5th FORUM ON NEW MATERIALS PART B

Erscheinungsjahr 2010
ISBN: 978-3-908158-40-0
Verlag: Trans Tech Publications

Sonstiges, Englisch, 212 Seiten, Format (B × H): 125 mm x 142 mm, Gewicht: 200 g

The 26 peer-reviewed papers collected here together offer a plenitude of up-to-date information on ?Materials Challenges for Future Nuclear Fission and Fusion Technologies?. The papers are conveniently arranged into MATERIALS CHALLENGES FOR FUTURE NUCLEAR FISSION AND FUSION TECHNOLOGIES, Low Activation Structural Materials for Nuclear Fusion Systems, Functional, Cladding and Fuel Materials for Nuclear Fission Reactors, Radiation Effects, MATERIALS TECHNOLOGY FOR NUCLEAR WASTE TREATMENT AND DISPOSAL.

Autoren/Hrsg.

Vincenzini, Pietro

Lin, Hua Tay

Fox, Kevin

Fachgebiete

• Technische Wissenschaften Maschinenbau | Werkstoffkunde Technische Mechanik | Werkstoffkunde Werkstoffkunde, Materialwissenschaft: Forschungsmethoden
• Wirtschaftswissenschaften Wirtschaftssektoren & Branchen Energie- & Versorgungswirtschaft Kernenergieindustrie
• Naturwissenschaften Physik Quantenphysik Kernphysik
• Technische Wissenschaften Energietechnik | Elektrotechnik Atomenergietechnik

Inhaltsverzeichnis

Design and Integration of ITER Divertor ComponentsTungsten as a Structural Divertor MaterialMicrostructural Control for Improving Properties of V-4Cr-4Ti AlloysSiC/SiC Composites Irradiation Behaviour in Fusion Reactor Environment ConditionsExperimental 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 ReactorUtilization of Hydride Materials in Nuclear ReactorsProgressive Development for Structural Integrity Quantification of Nuclear Grade Graphite in Very High Temperature Gas Cooled Reactor Core EnvironmentsMultiscale Modelling of the Influence of Damage on the Thermal Properties of Ceramic Matrix CompositesGeneral Corrosion Properties of Modified PNC1520 Austenitic Stainless Steel in Supercritical Water as a Fuel Cladding Candidate Material for Supercritical Water ReactorFrom High to Low Enriched Uranium Fuel in Research ReactorsSimulation and Modelling the Heterogeneous Effects of the Microstructure MOX Fuels on their Effective Properties in Nominal Pressure Water Reactor ConditionsFabrication of Fuel and Recycling of Minor Actinides in Fast ReactorsInfluence of the Microstructure on the U1-yAmyO2-x (y= 0.1; 0.15) Pellet Macroscopic SwellingGeometrical Aspects of Dislocation-Obstacle Interaction in IronQuantitative TEM Investigations on EUROFER 97 Irradiated up to 32 DpaThe Influence of Helium and ODS on the Irradiation-Induced Hardening of Eurofer97 at 300?CAdvantages Hot Isostatically Pressed Ceramic and Glass-Ceramic Waste Forms Bring to the Immobilization of Challenging Intermediate- and High-Level Nuclear WastesSynthesis and Properties of Reaction-Bonded SiC Ceramic with Embedded UO2 - TRISO Coated ParticlesNew Actinide Waste Forms with Pyrochlore and Garnet StructuresAn Innovative Hybrid Process Involving Plasma in a Cold Crucible Melter Devoted to the Futur Intermediate Level Waste Treatment: The SHIVA TechnologyDevelopment of New Waste Forms to Immobilize Iodine-129 Released from a Spent Fuel Reprocessing PlantStudy of New Filters Properties for Cs-137 Vapour Capture at High TemperatureUsing the Vitrification Test Rig for Process Improvements on the Waste Vitrification PlantsCold Crucible Inductive Melting Technology ? Application to Vitrification and Ceramization of High Level and Actinide WastesLessons Learned from the Yucca Mountain and WIPP Projects