5th FORUM on NEW MATERIALS PART B.

Intro -- 5th FORUM ON NEW MATERIALS PART B -- Preface -- Committees -- Table of Contents -- SECTION I - MATERIALS CHALLENGES FOR FUTURE NUCLEAR FISSION AND FUSION TECHNOLOGIES -- I-1 Low Activation Structural Materials for Nuclear Fusion Systems -- Design and Integration of ITER Divertor Components -- Tungsten as a Structural Divertor Material -- Microstructural Control for Improving Properties of V-4Cr-4Ti Alloys -- SiC/SiC Composites Irradiation Behaviour in Fusion Reactor Environment Conditions -- Experimental Development at a Pilot Plant Scale of a Reduced Activation Ferritic/Martensitic RAFM Steel, Asturfer® -- Corrosion Experiments of the Candidate Materials for Liquid Lithium Lead Blanket of Fusion Reactor -- I-2 Functional, Cladding and Fuel Materials for Nuclear Fission Reactors -- Utilization of Hydride Materials in Nuclear Reactors -- Progressive Development for Structural Integrity Quantification of Nuclear Grade Graphite in Very High Temperature Gas Cooled Reactor Core Environments -- Multiscale Modelling of the Influence of Damage on the Thermal Properties of Ceramic Matrix Composites -- General Corrosion Properties of Modified PNC1520 Austenitic Stainless Steel in Supercritical Water as a Fuel Cladding Candidate Material for Supercritical Water Reactor -- From High to Low Enriched Uranium Fuel in Research Reactors -- Simulation and Modelling the Heterogeneous Effects of the Microstructure MOX Fuels on their Effective Properties in Nominal Pressure Water Reactor Conditions -- Fabrication of Fuel and Recycling of Minor Actinides in Fast Reactors -- I-3 Radiation Effects -- Influence of the Microstructure on the U1-yAmyO2-x (y= 0.1 -- 0.15) Pellet Macroscopic Swelling -- Geometrical Aspects of Dislocation-Obstacle Interaction in Iron -- Quantitative TEM Investigations on EUROFER 97 Irradiated up to 32 Dpa.

The Influence of Helium and ODS on the Irradiation-Induced Hardening of Eurofer97 at 300°C -- SECTION II - MATERIALS TECHNOLOGY FOR NUCLEAR WASTE TREATMENT AND DISPOSAL -- Advantages Hot Isostatically Pressed Ceramic and Glass-Ceramic Waste Forms Bring to the Immobilization of Challenging Intermediate- and High-Level Nuclear Wastes -- Synthesis and Properties of Reaction-Bonded SiC Ceramic with Embedded UO2 - TRISO Coated Particles -- New Actinide Waste Forms with Pyrochlore and Garnet Structures -- An Innovative Hybrid Process Involving Plasma in a Cold Crucible Melter Devoted to the Futur Intermediate Level Waste Treatment: The SHIVA Technology -- Development of New Waste Forms to Immobilize Iodine-129 Released from a Spent Fuel Reprocessing Plant -- Study of New Filters Properties for Cs-137 Vapour Capture at High Temperature -- Using the Vitrification Test Rig for Process Improvements on the Waste Vitrification Plants -- Cold Crucible Inductive Melting Technology - Application to Vitrification and Ceramization of High Level and Actinide Wastes -- Lessons Learned from the Yucca Mountain and WIPP Projects -- Keywords Index -- Authors Index.

Materials Challenges for Future Nuclear Fission and Fusion TechnologiesSelected papers from the 5th Forum on New Materials, part of CIMTEC 2010-12 th International Ceramics Congress and 5th Forum on New Materials, Montecatini Terme, Italy, June 13-18, 2010.

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