
Comprehensive Nuclear Materials
- 1st Edition - May 12, 2011
- Editors: Rudy Konings, Todd R Allen, Roger E Stoller, Shinsuke Yamanaka
- Language: English
- eBook ISBN: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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Request a sales quoteComprehensive 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 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
RK
Rudy Konings
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Todd R Allen
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Roger E Stoller
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