Author: George P. Sabol
Publisher: ASTM International
ISBN: 0803124996
Category : Microstructure
Languages : en
Pages : 953
Book Description
Zirconium in the Nuclear Industry
Author: George P. Sabol
Publisher: ASTM International
ISBN: 0803124996
Category : Microstructure
Languages : en
Pages : 953
Book Description
Publisher: ASTM International
ISBN: 0803124996
Category : Microstructure
Languages : en
Pages : 953
Book Description
Microbeam Analysis
Author: D Williams
Publisher: CRC Press
ISBN: 9780750306850
Category : Science
Languages : en
Pages : 546
Book Description
Microbeam Analysis provides a major forum for the discussion of the latest microanalysis techniques using electron, ion, and photon beams. The volume contains 250 papers from the leading researchers in this advancing field. Researchers in physics, materials science, and electrical and electronic engineering will find useful information in this volume.
Publisher: CRC Press
ISBN: 9780750306850
Category : Science
Languages : en
Pages : 546
Book Description
Microbeam Analysis provides a major forum for the discussion of the latest microanalysis techniques using electron, ion, and photon beams. The volume contains 250 papers from the leading researchers in this advancing field. Researchers in physics, materials science, and electrical and electronic engineering will find useful information in this volume.
Comprehensive Nuclear Materials
Author:
Publisher: Elsevier
ISBN: 0081028660
Category : Science
Languages : en
Pages : 4871
Book Description
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
Publisher: Elsevier
ISBN: 0081028660
Category : Science
Languages : en
Pages : 4871
Book Description
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
Zirconium in the Nuclear Industry
Author: George P. Sabol
Publisher: ASTM International
ISBN: 0803124066
Category : Nuclear fuel claddings
Languages : en
Pages : 907
Book Description
Publisher: ASTM International
ISBN: 0803124066
Category : Nuclear fuel claddings
Languages : en
Pages : 907
Book Description
Zirconium in the Nuclear Industry
Author: Gerry D. Moan
Publisher: ASTM International
ISBN: 0803128959
Category : Nuclear fuel claddings
Languages : en
Pages : 891
Book Description
Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.
Publisher: ASTM International
ISBN: 0803128959
Category : Nuclear fuel claddings
Languages : en
Pages : 891
Book Description
Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.
Zirconium in the Nuclear Industry: Tenth International Symposium
Author: A. M. Garde
Publisher: ASTM International
ISBN: 0803120117
Category : Nuclear fuel claddings
Languages : en
Pages : 805
Book Description
Publisher: ASTM International
ISBN: 0803120117
Category : Nuclear fuel claddings
Languages : en
Pages : 805
Book Description
Transmission Electron Microscopy
Author: David B. Williams
Publisher: Springer Science & Business Media
ISBN: 1475725191
Category : Science
Languages : en
Pages : 708
Book Description
Electron microscopy has revolutionized our understanding the extraordinary intellectual demands required of the mi of materials by completing the processing-structure-prop croscopist in order to do the job properly: crystallography, erties links down to atomistic levels. It now is even possible diffraction, image contrast, inelastic scattering events, and to tailor the microstructure (and meso structure ) of materials spectroscopy. Remember, these used to be fields in them to achieve specific sets of properties; the extraordinary abili selves. Today, one has to understand the fundamentals ties of modem transmission electron microscopy-TEM of all of these areas before one can hope to tackle signifi instruments to provide almost all of the structural, phase, cant problems in materials science. TEM is a technique of and crystallographic data allow us to accomplish this feat. characterizing materials down to the atomic limits. It must Therefore, it is obvious that any curriculum in modem mate be used with care and attention, in many cases involving rials education must include suitable courses in electron mi teams of experts from different venues. The fundamentals croscopy. It is also essential that suitable texts be available are, of course, based in physics, so aspiring materials sci for the preparation of the students and researchers who must entists would be well advised to have prior exposure to, for carry out electron microscopy properly and quantitatively.
Publisher: Springer Science & Business Media
ISBN: 1475725191
Category : Science
Languages : en
Pages : 708
Book Description
Electron microscopy has revolutionized our understanding the extraordinary intellectual demands required of the mi of materials by completing the processing-structure-prop croscopist in order to do the job properly: crystallography, erties links down to atomistic levels. It now is even possible diffraction, image contrast, inelastic scattering events, and to tailor the microstructure (and meso structure ) of materials spectroscopy. Remember, these used to be fields in them to achieve specific sets of properties; the extraordinary abili selves. Today, one has to understand the fundamentals ties of modem transmission electron microscopy-TEM of all of these areas before one can hope to tackle signifi instruments to provide almost all of the structural, phase, cant problems in materials science. TEM is a technique of and crystallographic data allow us to accomplish this feat. characterizing materials down to the atomic limits. It must Therefore, it is obvious that any curriculum in modem mate be used with care and attention, in many cases involving rials education must include suitable courses in electron mi teams of experts from different venues. The fundamentals croscopy. It is also essential that suitable texts be available are, of course, based in physics, so aspiring materials sci for the preparation of the students and researchers who must entists would be well advised to have prior exposure to, for carry out electron microscopy properly and quantitatively.
Proceedings of the ... International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
Author:
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 1008
Book Description
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 1008
Book Description
Study of Point Defect Mobilities in Zirconium During Electron Irradiation in a HVEM
Author: Atomic Energy of Canada Limited
Publisher: Chalk River, Ont. : Chalk River Laboratories
ISBN:
Category : Alloys
Languages : en
Pages : 34
Book Description
A high voltage electron microscope (HVEM) was used to investigate the nature of intrinsic point effects in a-Zirconium by direct observation of dislocation climb and cavity growth or shrinkage. The material used was Marz-grade zirconium that had been pre-irradiated with neutrons at 740 K in the Dounreay Fast Reactor. Dislocation loops of vacancy character that were produced during the neutron irradiation were studied by further irradiation with electrons in the HVEM. C-component network dislocations and cavities were also studied.
Publisher: Chalk River, Ont. : Chalk River Laboratories
ISBN:
Category : Alloys
Languages : en
Pages : 34
Book Description
A high voltage electron microscope (HVEM) was used to investigate the nature of intrinsic point effects in a-Zirconium by direct observation of dislocation climb and cavity growth or shrinkage. The material used was Marz-grade zirconium that had been pre-irradiated with neutrons at 740 K in the Dounreay Fast Reactor. Dislocation loops of vacancy character that were produced during the neutron irradiation were studied by further irradiation with electrons in the HVEM. C-component network dislocations and cavities were also studied.
Nuclear Materials under Irradiation
Author: Serge Bouffard
Publisher: John Wiley & Sons
ISBN: 1394256280
Category : Technology & Engineering
Languages : en
Pages : 241
Book Description
At every stage of the fuel cycle, the materials used are at the heart of nuclear energy safety issues. These materials, which range from steel to polymers, including ceramics, glass, concrete and graphite, are submitted to extreme stresses combining mechanical, thermal and irradiation constraints. The objective of this book is to provide a basis for the research of nuclear materials subjected to irradiation, with the desire to contextualize them in the industrial environment. Therefore, most of the chapters are co-authored and contain a mix of basic and applied research. The reader will find chapters on nuclear reactor materials (structural materials, neutron absorbers, moderators and nuclear fuel) and on materials in waste management (glass, concrete and organic materials). These material chapters are complemented by more general information on defects and their creation, radiolysis and irradiation and characterization tools.
Publisher: John Wiley & Sons
ISBN: 1394256280
Category : Technology & Engineering
Languages : en
Pages : 241
Book Description
At every stage of the fuel cycle, the materials used are at the heart of nuclear energy safety issues. These materials, which range from steel to polymers, including ceramics, glass, concrete and graphite, are submitted to extreme stresses combining mechanical, thermal and irradiation constraints. The objective of this book is to provide a basis for the research of nuclear materials subjected to irradiation, with the desire to contextualize them in the industrial environment. Therefore, most of the chapters are co-authored and contain a mix of basic and applied research. The reader will find chapters on nuclear reactor materials (structural materials, neutron absorbers, moderators and nuclear fuel) and on materials in waste management (glass, concrete and organic materials). These material chapters are complemented by more general information on defects and their creation, radiolysis and irradiation and characterization tools.