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Abstract: A successful example of high-Cr oxide dispersion strengthened (ODS) steels development is introduced with showing key technologies to overcome the issues to meet material requirements for next generation nuclear systems as well as fusion blanket systems. Corrosion issue requires Cr concentration more than 14wt.%, but aging embrittlement issue requires it less than 16wt.%. An addition of 4wt.%Al is effective to improve corrosion resistance of 16wt.%Cr-ODS steel in supercritical water (SCW) and lead–bismuth eutectics (LBE), while it is detrimental to high-temperature strength. An addition of small amount of Zr or Hf results in a significant increase in creep strength at 973K in Al-added ODS steels. Feasibility of high-Cr ODS steel without Al addition is assessed for fusion application in terms of corrosion resistance in SCW. [Copyright &y& Elsevier]

Abstract: About one thousands of small size specimens will be irradiated in the High Flux Test Module (HFTM) with a limited irradiation volume of 0.5l in the International Fusion Materials Irradiation Facility (IFMIF). It is necessary to verify that the experimental data of these small specimens mechanical characterization can be safely extrapolated to standard specimen data, enabling a sound dimensioning of DEMO reactor. The program of small specimen test technique (SSTT) in IFMIF/EVEDA (Engineering Validation and Engineering Design Activity) phase for fatigue, fracture toughness and crack growth measurement is summarized, and recent progress and some analysis of the experiments for small size specimens have been shown. [Copyright &y& Elsevier]

Abstract: SiCf/SiC composites are candidate structural and functional materials for fusion blankets, attractive for their potential application for higher temperature liquid metal blankets compared to the range possible for metallic materials. However, the experimental data on the long term compatibility of SiCf/SiC composites with high temperature liquid metal is inadequate. To acquire parametric data on the compatibility of NITE SiCf/SiC composites with a high temperature liquid metal stream, the corrosion behavior was examined in liquid Pb–Li using a rotating disk apparatus. The materials used in this study were exposed to relative flow velocity of ∼10–37cm/s at 900°C for 1000h. Oxidation layers were detected on the matrix and fiber near the surface exposed to liquid Pb–Li at 900°C for 1000h. Additional results for shorter exposure times and relationship to flow velocity are discussed. [Copyright &y& Elsevier]

Abstract: Breeding blankets are the most important components in DEMO. The DEMO blanket has to withstand high neutron flux typically 15–30 dpa/year under continuous operation. Therefore integrated and effective development of blanket structural materials and breeding/multiplying materials is essential in the blanket development for DEMO. In parallel to the ITER program, broader approach (BA) activities are initiated by EU and Japan. Based on the common interest of each party towards DEMO, R&D on reduced activation ferritic martensitic (RAFM) steels as a DEMO blanket structural material, SiCf/SiC composites which have potential for use in DEMO blankets, advanced tritium breeders and neutron multiplier for DEMO blankets, and tritium technologies including tritium behavior studies in advanced materials for DEMO blanket applications will be carried out as a part of the BA activities. [Copyright &y& Elsevier]