Download or read book Dimensional Changes and Radiation Creep of Graphite at Very High Neutron Doses written by A.J. Perks and published by . This book was released on 1965 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Radiation Damage in Graphite written by J. H. W. Simmons and published by Elsevier. This book was released on 2013-10-22 with total page 264 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear Energy, Volume 102: Radiation Damage in Graphite provides a general account of the effects of irradiation on graphite. This book presents valuable work on the structure of the defects produced in graphite crystals by irradiation. Organized into eight chapters, this volume begins with an overview of the description of the methods of manufacturing graphite and of its physical properties. This text then presents details of the method of setting up a scale of irradiation dose. Other chapters consider the effect of irradiation at a given temperature on a physical property of graphite. This book discusses as well the changes in dimensions produced by irradiation and the effects of irradiation on the mechanical properties of graphite. The final chapter deals with the accumulation of stored energy, which is one of the main problems caused by the irradiation of graphite in nuclear reactors. This book is a valuable resource for physicists and chemical physicists.
Download or read book Defect Evolution in High temperature Irradiated Nuclear Graphite written by Steve Johns and published by . This book was released on 2020 with total page 113 pages. Available in PDF, EPUB and Kindle. Book excerpt: "Graphite has historically been used as a moderator material in nuclear reactor designs dating back to the first man-made nuclear reactor to achieve criticality (Chicago Pile 1) in 1942. Additionally, graphite is a candidate material for use in the future envisioned next-generation nuclear reactors (Gen IV); specifically, the molten-salt-cooled (MSR) and very-high-temperature reactor (VHTR) concepts. Gen IV reactor concepts will introduce material challenges as temperature regimes and reactor lifetimes are anticipated to far exceed those of earlier reactors. Irradiation-induced defect evolution is a fundamental response in nuclear graphite subjected to irradiation. These defects directly influence the many property changes of nuclear graphite subjected to displacing radiation; however, a comprehensive explanation for irradiation-induced dimensional change remains elusive. The macroscopic response of graphite subjected to displacing irradiation is often modeled semi-empirically based on irradiation data of specific graphite grades (some of which are obsolete). The lack of an analytical description of the response of nuclear graphite subjected to irradiation is due in part to the complex microstructure of synthetic semi-isotropic graphites. Chapter One provides a general overview of the application, processing, and irradiation-induced property changes of nuclear graphite. The key properties affected by displacing irradiation include, but are not limited to, coefficient of thermal expansion (CTE), irradiation creep, and irradiation-induced dimensional change. Additionally, historical models of radiation damage in nuclear graphite, including their inadequacies in accurately describing property changes, are discussed. It should be noted that a comprehensive explanation for all irradiation-induced property change is beyond the scope of this work, which is focused on the evolution of novel atomic-level defects in high-temperature irradiated nuclear graphite and the implications of these defects for the current understanding of irradiation-induced dimensional change. Chapter Two is focused on the development of a novel oxidation-based transmission electron microscopy (TEM) sample-preparation technique for nuclear-grade graphite. Conventionally, TEM specimens are prepared via ion-milling or a focused ion beam (FIB); however, these techniques require the use of displacing radiation and may result in localized areas of irradiation damage. As a result, distinguishing defect structures created as artifacts during sample preparation from those created by electron- or neutron-irradiation can be challenging. Bulk nuclear graphite grades IG-110, NBG-18, and highly oriented pyrolytic graphite (HOPG) were oxidized using a new jet-polishing-like setup where oxygen is used as an etchant. This technique is shown to produce self-supporting electron-transparent TEM specimens free of irradiation-induced artifacts; thus, these specimens can be used as a baseline for in situ irradiation experiments as they have no irradiation-induced damage. Chapter Three examines the dynamic evolution of defect structures in nuclear graphite IG-110 subjected to electron-irradiation. As use of fast neutrons for irradiation experiments is dangerous, expensive, and time consuming, electron-irradiation is arguably a useful surrogate; however, comparisons between the two irradiating particles is also discussed. In situ video recordings of specimens undergoing simultaneous heating and electron-irradiation were used to analyze the dynamic atomic-level defect evolution in real time. Novel fullerene-like defect structures are shown to evolve as a direct result of high-temperature electron-irradiation and cause significant dimensional change to crystallites. Neutron-irradiated nuclear graphite IG-110 was supplied by Idaho National Laboratory as part of the Advanced Graphite Creep capsule experiments (AGC-3). Chapter Four reports the preliminary characterization of IG-110 neutron-irradiated at 817°C to a dose of 3.56 displacements per atom (dpa). Shown is experimental evidence of a 'ruck and tuck' defect occurring in high-temperature neutron-irradiated nuclear graphite. The 'ruck and tuck' defect arises due to irradiation-induced defects. The interaction of these defects results in the buckling of atomic planes and the formation of a structure composed of two partial carbon nanotubes. The "buckle, ruck and tuck" model was first theoretically predicted via computational modeling in 2011 as a plausible defect structure/mechanism occurring in high-temperature neutron-irradiated graphite by Prof. Malcolm Heggie et al. Chapter Four shows the first direct experimental results to support the "buckle, ruck and tuck" model. Chapter Five further characterizes nuclear graphite IG-110 neutron-irradiated at high temperature (>=800 °C) at doses of 1.73 and 3.56 dpa. Results show further evidence to support the 'buckle, ruck and tuck' model and additionally show the presence of larger concentric shelled fullerene-like defects. Fullerene-like defects were found to occur in disordered regions of the microstructure including within nanocracks (Mrozowski cracks). These results agree with high-temperature electron-irradiation studies which showed the formation of fullerene-like defects in-situ and give additional validity to the use of high-flux electron-irradiation as a useful approximation to neutron-irradiation. Furthermore, Chapter Five gives valuable insight to unresolved quantitative anomalies of historical models of graphite expansion and may improve the understanding of current empirical and theoretical models of irradiation-induced property changes in nuclear graphite."--Boise State University ScholarWorks.
Download or read book Irradiation Creep of Graphite written by and published by . This book was released on 1990 with total page 4 pages. Available in PDF, EPUB and Kindle. Book excerpt: Displacement damage of graphite by neutron irradiation causes graphite to change dimensions. This dimensional instability requires careful attention when graphite is used as as moderator and reflector material in nuclear devices. Natural gradients in flux and temperature result in time-varying differential growth generating stresses similar to thermal stresses with an ever increasing temperature gradient. Graphite, however, does have the ability to creep under irradiation, allowing the stress intensity to relax below the fracture strength of the material. Creep strain also serves to average the radiation-induced strains, thus contributing to the stability of the core. As the dimensional instability is a function of temperature, so are the creep characteristics of graphite, and it is of interest to generalize the available data for extension to more extreme conditions of fluence and temperature. Irradiation creep of graphite is characterized by two stages of creep; a primary stage that saturates with time and a secondary stage that is generally assumed to be linear and constant with time. Virtually all past studies have not considered primary creep in detail primarily because there is limited available data at the very low fluences required to saturate primary creep. It is the purpose of this study to carefully examine primary creep in detail over the irradiation temperature range of 150 to 1000°C. These studies also include the combined effects of creep, differential growth, and structural changes in graphite by irradiation. 3 refs., 5 figs.
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975-12 with total page 886 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Effect of Neutron Irradiation on the Liquid Sodium Dilation of Graphite written by D. L. Henry and published by . This book was released on 1965 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Radiation induced Dimensional Changes of Graphite Containing Carbon Black written by J. W. Helm and published by . This book was released on 1966 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Graphite written by R. E. Nightingale and published by Academic Press. This book was released on 2013-10-02 with total page 566 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear Graphite focuses on the development and uses of nuclear graphite, including machining practices, manufacture, nuclear properties and structure, radiation, and electrical resistance. The selection first discusses the applications of graphite in the nuclear industry, machining practices, and manufacture. Discussions focus on early, current, and future applications of graphite, impregnation, graphitization, purification, general machining techniques, and equipment and methods in the nuclear industry. The book then examines the structure and nuclear and properties of graphite. The text evaluates radiation-induced structural and dimensional changes; radiation effects on electrical and thermal properties; and radiation effects on mechanical properties. Topics include radiation effects on crystal structure, electrical resistance, thermoelectric power, magnetoresistance, coefficient of friction, irradiation under stress, and elastic moduli of nuclear graphite. The book also ponders on stored energy, annealing radiation effects, and gas-graphite systems. The selection is a dependable source of data for readers interested in the applications of nuclear graphite.
Download or read book Physical Properties of Graphite written by W. N. Reynolds and published by . This book was released on 1968 with total page 214 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Materials written by and published by . This book was released on 1969 with total page 304 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 International Aerospace Abstracts written by and published by . This book was released on 1965 with total page 970 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 Monthly Accession List written by Radiation Effects Information Center (Columbus, Ohio). and published by . This book was released on 1966 with total page 58 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1965 with total page 388 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Atoms for Peace Conference 1964 Third United Nations International Conference on the Peaceful Uses of Atomic Energy Geneva Switzerland August 31 Sept 9 1964 a Report by the United States Delegation written by U.S. Atomic Energy Commission and published by . This book was released on 1965 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Atoms for Peace Conference 1964 written by United States. Delegation to the International Conference on the Peaceful Uses of Atomic Energy and published by . This book was released on 1965 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt:
