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(FT/1-1Ra) Recent Progress in Reduced Activation Ferritic Steels R&D in Japan

A. Kimura1), T. Sawai2), K. Shiba2), A. Hishinuma2), S. Jitsukawa2), S. Ukai3), A. Kohyama1)
 
1) Institute of Advanced Energy, Kyoto University, Uji, Kyoto, Japan
2) Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki, Japan
3) Japan Nuclear Cycle Development Institute, Oarai, Ibaraki, Japan

Abstract.  The Japanese RAFSs R&D road map toward DEMO is shown. Important steps include high-dose irradiation by fission reactors, such as HFIR in ORNL, irradiation tests by 14 MeV neutrons in IFMIF and application to ITER test blanket modules to provide an adequate database of RAFS for the design of DEMO. Current status of RAFS development is also introduced. The major properties of concern are well within our knowledge and process technologies are mostly ready for fusion application. The RAFSs are now certainly ready to proceed to the next stage. Material database is already in hand and further progress is anticipated for the design of ITER test blanket. Oxide Dispersion strengthening (ODS) steels are quite promising for high temperature operation of the blanket system with potential improvements in radiation resistance of mechanical performances and of corrosion.

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IAEA 2003