| Preface |
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| Committees |
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SECTION I MATERIALS CHALLENGES FOR FUTURE NUCLEAR FISSION AND FUSION TECHNOLOGIES |
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I-1 LOW ACTIVATION STRUCTURAL MATERIALS FOR NUCLEAR FUSION SYSTEMS |
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Design and Integration of ITER Divertor Components |
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1 | (10) |
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Tungsten as a Structural Divertor Material |
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11 | (11) |
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Microstructural Control for Improving Properties of V-4Cr-4Ti Alloys |
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22 | (5) |
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SiC/SiC Composites Irradiation Behaviour in Fusion Reactor Environment Conditions |
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27 | (9) |
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Experimental Development at a Pilot Plant Scale of a Reduced Activation Ferritic/Martensitic RAFM Steel, Asturfer® |
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36 | (5) |
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Corrosion Experiments of the Candidate Materials for Liquid Lithium Lead Blanket of Fusion Reactor |
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41 | (10) |
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I-2 FUNCTIONAL, CLADDING AND FUEL MATERIALS FOR NUCLEAR FISSION REACTORS |
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Utilization of Hydride Materials in Nuclear Reactors |
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51 | (8) |
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Progressive Development for Structural Integrity Quantification of Nuclear Grade Graphite in Very High Temperature Gas Cooled Reactor Core Environments |
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59 | (6) |
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Multiscale Modelling of the Influence of Damage on the Thermal Properties of Ceramic Matrix Composites |
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65 | (7) |
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General Corrosion Properties of Modified PNC1520 Austenitic Stainless Steel in Supercritical Water as a Fuel Cladding Candidate Material for Supercritical Water Reactor |
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72 | (6) |
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From High to Low Enriched Uranium Fuel in Research Reactors |
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78 | (13) |
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Simulation and Modelling the Heterogeneous Effects of the Microstructure MOX Fuels on their Effective Properties in Nominal Pressure Water Reactor Conditions |
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91 | (6) |
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Fabrication of Fuel and Recycling of Minor Actinides in Fast Reactors |
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97 | (7) |
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Influence of the Microstructure on the U1-yAmyO2-x (y=0.1; 0.15) Pellet Macroscopic Swelling |
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104 | (5) |
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Geometrical Aspects of Dislocation-Obstacle Interaction in Iron |
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109 | (9) |
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Quantitative TEM Investigations on EUROFER 97 Irradiated up to 32 Dpa |
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118 | (6) |
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The Influence of Helium and ODS on the Irradiation-Induced Hardening of Eurofer97 at 300°C |
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124 | (6) |
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SECTION II MATERIALS TECHNOLOGY FOR NUCLEAR WASTE TREATMENT AND DISPOSAL |
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Advantages Hot Isostatically Pressed Ceramic and Glass-Ceramic Waste Forms Bring to the Immobilization of Challenging Intermediate- and High-Level Nuclear Wastes |
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130 | (6) |
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Synthesis and Properties of Reaction-Bonded SiC Ceramic with Embedded UO2 -TRISO Coated Particles |
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136 | (6) |
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New Actinide Waste Forms with Pyrochlore and Garnet Structures |
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142 | (6) |
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An Innovative Hybrid Process Involving Plasma in a Cold Crucible Melter Devoted to the Futur Intermediate Level Waste Treatment: The SHIVA Technology |
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148 | (10) |
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Development of New Waste Forms to Immobilize Iodine-129 Released from a Spent Fuel Reprocessing Plant |
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158 | (13) |
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Study of New Filters Properties for Cs-137 Vapour Capture at High Temperature |
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171 | (5) |
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Using the Vitrification Test Rig for Process Improvements on the Waste Vitrification Plants |
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176 | (7) |
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Cold Crucible Inductive Melting Technology --- Application to Vitrification and Ceramization of High Level and Actinide Wastes |
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183 | (11) |
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Lessons Learned from the Yucca Mountain and WIPP Projects |
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194 | (9) |
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| Keyword Index |
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203 | (2) |
| Author Index |
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205 | |
