Download or read book Ion Irradiation induced Microstructural Change in SiC written by Chien-Hung Chen and published by . This book was released on 2015 with total page 117 pages. Available in PDF, EPUB and Kindle. Book excerpt: The high temperature radiation resistance of nuclear materials has become a key issue in developing future nuclear reactors. Because of its mechanical stability under high-energy neutron irradiation and high temperature, silicon carbide (SiC) has great potential as a structural material in advanced nuclear energy systems. A newly developed nano-engineered (NE) 3C SiC with a nano-layered stacking fault (SFs) structure has been recently considered as a prospective choice due to enhanced point defect annihilation between layer-type structures, leading to outstanding radiation durability. The objective of this project was to advance the understanding of gas bubble formation mechanisms under irradiation conditions in SiC. In this work, microstructural evolution induced by helium implantation and ion irradiation was investigated in single crystal and NE SiC. Elastic recoil detection analysis confirmed that the as-implanted helium depth profile did not change under irradiation to 30 dpa at 700 °C. Helium bubbles were found in NE SiC after heavy ion irradiation at a lower temperature than in previous literature results. These results expand the current understanding of helium migration mechanism of NE SiC under high temperature irradiation environment. No obvious bubble growth was observed after ion irradiation at 700 °C, suggesting a long helium bubble incubation process under continued irradiation at this temperature and dose. As determined by electron energy loss spectroscopy measurements, only 1 % of the implanted helium atoms are trapped in bubbles. Helium redistribution and release was observed in the TEM samples under in-situ irradiation at 800 °C. In-situ TEM analysis revealed that the nano-layered SF structure is radiation tolerant below a dose of about 15 dpa at 800 °C, but continued irradiation to 20 dpa under these in-situ conditions leads to loss of the stacking fault structure, which may be a manifestation of irradiating thin TEM foils. The irradiation stability of the SF structure under bulk irradiation remains unknown. This stacking fault structure is critical since it suppresses the formation of dislocation loops normally observed under these irradiation conditions. Systematic studies towards understanding the role of defect migration under irradiation on the evolution of helium bubbles in NE SiC were performed. Keywords SiC, Irradiation, Helium Bubble, TEM/STEM, EELS, In-situ, ERDA

Download or read book Microstructural Stability of SiC SiC Composites Under Dual Beam Ion Irradiation written by H. Takahashi and published by . This book was released on 2001 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Microstructural evolution of silicon carbide fiber-reinforced silicon carbide matrix composites (SiC/SiC composites) during dual-beam ion irradiation was studied. The composites had been fabricated by means of chemical vapor infiltration (CVI) and polymer impregnation and pyrolysis (PIP) methods using advanced fibers, i.e., Hi-NicalonTM Type-S and TyrannoTM-SA, as well as conventional fibers. Dual-beam ion irradiation was performed to 10 dpa at 873K and 60appmHe/dpa. Composites with advanced low-oxygen near-stoichiometric SiC fiber with high crystallinity and beta-SiC matrix exhibited superior irradiation resistance, in contrast to that amorphous Si-C-O based fibers and conventional polymer-derived matrix exhibited microstructural instability in association with irradiation-induced crystallization. Pyrolytic carbon deposited as the fiber-matrix (F-M) interphase exhibited irradiation-induced amorphization and the helium co-implantation enhanced it. Post-irradiation heat treatment caused significant microstructural changes across the F-M interphases at temperatures as low as the composites are supposed to retain their mechanical strength.

Download or read book Mechanical and Structural Property Changes of Monolithic SiC and Advanced SiC SiC Composites Due to Low Temperature He Ion Irradiation and Post Irradiation High Temperature Annealing written by S. Nogami and published by . This book was released on 2004 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: The hardness and elastic modulus of monolithic ?-SiC and advanced SiC/SiC composites irradiated to He-concentrations of from 1000 to 20 000 at.ppm at a temperature below 100°C were investigated. Changes in the hardness and elastic modulus were correlated with He release behavior and with irradiation-induced microstructural changes and swelling. The hardness and elastic modulus of the irradiated specimens decreased with He concentration. Amorphized regions were observed in the He-irradiated monolithic ?-SiC. The mechanical property changes likely were due to irradiation-induced amorphization. By the annealing at 1200°C, nearly full recovery was achieved. He release peaks from the pyrolitic graphite, monolithic SiC, and the SiC/SiC composites at 250, 700, 1000, and 1150°C, were identified. The correlation between the mechanical property and microstructural changes and the He release behavior are discussed.

Download or read book Silicon Carbide written by Wolfgang J. Choyke and published by Springer Science & Business Media. This book was released on 2013-04-17 with total page 911 pages. Available in PDF, EPUB and Kindle. Book excerpt: Since the 1997 publication of "Silicon Carbide - A Review of Fundamental Questions and Applications to Current Device Technology" edited by Choyke, et al., there has been impressive progress in both the fundamental and developmental aspects of the SiC field. So there is a growing need to update the scientific community on the important events in research and development since then. The editors have again gathered an outstanding team of the world's leading SiC researchers and design engineers to write on the most recent developments in SiC.

Download or read book Effects of Radiation on Materials written by Martin L. Grossbeck and published by ASTM International. This book was released on 2004 with total page 767 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book 23rd Annual Conference on Composites Advanced Ceramics Materials and Structures B Volume 20 Issue 4 written by Ersan Ustundag and published by John Wiley & Sons. This book was released on 2009-09-28 with total page 619 pages. Available in PDF, EPUB and Kindle. Book excerpt: This volume is part of the Ceramic Engineering and Science Proceeding (CESP) series. This series contains a collection of papers dealing with issues in both traditional ceramics (i.e., glass, whitewares, refractories, and porcelain enamel) and advanced ceramics. Topics covered in the area of advanced ceramic include bioceramics, nanomaterials, composites, solid oxide fuel cells, mechanical properties and structural design, advanced ceramic coatings, ceramic armor, porous ceramics, and more.

Download or read book Effects of Radiation on Materials written by Stan T. Rosinski and published by ASTM International. This book was released on 2001 with total page 879 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Ion Beam Technology and Applications written by Ozan Artun and published by BoD – Books on Demand. This book was released on 2023-11-22 with total page 112 pages. Available in PDF, EPUB and Kindle. Book excerpt: The scientific and commercial purposes of ion beams are remarkable in many fields because ion beam technology is a primary tool that provides a wide range of applications in science, medicine, space, and engineering. This book presents theoretical and experimental knowledge about ion beam applications and technology. It includes six chapters that address such topics as the interaction of ion beams with matter, the evaluation of nuclear material damage, surface microstructure changes, oblique Ar+ sputtered SiC thin films, electron beam processing, and ribbon ion beams.

Download or read book Energy Research Abstracts written by and published by . This book was released on 1994-05 with total page 438 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 Radiation Damage in Materials written by Yongqiang Wang and published by MDPI. This book was released on 2020-12-28 with total page 196 pages. Available in PDF, EPUB and Kindle. Book excerpt: The complexity of radiation damage effects in materials that are used in various irradiation environments stems from the fundamental particle–solid interactions and the subsequent damage recovery dynamics after the collision cascades, which involves multiple length and time scales. Adding to this complexity are the transmuted impurities that are unavoidable from accompanying nuclear processes. Helium is one such impurity that plays an important and unique role in controlling the microstructure and properties of materials used in fast fission reactors, plasma-facing and structural materials in fusion devices, spallation neutron target designs, actinides, tritium-containing materials, and nuclear waste. Their ultra-low solubility in virtually all solids forces He atoms to self-precipitate into small bubbles that become nucleation sites for further void growth under radiation-induced vacancy supersaturations, resulting in material swelling and high-temperature He embrittlement, as well as surface blistering under low-energy and high-flux He bombardment. This Special Issue, “Radiation Damage in Materials—Helium Effects”, contains review articles and full-length papers on new irradiation material research activities and novel material ideas using experimental and/or modeling approaches. These studies elucidate the interactions of helium with various extreme environments and tailored nanostructures, as well as their impact on microstructural evolution and material properties.

Download or read book Materials Transactions JIM written by and published by . This book was released on 2005 with total page 712 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fundamentals of Radiation Materials Science written by GARY S. WAS and published by Springer. This book was released on 2016-07-08 with total page 1014 pages. Available in PDF, EPUB and Kindle. Book excerpt: The revised second edition of this established text offers readers a significantly expanded introduction to the effects of radiation on metals and alloys. It describes the various processes that occur when energetic particles strike a solid, inducing changes to the physical and mechanical properties of the material. Specifically it covers particle interaction with the metals and alloys used in nuclear reactor cores and hence subject to intense radiation fields. It describes the basics of particle-atom interaction for a range of particle types, the amount and spatial extent of the resulting radiation damage, the physical effects of irradiation and the changes in mechanical behavior of irradiated metals and alloys. Updated throughout, some major enhancements for the new edition include improved treatment of low- and intermediate-energy elastic collisions and stopping power, expanded sections on molecular dynamics and kinetic Monte Carlo methodologies describing collision cascade evolution, new treatment of the multi-frequency model of diffusion, numerous examples of RIS in austenitic and ferritic-martensitic alloys, expanded treatment of in-cascade defect clustering, cluster evolution, and cluster mobility, new discussion of void behavior near grain boundaries, a new section on ion beam assisted deposition, and reorganization of hardening, creep and fracture of irradiated materials (Chaps 12-14) to provide a smoother and more integrated transition between the topics. The book also contains two new chapters. Chapter 15 focuses on the fundamentals of corrosion and stress corrosion cracking, covering forms of corrosion, corrosion thermodynamics, corrosion kinetics, polarization theory, passivity, crevice corrosion, and stress corrosion cracking. Chapter 16 extends this treatment and considers the effects of irradiation on corrosion and environmentally assisted corrosion, including the effects of irradiation on water chemistry and the mechanisms of irradiation-induced stress corrosion cracking. The book maintains the previous style, concepts are developed systematically and quantitatively, supported by worked examples, references for further reading and end-of-chapter problem sets. Aimed primarily at students of materials sciences and nuclear engineering, the book will also provide a valuable resource for academic and industrial research professionals. Reviews of the first edition: "...nomenclature, problems and separate bibliography at the end of each chapter allow to the reader to reach a straightforward understanding of the subject, part by part. ... this book is very pleasant to read, well documented and can be seen as a very good introduction to the effects of irradiation on matter, or as a good references compilation for experimented readers." - Pauly Nicolas, Physicalia Magazine, Vol. 30 (1), 2008 “The text provides enough fundamental material to explain the science and theory behind radiation effects in solids, but is also written at a high enough level to be useful for professional scientists. Its organization suits a graduate level materials or nuclear science course... the text was written by a noted expert and active researcher in the field of radiation effects in metals, the selection and organization of the material is excellent... may well become a necessary reference for graduate students and researchers in radiation materials science.” - L.M. Dougherty, 07/11/2008, JOM, the Member Journal of The Minerals, Metals and Materials Society.

Download or read book Multiscale Modeling of Evolution of SiC Microstructure Due to Radiation and Corrosion written by Cheng Liu and published by . This book was released on 2018 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: SiC is an attractive material for nuclear energy, aerospace and semiconductor industries because of its uniquely combined properties, such as high-temperature strength, low neutron cross section, excellent corrosion and oxidation resistance, wide band-gap and low thermal expansion coefficient. Current and proposed applications include nuclear fuel components, nuclear structural components, airplane turbines, aerospace thermal protection layers and semiconductor electronics, etc. High temperature, irradiation and oxidizing environments can lead to degradation of SiC and its reduced reliability in application systems. This thesis is focused on understanding radiation-induced defects generation and evolution and as well as mechanisms of environmental degradation. Firstly, I report a statistical analysis of sizes and compositions of clusters produced in cascades during irradiation of SiC. The results are obtained by integrating molecular dynamics simulations of cascades caused by primary knock-on atoms (PKAs) over PKA energy spectrum derived from Stopping Range of Ions in Matter (SRIM) code. It is found that distributions of cluster size n obey a power law [f=A/n^S] and these clusters are dominated by carbons defects. Secondly, distribution of black spot defects (BSDs) and small clusters in irradiated 3C-SiC has been investigated by combining microscopy characterization with cluster dynamics (CD) model. It is found that there are small clusters identified in scanning transmission electron microscopy (STEM) invisible in TEM images. Simulations showed that both established properties of point defects (PDs) generation, reaction, clustering, and cluster dissociation, and additional phenomena of clusters generation, diffusion and morphology preference are necessary to be considered in a predictive model on cluster evolution in ion irradiated SiC. Then, based on CD model above, I developed a swelling model to estimate the swelling contributed by defects, which qualitatively explains that the swelling estimated based on X-Ray diffraction (XRD) is larger than that based on TEM is because there are PDs and small clusters invisible from TEM. Lastly, our molecular dynamics simulations show Incoherent grain boundaries (GBs) were more vulnerable to oxidation than single crystals, whereas oxidation of bicrystals with coherent GBs proceeded at a similar rate to that on single crystals. The accelerated oxidation along incoherent GBs can be attributed to larger free volume and silicon atoms with more negative charge state near GBs.

Download or read book Advances in Science and Technology of Mn 1AXn Phases written by I M Low and published by Elsevier. This book was released on 2012-10-26 with total page 474 pages. Available in PDF, EPUB and Kindle. Book excerpt: Advances in Science and Technology of Mn+1AXn Phases presents a comprehensive review of synthesis, microstructures, properties, ab-initio calculations and applications of Mn+1AXn phases and targets the continuing research of advanced materials and ceramics. An overview of the current status, future directions, challenges and opportunities of Mn+1AXn phases that exhibit some of the best attributes of metals and ceramics is included. Students of materials science and engineering at postgraduate level will value this book as a reference source at an international level for both teaching and research in materials science and engineering. In addition to students the principal audiences of this book are ceramic researchers, materials scientists and engineers, materials physicists and chemists. The book is also an invaluable reference for the professional materials and ceramics societies. The most up-to-date and comprehensive research data on MAX phases is presented Written by highly knowledgeable and well-respected researchers in the field Discusses new and unusual properties

Download or read book The Analysis of Nuclear Materials and Their Environments written by Claude André Degueldre and published by Springer. This book was released on 2017-10-11 with total page 308 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book provides an overview of passive and interactive analytical techniques for nuclear materials. The book aims to update readers on new techniques available and provide an introduction for those who are new to the topic or are looking to move into actinides and nuclear materials science. The characterization of actinide species and radioactive materials is vital for understanding how these elements and radioactive isotopes are formed and behave and how these materials can be improved. The analysis of the actinides or radioactive materials goes beyond spent fuel science to the applicable complete fuel cycle and including analysis of reactor materials.

Download or read book An Introduction to Nuclear Materials written by K. Linga Murty and published by John Wiley & Sons. This book was released on 2013-07-26 with total page 398 pages. Available in PDF, EPUB and Kindle. Book excerpt: Covering both fundamental and advanced aspects in an accessible way, this textbook begins with an overview of nuclear reactor systems, helping readers to familiarize themselves with the varied designs. Then the readers are introduced to different possibilities for materials applications in the various sections of nuclear energy systems. Materials selection and life prediction methodologies for nuclear reactors are also presented in relation to creep, corrosion and other degradation mechanisms. An appendix compiles useful property data relevant for nuclear reactor applications. Throughout the book, there is a thorough coverage of various materials science principles, such as physical and mechanical metallurgy, defects and diffusion and radiation effects on materials, with serious efforts made to establish structure-property correlations wherever possible. With its emphasis on the latest developments and outstanding problems in the field, this is both a valuable introduction and a ready reference for beginners and experienced practitioners alike.