5th FORUM ON NEW MATERIALS PART B

Erscheinungsjahr 2011
ISBN: 978-3-908158-56-1
Verlag: Trans Tech Publications

Buch, Englisch, 212 Seiten, Format (B × H): 170 mm x 240 mm, Gewicht: 600 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 Energietechnik | Elektrotechnik Atomenergietechnik
• Naturwissenschaften Physik Quantenphysik Kernphysik
• Wirtschaftswissenschaften Wirtschaftssektoren & Branchen Energie- & Versorgungswirtschaft Kernenergieindustrie
• Technische Wissenschaften Maschinenbau | Werkstoffkunde Technische Mechanik | Werkstoffkunde Werkstoffkunde, Materialwissenschaft: Forschungsmethoden

Inhaltsverzeichnis

Preface
Committees
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