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C&SiC Composites in Extremat IP
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Heat Sink Materials for the Plasma-facing Components of Fusion Devices
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Silicon Carbide Reinforced Copper as a Heat Sink Material for Future Fusion Reactors
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Effect of Plastic Instability on Ductile Crack Resistance Behaviour of 9Cr-ferritic-martensitic Steels
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Fracture Toughness Vis-a-Vis the Master Curve for Some Advanced Reactor Pressure Vessel and Structural Steels
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Alternative Fabrication Method of U Polycrystalline Foils for Mo-99 Irradiation Target
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Transmutation, Sigma Phase Formation and Neutron Embrittlement in Candidate High-Z Plasma-facing Fusion Materials
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Behaviour of Reversible Hydrogen Getters under the Pulsed Plasma Heat Loads
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On Possible Mechanism of Copper Precipitate Clustering in Model FeCu Alloys under Cascade-Damage Irradiation
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Laser Pyrolysis Growth of ZrC, TiC, and SiC Nanopowders for Nanostructured Ceramics Elaboration
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Plasma Surface Interaction Characterize of New Type Multi-elements Doped Carbon-Base Materials
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Effect of the Composition on the Irradiation Damage Accumulation in Fe-Cr Model Alloys
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Influence of W and Re Interlayers on the Interface between SiC Fibers and 9Cr Steel Matrix
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ODS-Eurofer - A Reduced Activation Ferritic Martensitic (RAFM) ODS-steel for Application in Advanced Blanket Concepts
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Development and Testing of High Heat Flux Components for ITER
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Development of Nano-Particle-Strengthened Ferritic/Martensitic Steel
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Testing of Carbon Materials for Fusion Applications on Linear Plasma Trap GOL-3
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Irradiation Behaviour of Three Candidate Structural Materials for ADS Systems: EM10, T91 And HT9 (Ferritic/Martensitic Steels)
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Material Issues for ADS: MYRRHA-Project
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Beamline Investigations on Advanced VHTR Materials
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Composites for Nuclear Structural Applications
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Radiation Resistant Materials
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ExtreMat is funded within the Sixth Framework
Programme of the European Community.
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