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Comprehensive Nuclear Materials
1st Edition - May 12, 2011
Editors: Todd R Allen, Rudy Konings, Roger E Stoller, Shinsuke Yamanaka
Language: English
eBook ISBN:9780080560335
9 7 8 - 0 - 0 8 - 0 5 6 0 3 3 - 5
Comprehensive Nuclear Materials, Five Volume Set discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerat…Read more
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Comprehensive Nuclear Materials, Five Volume Set discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials. The work addresses the full panorama of contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds' leading scientists and engineers.
Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environment
Fully integrated with F-elements.net, a proprietary database containing useful cross-referenced property data on the lanthanides and actinides
Details contemporary developments in numerical simulation, modelling, experimentation, and computational analysis, for effective implementation in labs and plants
The work will be suitable for graduate students and above studying any materials aspect of nuclear science within academia, and engineering, as well as professional nuclear engineers and research scientists
Fundamental Properties of Defects in Metals Fundamental Point Defect Properties in Ceramics Radiation-Induced Effects on Microstructure Radiation-Induced Effects on Material Properties of Metals (Mechanical and Dimensional) Radiation-Induced Effects on Material Properties of Ceramics (Mechanical and Dimensional) The Effects of Helium in Irradiated Structural Alloys Radiation Damage Using Ion Beams Ab Initio Electronic Structure Calculations for Nuclear Materials Molecular Dynamics Interatomic Potential Development Primary Radiation Damage Formation Atomic-Level Level Dislocation Dynamics in Irradiated Metals Mean Field Reaction Rate Theory Kinetic Monte Carlo Simulations of Irradiation Effects Phase Field Methods Dislocation Dynamics Computational Thermodynamics: Application to Nuclear Materials Radiation-Induced Segregation The Actinides Elements: Properties and Characteristics Thermodynamic and Thermophysical Properties of the Actinide Oxides Thermodynamic and Thermophysical Properties of the Actinide Nitrides Thermodynamic and Thermophysical Properties of the Actinide Carbides Phase Diagrams of Actinide Alloys The U-F System Zirconium Alloys: Properties and Characteristics Nickel Alloys: Properties and Characteristics Properties of Austenitic Steels for Nuclear Reactor Applications Graphite: Properties and Characteristics Neutron Reflector Materials (Be, Hydrides) Proerties and Characteristics of SiC and SiC/SiC Composites Proerties and Characteristics of ZrC Properties of Liquid Metal Coolants Uranium Oxide and MOX Production Burnable Poison-Doped Fuel Thermal Properties of Irradiated UO₂ and MOX Radiation Effects in UO2 Fuel Performance of Light Water Reactors (Uranium Oxide and MOX) Fission Product Chemistry in Oxide Fuels Fuel Performance of Fast Spectrum Oxide Fuel Transient Response of LWR Fuels (RIA) Behaviour of LWR Fuel During Loss-of_Coolant Accidents Behaviour of Fast Reactor Fuels During Transient and Accident Conditions Core Concrete Interaction Metal Fuel Nitride Fuel Carbide Fuel Thorium Oxide Fuel Actinide Bearing Fuels and Transmutation Targets TRISO Fuel Production TRISO-Coated Particle Fuel Performance Advanced Concepts in TRISO Fuel Inert Matrix Fuel Composite Fuel (CERMET, CERCER) Sphere-Pac and VIPAC Fuel Uranium-Zirconium Hydride Fuel Molten Salt Reactor Fuel and Coolant Uranium Inter-Metallic Fuels (U-Al, U-Si, U-Mo) Metal Fuel-Cladding Interaction Ceramic Fuel-Cladding Interaction Thermal Spectrum Control Rod Materials Fast Spectrum Control Rod Materials Oxide Fuel Performance Modelling and Simulation Modeling of Fission-Gas Induced Swelling of Nuclear Fuels Matter Transport in Fast Reactor Fuels Modelling of Pellet Cladding Interaction Metal Fuel Performance Modelling and Simulation TRISO Fuel Performance Modelling and Simulation Modeling of Sphere-Pac Fuel Radiation Effects in Zirconium Alloys Radiation Damage in Austenitic Steels Ferritic Steels and Advanced Ferritic-Martensitic Steels Radiation Effects in Nickel-Based Alloys Radiation Damage of Reactor Pressure Vessel Steels Radiation Effects in Refractory Metals and Alloys Radiation Effects in SiC and SiC-SiC Oxide Dispersion Strengthened Steels Welds for Nuclear Systems Radiation Effects in Graphite Graphite in Gas-Cooled Reactors Vanadium for Nuclear Systems Concrete Fracture Toughness Master Curve of BCC Steels Ceramic Breeder Materials Tritium Barriers and Tritium Diffusion in Fusion Reactors Tungsten as a Plasma-Facing Material Carbon as a Fusion Plasma-Facing Material Beryllium as a Plasma-Facing Material for Near-Term Fusion Devices Physical and Mechanical Properties of Copper and Copper Alloys Ceramic Coating as Insulators Radiation Effects on the Physical Properties of Dielectric Insulators for Fusion Reactors Corrosion and Compatibility Water Chemistry Control in LWRs Corrosion of Zirconium Alloys Corrosion and Stress Corrosion Cracking of Ni-Base Alloys Corrosion and Stress Corrosion Cracking of Austenitic Stainless Steels Corrosion and Environmentally-Assisted Cracking of Carbon and Low-Alloy Steels Performance of Aluminium in Research Reactors Irradiation Assisted Stress Corrosion Cracking Material Performance in Lead-Alloys Material Performance in Molten Salts Material Performance in Helium-Cooled Systems Material Performance in Supercritical Water Material Performance in Sodium Spent Fuel Dissolution and Reprocessing Processes Degradation Issues in Aqueous Reprocessing Systems Spent Fuel as Waste Material Waste Containers Waste Glass Ceramic Waste Forms Metallic Waste Forms Graphite Minerals and Natural Analogues
No. of pages: 3560
Language: English
Edition: 1
Published: May 12, 2011
Imprint: Elsevier Science
eBook ISBN: 9780080560335
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Todd R Allen
Dr. Todd Allen is an Associate Professor in the Department of Engineering Physics at the University of Wisconsin – Madison since 2003. Professor Allen's research expertise is in the area of materials related issues in nuclear reactors, specifically radiation damage and corrosion. Dr. Allen has established the Extreme Environment Laboratory equipped with facilities for a wide array of high temperature studies as well as the ion beam laboratory for radiation damage studies. Dr. Allen is also the Scientific Director for the Advanced Test Reactor National Scientific User Facility at Idaho National Laboratory, a position that he holds in conjunction with his faculty position at the University of Wisconsin.
Affiliations and expertise
University of Wisconsin-Madison, WI, USA
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Rudy Konings
Rudy Konings graduated from Utrecht University with an MSc in Earth Sciences in 1985. He then joined the Netherlands Energy Research Foundation ECN as researcher in the field of thermodynamics of nuclear materials and defended his PhD at the University of Amsterdam in 1990. He stayed at ECN and subsequently at NRG (Nuclear Research and Consultancy Group) working on nuclear fuel-related issues, his last role being head of the unit "Fuel, Actinides and Isotopes". In 1999 he joined the European Commission's Joint Research Centre in Karlsruhe (formerly the Institute for Transuranium Elements). There he currently is the head of the Nuclear Fuel Safety Unit, responsible for the nuclear fuel related research, comprising fuel synthesis, characterization, and accident behavior. In addition he is part-time professor at the Delft University of Technology, holding the chair "Chemistry of the nuclear fuel cycle". His research interests are nuclear fuels and actinide materials, with particular emphasis on high temperature chemistry and thermodynamics. He is a (co)author of more than 300 scientific publications in peer-reviewed journal and 14 book chapters, has been editor of Journal of Nuclear Materials (2009-2012), and editor-in-chief of the first edition of Comprehensive Nuclear Materials.
Affiliations and expertise
Head of the Nuclear Fuel Safety Unit, European Commission's Joint Research Centre, Karlsruhe, Germany
RS
Roger E Stoller
Dr. Stoller is currently a Distinguished Research Staff Member in the Materials Science and Technology Division of the Oak Ridge National Laboratory, and serves as the ORNL Program Manager for Fusion Reactor Materials for ORNL. He joined ORNL in 1984, and is actively involved in research on the effects of radiation on structural materials and fuels for nuclear energy systems. His primary expertise is in the area of computational modeling and simulation. He has authored or co-authored more than 100 publications and reports on the effects of radiation on materials, as well as having edited the proceedings of several international conferences.
Affiliations and expertise
Oak Ridge National Laboratory, TN, USA
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Shinsuke Yamanaka
Shinsuke Yamanaka has been a Professor in the Division of Sustainable Energy and Environmental Engineering, Graduate School of Engineering, Osaka University since 1998. Prof. Yamanaka has studied the thermophysics and thermochemistry of nuclear fuel and materials. His research for the hydrogen behavior in LWR fuel cladding is notable among his achievements and he received the Young Scientist Award (1980) and the Best Paper Award (2004) from Japan's Atomic Energy Society. Prof. Yamanaka has been the program officer of Japan's Science and Technology Agency since 2005 and the visiting professor of Fukui University since 2009. He is also the associate dean of the Graduate School of Engineering at Osaka University.
Affiliations and expertise
Osaka University, Osaka, Japan
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