Comprehensive Nuclear Materials book cover

Comprehensive Nuclear Materials

Five volume Set

Comprehensive Nuclear Materials 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.


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.

Hardbound, 3560 Pages

Published: February 2012

Imprint: Elsevier

ISBN: 978-0-08-056027-4


  • From the Foreword

    “Nuclear materials” denotes a field of great breadth and depth, whose topics address applications and facilities that depend upon nuclear reactions. The major topics within the field are devoted to the materials science and engineering surrounding fission and fusion reactions in energy conversion reactors. Most of the rest of the field is formed of the closely related materials science needed for the effects of energetic particles on the targets and other radiation areas of charged particle accelerators and plasma devices. A more complete but also more cumbersome descriptor, thus, would be “the science and engineering of materials for fission reactors, fusion reactors, and closely related topics”. In these areas the very existence of such technologies turns upon our capabilities to understand the physical behavior of materials. Performance of facilities and components to the demanding limits required are dictated by the capabilities of materials to withstand unique and aggressive environments. The unifying concept that runs through all aspects is the effect of radiation on materials. In this way the main feature is somewhat analogous to the unifying concept of elevated temperature in that part of materials science and engineering termed “high-temperature materials”.

    Nuclear materials came into existence in the 1950s, and began to grow as an internationally recognized field of endeavor late in that decade. The beginning in this field has been attributed to presentations and discussions that occurred at the First and Second International Conferences on the Peaceful Uses of Atomic Energy, held in Geneva in 1955 and 1958. Journal of Nuclear Materials, which is the home journal for this area of materials science, was founded in 1959. The development of nuclear materials science and engineering took place in the same rapid growth time period as the parent field of materials science and engineering. And similarly to the parent field, nuclear materials draws together the formerly separate disciplines of metallurgy, solid-state physics, ceramics, and materials chemistry that were early devoted to nuclear applications. The small priesthood of first researchers in half a dozen countries has now grown to a cohort of thousands, whose home institutions are anchored in more than 40 nations.

    The prodigious work, Comprehensive Nuclear Materials, captures the essence and the extensive scope of the field. It provides authoritative chapters that review the full range of endeavor. In the present day of glance and click “reading” of short snippets from the Internet, this is an old-fashioned book in the best sense of the word, which will be available in both electronic and printed form. All of the main segments of the field are covered, as well as most of the specialized areas and subtopics. With well over 100 chapters, the reader finds thorough coverage on topics ranging from fundamentals of atom movements after displacement by energetic particles, to testing and engineering analysis methods of large components. All the materials classes that have main application in nuclear technologies are visited, and the most important of them are covered in exhaustive fashion. Authors of the chapters are practitioners who are at the highest level of achievement and knowledge in their respective areas. Many of these authors not only have lived through a substantial part of the history sketched above, but they themselves are the architects. Without those represented here in the author list, the field would certainly be a weaker reflection of itself. It is no small feat that so many of my distinguished colleagues could have been persuaded to join this collective endeavor and to make the real sacrifices entailed in such time consuming work. I congratulate the Editor, Rudy Konings, and the associate Editors, Roger Stoller, Todd Allen and Shinsuke Yamanaka. This book will be an important asset to young researchers entering the field as well as a valuable resource to workers engaged in the enterprise at present.

    Dr. Louis K. Mansur
    Oak Ridge, Tennessee, USA
    May 2011


  • 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
    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
    Minerals and Natural Analogues


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