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Material Properties Database For Irradiated Core Structural Components For Lifetime Management For Long Term Operation Of Research Reactors
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Book Synopsis Material Properties Database for Irradiated Core Structural Components for Lifetime Management for Long Term Operation of Research Reactors by : International Atomic Energy Agency
Download or read book Material Properties Database for Irradiated Core Structural Components for Lifetime Management for Long Term Operation of Research Reactors written by International Atomic Energy Agency and published by . This book was released on 2019-07-02 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication presents the results of an IAEA coordinated research project which served as a forum for the establishment of a research reactor material properties database for irradiated core structural components that are important to safety. The database is a compilation of data from comprehensive literature reviews, coordinated research projects and experimental data from research reactors on changes in research reactor core structural material properties owing to irradiation. Such a structured database is a resource for those involved in the aging assessment of core materials used in RRs to ensure the reactor's continued safe operation and possible life extension. The publication describes the coordinated effort to provide a comprehensive background and relevant information on the properties of irradiated core structural materials for RRs and make these data available to the research reactor community. Use of the information provided will contribute to the safe and reliable long-term operation and lifetime extension of operating RRs, as well as to the design of new ones.
Book Synopsis Material Properties Database for Irradiated Core Structural Components for Lifetime Management for Long Term Operation of Research Reactors by :
Download or read book Material Properties Database for Irradiated Core Structural Components for Lifetime Management for Long Term Operation of Research Reactors written by and published by . This book was released on 2019 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: "This publication presents the results of an IAEA coordinated research project which served as a forum for the establishment of a research reactor material properties database for irradiated core structural components that are important to safety. The database is a compilation of data from comprehensive literature reviews, coordinated research projects and experimental data from research reactors on changes in research reactor core structural material properties owing to irradiation. Such a structured database is a resource for those involved in the aging assessment of core materials used in RRs to ensure the reactor's continued safe operation and possible life extension. The publication describes the coordinated effort to provide a comprehensive background and relevant information on the properties of irradiated core structural materials for RRs and make these data available to the research reactor community. Use of the information provided will contribute to the safe and reliable long-term operation and lifetime extension of operating RRs, as well as to the design of new ones."--Publisher's description
Book Synopsis Structural Materials for Generation IV Nuclear Reactors by : Pascal Yvon
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
Book Synopsis Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation by :
Download or read book Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term and Elevated Temperature Irradiation written by and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The in-service degradation of reactor core materials is related to underlying changes in the irradiated microstructure. During reactor operation, structural components and cladding experience displacement of atoms by collisions with neutrons at temperatures at which the radiation-induced defects are mobile, leading to microstructure evolution under irradiation that can degrade material properties. At the doses and temperatures relevant to fast reactor operation, the microstructure evolves by dislocation loop formation and growth, microchemistry changes due to radiation-induced segregation, radiation-induced precipitation, destabilization of the existing precipitate structure, and in some cases, void formation and growth. These processes do not occur independently; rather, their evolution is highly interlinked. Radiationinduced segregation of Cr and existing chromium carbide coverage in irradiated alloy T91 track each other closely. The radiation-induced precipitation of Ni-Si precipitates and RIS of Ni and Si in alloys T91 and HCM12A are likely related. Neither the evolution of these processes nor their coupling is understood under the conditions required for materials performance in fast reactors (temperature range 300-600°C and doses beyond 200 dpa). Further, predictive modeling is not yet possible as models for microstructure evolution must be developed along with experiments to characterize these key processes and provide tools for extrapolation. To extend the range of operation of nuclear fuel cladding and structural materials in advanced nuclear energy and transmutation systems to that required for the fast reactor, the irradiation-induced evolution of the microstructure, microchemistry, and the associated mechanical properties at relevant temperatures and doses must be understood. Predictive modeling relies on an understanding of the physical processes and also on the development of microstructure and microchemical models to describe their evolution under irradiation. This project will focus on modeling microstructural and microchemical evolution of irradiated alloys by performing detailed modeling of such microstructure evolution processes coupled with well-designed in situ experiments that can provide validation and benchmarking to the computer codes. The broad scientific and technical objectives of this proposal are to evaluate the microstructure and microchemical evolution in advanced ferritic/martensitic and oxide dispersion strengthened (ODS) alloys for cladding and duct reactor materials under long-term and elevated temperature irradiation, leading to improved ability to model structural materials performance and lifetime. Specifically, we propose four research thrusts, namely Thrust 1: Identify the formation mechanism and evolution for dislocation loops with Burgers vector of a100 and determine whether the defect microstructure (predominately dislocation loop/dislocation density) saturates at high dose. Thrust 2: Identify whether a threshold irradiation temperature or dose exists for the nucleation of growing voids that mark the beginning of irradiation-induced swelling, and begin to probe the limits of thermal stability of the tempered Martensitic structure under irradiation. Thrust 3: Evaluate the stability of nanometer sized Y- Ti-O based oxide dispersion strengthened (ODS) particles at high fluence/temperature. Thrust 4: Evaluate the extent to which precipitates form and/or dissolve as a function of irradiation temperature and dose, and how these changes are driven by radiation induced segregation and microchemical evolutions and determined by the initial microstructure.
Author :International Atomic Energy Agency Publisher :International Atomic Energy Agency ISBN 13 :9789201450104 Total Pages :108 pages Book Rating :4.4/5 (51 download)
Book Synopsis Applications of Research Reactors by : International Atomic Energy Agency
Download or read book Applications of Research Reactors written by International Atomic Energy Agency and published by International Atomic Energy Agency. This book was released on 2014 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication is a comprehensive study that reviews the current situation in a great number of applications of research reactors. It revises the contents of IAEA TECDOC-1234, The Applications of Research Reactors, giving detailed updates on each field of research reactor uses worldwide. Reactors of all sizes and capabilities can benefit from the sharing of current practices and research enabled via this updated version, which describes the requirements for practicing methods as diverse as neutron activation analysis, education and training, neutron scattering and neutron imaging, silicon doping and radioisotope production, material/fuel irradiation and testing, and some others. Many underutilised research reactors can learn how to diversify their technical capabilities, staff and potential commercial partners and users seeking research reactor services and products. The content of the publication has also been strengthened in terms of current issues facing the vast majority of research reactors by including sections describing user and customer relations as well as strategic planning considerations.
Book Synopsis Structural Materials for Heavy Liquid Metal Cooled Fast Reactors by :
Download or read book Structural Materials for Heavy Liquid Metal Cooled Fast Reactors written by and published by . This book was released on 2021 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: "The compatibility of structural materials, such as steels with lead and lead-bismuth eutectic, poses a critical challenge in the development of heavy liquid metal (HLM) cooled fast reactors. Factors such as the high temperatures, fast neutron flux and irradiation exposure and corrosiveness provide a severe environment for the materials in these advanced reactor systems. The compatibility of liquid coolant with structural materials is critical for the development of innovative nuclear energy systems. To understand the current status of the research and development in this area as well as to provide a forum to exchange information on structural materials for HLM cooled reactors at the national and international levels, the IAEA organized a technical meeting. This resulted in the current publication which presents the summaries of the technical and the group sessions, conclusions and recommendations, and the papers presented at the event."--Publisher's description.
Book Synopsis Periodic Safety Review for Research Reactors by : IAEA
Download or read book Periodic Safety Review for Research Reactors written by IAEA and published by International Atomic Energy Agency. This book was released on 2020-12-03 with total page 128 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication provides information and guidance on the establishment of a process for periodic safety review for research reactors, including preparation, conduct of the review and reporting of results. In addition, it covers the regulatory assessment of these results. The publication also provides information on the experience of Member States in establishing and implementing periodic safety reviews of research reactors, including implementation of reasonable and practical improvements based on these reviews.
Book Synopsis Irradiation Effects on Mechanical and Physical Properties of SS304L-nanotube Composites by : Mohammad Shahin (S.M.)
Download or read book Irradiation Effects on Mechanical and Physical Properties of SS304L-nanotube Composites written by Mohammad Shahin (S.M.) and published by . This book was released on 2020 with total page 47 pages. Available in PDF, EPUB and Kindle. Book excerpt: For decades nuclear power has been a reliable and affordable source of base-load power[1] with relatively small amounts of CO2 emissions.[2] The levelized cost of electricity generated by nuclear power plants is dominated by the capital cost of the structural components,[3] therefore extending the operating lifetime of these plants is of high economic and environmental interests. However, degradation of mechanical behavior of structural materials due to radiation damage is a key limiting factor to service lifetime. The development of advanced materials can potentially improve material performance under irradiation and increase their design lifetime. Traditional alloy design always sacrifices one property for another, such as strength for ductility, or creep strength for radiation resistance. However, a new approach promises to break this property dependency, allowing for obtaining the best properties potentially without sacrificing others.[3-5] This work aims to study the effects of introducing a variety of NanoTubes (NTs) within the metal matrix of austenitic Stainless SS (SS) type 304L on the radiation resistance of the composites. Rapid non- and semi- destructive methods are used to quantify these effects and study the correlation between them. SS and SS Metal Matrix Composites (MMCs) were synthesized by powder metallurgy and Spark Plasma Sintering (SPS) to densify bulk samples approaching the theoretical density. The synthesized materials were then irradiated by accelerated heavy charged particles to mimic the damage caused by neutron irradiation in a nuclear reactor over a longer period of time. Finally, the mechanical and physical properties of the irradiated SS as well as the MMCs were characterized and compared to the non-irradiated samples to study the effects of incorporating the NTs, and to test the hypothesis that the metal-nanotube interfaces serve as recombination sites for defects. The experimental examination of the new materials is necessary to assess their potential for future developments in reactor designs, which would allow improvements to overcome current limitations in service lifetime and hence improve the economy of nuclear power. The results show that the dispersion of NTs within the SS304L mostly caused a slight decrease in thermal diffusivity and an increase in hardness. The results also indicate that incorporating NTs did not break the correlation of property changes after irradiation that was observed in the control (NT-free) sample. In addition, all the SS matrices showed a potential inherent recovery in at least one of the measured properties when irradiated beyond 1 dpa (up to 10 dpa), which suggest the occurrence of onset of defect clustering between 1 and 10 dpa when the SS matrix is irradiated with Ni ions at room temperature.
Book Synopsis Impact of Fuel Density on Performance and Economy of Research Reactors by : International Atomic Energy Agency
Download or read book Impact of Fuel Density on Performance and Economy of Research Reactors written by International Atomic Energy Agency and published by . This book was released on 2021 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt: Research reactor fuel technology continues to evolve, driven in part by international efforts to develop high density fuels to enable the conversion of more reactors from highly enriched uranium (HEU) to low enriched uranium (LEU) fuels. These high density fuels may offer economic benefits for research reactors, despite being more expensive initially, because they offer the prospect of higher per-assembly burnup, thus reducing the number of assemblies that must be procured, and more flexibility in terms of spent fuel management compared to the currently qualified and commercially available LEU silicide fuels. Additionally, these new fuels may offer better performance characteristics. This publication provides a preliminary evaluation of the impacts on research reactor performance and fuel costs from using high density fuel. Several case studies are presented and compared to illustrate these impacts.
Book Synopsis NUREG/CR. by : U.S. Nuclear Regulatory Commission
Download or read book NUREG/CR. written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1977 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Structural Materials for Liquid Metal Cooled Fast Reactor Fuel Assemblies by :
Download or read book Structural Materials for Liquid Metal Cooled Fast Reactor Fuel Assemblies written by and published by . This book was released on 2012 with total page 87 pages. Available in PDF, EPUB and Kindle. Book excerpt: "This publication summarizes the findings of several IAEA meetings on fast reactor materials and provides a review of historically available and new information on the properties, fabrication technologies and irradiation behaviour of stainless steel structural materials for liquid metal cooled fast reactor (LMFR) fuel assemblies. It identifies different varieties of austenitic, ferritic-martensitic, oxide dispersion strengthened (ODS) steels and nickel based alloys used or planned to be used as fuel cladding and structural components of fast reactor fuel assemblies; describes manufacturing processes of LMFR fuel cladding tubes and in-core components; and provides an overview of the operational behaviour of these materials in fast reactors. Particular attention is given to ODS steels as the promising path towards achieving higher fuel burnup in fast reactors."--Provided by publisher.
Book Synopsis Structural Materials in Nuclear Power Systems by : J. T. Adrian Roberts
Download or read book Structural Materials in Nuclear Power Systems written by J. T. Adrian Roberts and published by Springer. This book was released on 1981-05-31 with total page 514 pages. Available in PDF, EPUB and Kindle. Book excerpt: In recent years the effort devoted to assuring both the safety and reliability of commercial nuclear fission power reactors has markedly increased. The incentives for performing this work are large since the resulting im provement in plant productivity translates into lower fuel costs and, more importantly, reduced reliance on imported oil. Reliability and availability of nuclear power plants, whether fission or fusion, demand that more attention be focused on the behavior of materials. Recent experiences with fission power indicate that the basic properties of materials, which categorize their reliable behavior under specified conditions, need reinforcement to assure trouble-free operation for the expected service life. The pursuit of additional information con tinues to demand a better understanding of some of the observed anom alous behavior, and of the margin of resistance of materials to unpre dictable service conditions. It is also apparent that, next to plasma heating and confinement, materials selection represents the most serious chal lenge to the introduction of fusion power. The recognition of the importance of materials performance to nu clear plant performance has sustained a multimillion dollar worldwide research and development effort that has yielded significant results, both in quantification of the performance limits of materials in current use and the development and qualification of new materials. Most of this infor mation appears in the open literature in the form of research reports, journal articles, and conference proceedings.
Book Synopsis Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature by :
Download or read book Microstructure and Property Evolution in Advanced Cladding and Duct Materials Under Long-Term Irradiation at Elevated Temperature written by and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The in-service degradation of reactor core materials is related to underlying changes in the irradiated microstructure. During reactor operation, structural components and cladding experience displacement of atoms by collisions with neutrons at temperatures at which the radiation-induced defects are mobile, leading to microstructure evolution under irradiation that can degrade material properties. At the doses and temperatures relevant to fast reactor operation, the microstructure evolves by microchemistry changes due to radiation-induced segregation, dislocation loop formation and growth, radiation induced precipitation, destabilization of the existing precipitate structure, as well as the possibility for void formation and growth. These processes do not occur independently; rather, their evolution is highly interlinked. Radiation-induced segregation of Cr and existing chromium carbide coverage in irradiated alloy T91 track each other closely. The radiation-induced precipitation of Ni-Si precipitates and RIS of Ni and Si in alloys T91 and HCM12A are likely related. Neither the evolution of these processes nor their coupling is understood under the conditions required for materials performance in fast reactors (temperature range 300-600°C and doses to 200 dpa and beyond). Further, predictive modeling is not yet possible, as models for microstructure evolution must be developed along with experiments to characterize these key processes and provide tools for extrapolation. To extend the range of operation of nuclear fuel cladding and structural materials in advanced nuclear energy and transmutation systems to that required for the fast reactor, the irradiation-induced evolution of the microstructure, microchemistry, and the associated mechanical properties at relevant temperatures and doses must be understood. This project builds upon joint work at the proposing institutions, under a NERI-C program that is scheduled to end in September, to understand the effects of radiation on these important materials. The objective of this project is to conduct critical experiments to understand the evolution of microstructural and microchemical features (loops, voids, precipitates, and segregation) and mechanical properties (hardening and creep) under high temperature and full dose range radiation, including the effect of differences in the initial material composition and microstructure on the microstructural response, including key questions related to saturation of the microstructure at high doses and temperatures.
Download or read book Reactor Core Materials written by and published by . This book was released on 1962 with total page 808 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Irradiation Effects on Structural Alloys for Nuclear Reactor Applications by : A. L. Bement
Download or read book Irradiation Effects on Structural Alloys for Nuclear Reactor Applications written by A. L. Bement and published by ASTM International. This book was released on 1971 with total page 571 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :National Academies of Sciences, Engineering, and Medicine Publisher :National Academies Press ISBN 13 :0309379210 Total Pages :205 pages Book Rating :4.3/5 (93 download)
Book Synopsis Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors by : National Academies of Sciences, Engineering, and Medicine
Download or read book Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors written by National Academies of Sciences, Engineering, and Medicine and published by National Academies Press. This book was released on 2016-02-12 with total page 205 pages. Available in PDF, EPUB and Kindle. Book excerpt: The continued presence of highly enriched uranium (HEU) in civilian installations such as research reactors poses a threat to national and international security. Minimization, and ultimately elimination, of HEU in civilian research reactors worldwide has been a goal of U.S. policy and programs since 1978. Today, 74 civilian research reactors around the world, including 8 in the United States, use or are planning to use HEU fuel. Since the last National Academies of Sciences, Engineering, and Medicine report on this topic in 2009, 28 reactors have been either shut down or converted from HEU to low enriched uranium fuel. Despite this progress, the large number of remaining HEU-fueled reactors demonstrates that an HEU minimization program continues to be needed on a worldwide scale. Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors assesses the status of and progress toward eliminating the worldwide use of HEU fuel in civilian research and test reactors.
Book Synopsis Microstructures of Irradiated Materials by : H. S. Rosenbaum
Download or read book Microstructures of Irradiated Materials written by H. S. Rosenbaum and published by Elsevier. This book was released on 2013-10-22 with total page 189 pages. Available in PDF, EPUB and Kindle. Book excerpt: Treatise on Materials Science and Technology, Volume 7: Microstructures of Irradiated Materials covers the effects of irradiation on the microstructures of solids. The book introduces basic concepts and terminology and discusses the physical effects of irradiation, those having to do with the physical displacement of atoms and the subsequent atom rearrangements that can occur either by momentum transfer or by diffusional phenomena. The text also describes the chemical effects of irradiation, including diffusion, phase changes, precipitation of solute atoms, transmutations, and combinations of these. Some of the complex situations encountered in some nuclear fuels and structural materials of practical concern are also encompassed. Metallurgists, metallurgical engineers, ceramists, materials scientists, and people interested in the nuclear field will find the book invaluable.
