describing particular examples of the application of neutron scattering: fifteen of such monographs have been published already in the Oxford University Press series edited by S. Lovesey and E. Mitchell. However this book will appeal to newcomers to the field of neutron scattering, who may be intimidated by the bewildering array of instruments at central facilities (such as the Institut Laue Langevin in France, the ISIS Laboratory in the UK, or the PSI Laboratory in Switzerland), and who may be uncertain as to which instrument to use.

Download or read book Atom Probe Tomography written by Williams Lefebvre and published by Academic Press. This book was released on 2016-05-30 with total page 418 pages. Available in PDF, EPUB and Kindle. Book excerpt: Atom Probe Tomography is aimed at beginners and researchers interested in expanding their expertise in this area. It provides the theoretical background and practical information necessary to investigate how materials work using atom probe microscopy techniques, and includes detailed explanations of the fundamentals, the instrumentation, contemporary specimen preparation techniques, and experimental details, as well as an overview of the results that can be obtained. The book emphasizes processes for assessing data quality and the proper implementation of advanced data mining algorithms. For those more experienced in the technique, this book will serve as a single comprehensive source of indispensable reference information, tables, and techniques. Both beginner and expert will value the way the book is set out in the context of materials science and engineering. In addition, its references to key research outcomes based upon the training program held at the University of Rouen—one of the leading scientific research centers exploring the various aspects of the instrument—will further enhance understanding and the learning process. Provides an introduction to the capabilities and limitations of atom probe tomography when analyzing materials Written for both experienced researchers and new users Includes exercises, along with corrections, for users to practice the techniques discussed Contains coverage of more advanced and less widespread techniques, such as correlative APT and STEM microscopy

Download or read book Accident Tolerant Materials for Light Water Reactor Fuels written by Raul B. Rebak and published by Elsevier. This book was released on 2020-01-10 with total page 237 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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. It then moves on to discuss the recent advancements being made in accident tolerant fuels, reviewing the specific materials, their fabrication and implementation, environmental resistance, irradiation behavior, and licensing requirements. The book concludes with a look to the future of new power generation technologies. It is written for scientists and engineers working in the nuclear power industry and is the first comprehensive work on this topic. Introduces the fundamental description of accident tolerant fuel, including fabrication and implementation Describes both the benefits and detriments of the various Accident Tolerant Fuel concepts Includes information on the process of materials selection with a discussion of how and why specific materials were chosen, as well as why others failed

Download or read book The Handbook of Advanced Materials written by and published by John Wiley & Sons. This book was released on 2004-04-27 with total page 656 pages. Available in PDF, EPUB and Kindle. Book excerpt: Written to educate readers about recent advances in the area of new materials used in making products. Materials and their properties usually limit the component designer. * Presents information about all of these advanced materials that enable products to be designed in a new way * Provides a cost effective way for the design engineer to become acquainted with new materials * The material expert benefits by being aware of the latest development in all these areas so he/she can focus on further improvements