Author: M.R. Cundy
Publisher: Elsevier
ISBN: 1483163903
Category : Science
Languages : en
Pages : 348
Book Description
Measurement of Irradiation-Enhanced Creep in Nuclear Materials covers the proceedings of an international conference organized by the commission of the European communities. The book presents 37 papers that are organized according to the session of the conference. Each session focuses on various topics that relate to the irradiation creep of a specific material, which are ceramic nuclear fuels, graphite, and non-fissile metal and alloys. The text will be of great use for researchers and professionals whose work involves quantifying irradiation creep in nuclear materials.
Measurement of Irradiation-Enhanced Creep in Nuclear Materials
Author: M.R. Cundy
Publisher: Elsevier
ISBN: 1483163903
Category : Science
Languages : en
Pages : 348
Book Description
Measurement of Irradiation-Enhanced Creep in Nuclear Materials covers the proceedings of an international conference organized by the commission of the European communities. The book presents 37 papers that are organized according to the session of the conference. Each session focuses on various topics that relate to the irradiation creep of a specific material, which are ceramic nuclear fuels, graphite, and non-fissile metal and alloys. The text will be of great use for researchers and professionals whose work involves quantifying irradiation creep in nuclear materials.
Publisher: Elsevier
ISBN: 1483163903
Category : Science
Languages : en
Pages : 348
Book Description
Measurement of Irradiation-Enhanced Creep in Nuclear Materials covers the proceedings of an international conference organized by the commission of the European communities. The book presents 37 papers that are organized according to the session of the conference. Each session focuses on various topics that relate to the irradiation creep of a specific material, which are ceramic nuclear fuels, graphite, and non-fissile metal and alloys. The text will be of great use for researchers and professionals whose work involves quantifying irradiation creep in nuclear materials.
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1554
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1554
Book Description
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 960
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 960
Book Description
Scientific and Technical Aerospace Reports
Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1282
Book Description
Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1282
Book Description
Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.
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
Proceedings of the Fifth Conference on Carbon
Author: Sam Stuart
Publisher: Elsevier
ISBN: 1483151379
Category : Science
Languages : en
Pages : 652
Book Description
Proceedings of the Fifth Conference on Carbon
Publisher: Elsevier
ISBN: 1483151379
Category : Science
Languages : en
Pages : 652
Book Description
Proceedings of the Fifth Conference on Carbon
Accessions of Unlimited Distribution Reports
Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 74
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 74
Book Description
Metals Abstracts
Author:
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 1080
Book Description
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 1080
Book Description
Proceedings
Author: Conference on Carbon
Publisher:
ISBN:
Category : Carbon
Languages : en
Pages : 668
Book Description
Publisher:
ISBN:
Category : Carbon
Languages : en
Pages : 668
Book Description
Carbon
Author: Sam Stuart
Publisher: Elsevier
ISBN: 1483223388
Category : Science
Languages : en
Pages : 795
Book Description
Proceedings of the Fourth Conference on Carbon is a collection of manuscripts presented at the Fourth Conference on Carbon, held at the University of Buffalo on June 15-19, 1959, jointly sponsored by the American Carbon Committee and the University of Buffalo. The contributors explore the manufacture, properties, and use of carbonaceous materials. This book is organized into five parts encompassing 79 chapters. Parts I and II describe the surface and electronic properties, adsorption, and reactivity of carbonaceous materials, including carbon black, activated carbon, coal, and graphite. These parts also cover reactions such as thermal oxidation, gasification, and catalysis. Part III highlights the processes of carbonization, graphitization, and crystallite growth of carbon, while Part IV examines their mechanical and thermal properties. Part V looks into the raw materials used for the manufacture of certain carbon materials and the influence of several properties, including porosity and density. Organic chemists and carbon scientists and researchers will find this book invaluable.
Publisher: Elsevier
ISBN: 1483223388
Category : Science
Languages : en
Pages : 795
Book Description
Proceedings of the Fourth Conference on Carbon is a collection of manuscripts presented at the Fourth Conference on Carbon, held at the University of Buffalo on June 15-19, 1959, jointly sponsored by the American Carbon Committee and the University of Buffalo. The contributors explore the manufacture, properties, and use of carbonaceous materials. This book is organized into five parts encompassing 79 chapters. Parts I and II describe the surface and electronic properties, adsorption, and reactivity of carbonaceous materials, including carbon black, activated carbon, coal, and graphite. These parts also cover reactions such as thermal oxidation, gasification, and catalysis. Part III highlights the processes of carbonization, graphitization, and crystallite growth of carbon, while Part IV examines their mechanical and thermal properties. Part V looks into the raw materials used for the manufacture of certain carbon materials and the influence of several properties, including porosity and density. Organic chemists and carbon scientists and researchers will find this book invaluable.