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Author: J. H. W. Simmons
Publisher: Elsevier
ISBN: 1483186490
Category : Technology & Engineering
Languages : en
Pages : 264
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Book Description
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.
Author: J. H. W. Simmons
Publisher: Elsevier
ISBN: 1483186490
Category : Technology & Engineering
Languages : en
Pages : 264
Get Book Here
Book Description
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.
Author: & The Minerals, Metals Materials Society
Publisher: Springer
ISBN: 3030058611
Category : Technology & Engineering
Languages : en
Pages : 1631
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Book Description
This collection features papers presented at the 148th Annual Meeting & Exhibition of The Minerals, Metals & Materials Society.
Author: T.D. Burchell
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 568
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Book Description
This study begins with a review of carbon materials, emphasizing structure and chemical bonding in various forms of carbon. It then goes on to discuss advanced technologies for the manufacture and modification of carbon-based materials and their practical applications.
Author: Hubert Jäger
Publisher: John Wiley & Sons
ISBN: 3527674039
Category : Technology & Engineering
Languages : de
Pages : 1006
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Book Description
- Hochaktuelles Thema: Kohlenstoff- und Graphitmaterialien gehören aufgrund ihrer ausgezeichneten Eigenschaften und vielfältigen Anwendungsmöglichkeiten in unzähligen Bereichen, von der Nanotechnologie bis hin zur Elektronik, zu den interessantesten Verbindungsklassen. - Einzigartig und anwendungsorientiert: Es gibt viele Publikationen, die sich mit Materialien aus Kohlenstoff und Graphit beschäftigen. Dieses zweibändige Fachbuch gibt jedoch einen ausgezeichneten Überblick über Fertigung, Einsatz und Anwendung dieser Materialien in der Industrie. - Große Zielgruppe: Chemiker aus den Bereichen Elektrochemie (Li-Ionen-Batterien), Maschinenbau, Nukleartechnologie, Nanotechnologie, Katalyse, Keramik, Fasern, Polymere u.v.m. - Exzellentes Referenzwerk mit mehr als 1000 Seiten: von polygranularen Materialien bis zu Fullerenen, von Nanoröhren bis zu aktiviertem Kohlenstoff, alle wichtigen Kohlenstoff- und Graphitklassen werden behandelt.
Author: Yongqiang Wang
Publisher: MDPI
ISBN: 303936362X
Category : Science
Languages : en
Pages : 196
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Book Description
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.
Author: International Atomic Energy Agency
Publisher: IAEA Tecdoc Series No. 1790
ISBN: 9789201040169
Category : Technology & Engineering
Languages : en
Pages : 0
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Book Description
Graphite is widely used in the nuclear industry and in research facilities and this has led to increasing amounts of irradiated graphite residing in temporary storage facilities pending disposal. This publication arises from a coordinated research project (CRP) on the processing of irradiated graphite to meet acceptance criteria for waste disposal.
Author: Pascal Yvon
Publisher: Woodhead Publishing
ISBN: 0081009127
Category : Technology & Engineering
Languages : en
Pages : 686
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Book Description
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
Author: Brian Thomas Kelly
Publisher: Chapman & Hall
ISBN: 9780853349600
Category : Science
Languages : en
Pages : 477
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Book Description
Author: J. Koutský
Publisher: Elsevier
ISBN: 1483291626
Category : Technology & Engineering
Languages : en
Pages : 362
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Book Description
Maintaining the integrity of nuclear power plants is critical in the prevention or control of severe accidents. This monograph deals with both basic groups of structural materials used in the design of light-water nuclear reactors, making the primary safety barriers of NPPs. Emphasis is placed on materials used in VVER-type nuclear reactors: Cr-Mo-V and Cr-Ni-Mo-V steel for RPV and Zr-Nb alloys for fuel element cladding. The book is divided into 7 main chapters, with the exception of the opening one and the chapter providing a phenomenological background for the subject of radiation damage. Chapters 3-6 are devoted to RPV steels and chapters 7-9 to zirconium alloys, analysing their radiation damage structure, changes of mechanical properties due to neutron irradiation as well as factors influencing the degree of their performance degradation. The recovery of damaged materials is also discussed. Considerable attention is paid to a comparison of VVER-type and western-type light-water materials. This monograph will be of great value to postgraduate students in nuclear engineering and materials science, and for designers and research workers in nuclear energy.
Author: Hugh O. Pierson
Publisher: William Andrew
ISBN: 0815517394
Category : Technology & Engineering
Languages : en
Pages : 420
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Book Description
This book is a review of the science and technology of the element carbon and its allotropes: graphite, diamond and the fullerenes. This field has expanded greatly in the last three decades stimulated by many major discoveries such as carbon fibers, low-pressure diamond, and the fullerenes. The need for such a book has been felt for some time. These carbon materials are very different in structure and properties. Some are very old (charcoal), others brand new (the fullerenes). They have different applications and markets and are produced by different segments of the industry.Few studies are available that attempt to review the entire field of carbon as a whole discipline. Moreover these studies were written several decades ago and a generally outdated since the development of the technology is moving very rapidly and scope of applications is constantly expanding and reaching into new fields such as aerospace, automotive, semiconductors, optics, and electronics. In this book the author provides a valuable, up-to-date account of both the newer and traditional forms of carbon, both naturally occurring and man-made. This volume will be a valuable resource for both specialists in, and occasional users of carbon materials.
