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Nishitani, Takeo; Tanigawa, Hiroyasu; Yamanishi, Toshihiko; Clement Lorenzo, S.*; Baluc, N.*; Hayashi, Kimio; Nakajima, Noriyoshi*; Kimura, Haruyuki; Sugimoto, Masayoshi; Heidinger, R.*; et al.
Fusion Science and Technology, 62(1), p.210 - 218, 2012/07
Times Cited Count：3 Percentile：23.90(Nuclear Science & Technology)Recent progress in the material related researches and the IFMIF/EVEDA project, which are carried out under the Broader Approach (BA) framework, is reported. In the International Fusion Energy Research Center (IFERC) project of BA, the R&D building was completed March 2010 at the Rokkasho BA site. R&Ds on reduced activation ferritic/ martensitic (RAFM) steels as structural material, SiC/SiC composites as a flow channel insert material and/or alternative structural material, advanced tritium breeders and neutron multipliers, and tritium technology relevant to the DEMO operational condition are progressed in Japan and EU. In the IFMIF/EVEDA project, the fabrication of the injector for the IFMIF prototype accelerator was completed at the CEA Saclay, and the first proton beam was obtained in May, 2011. The IFMIF lithium target test loop was completed in March 2011, and a lithium flow of 5 m/s was obtained.
Nishitani, Takeo; Tanigawa, Hiroyasu; Nozawa, Takashi; Jitsukawa, Shiro; Nakamichi, Masaru; Hoshino, Tsuyoshi; Yamanishi, Toshihiko; Baluc, N.*; M
slang, A.*; Lindou, R.*; et al.
Journal of Nuclear Materials, 417(1-3), p.1331 - 1335, 2011/10
Times Cited Count：14 Percentile：70.13(Materials Science, Multidisciplinary)As a part of the Broader Approach (BA) activities, the research and development on blanket related materials and tritium technology have been initiated toward DEMO by Japan and EU. Recently, those five R&D items have progressed substantially in Japan and EU. As a preparatory work aiming at the RAFM steel muss-production development, a 5-ton heat of RAFM steel (F82H) was procured with the Electro Slag Re-melting as a secondary melting. The result of the double notch tensile test method for the NITE-SiC
/SiC specimen indicated notch insensitivity and very minor size effect on proportional limit tensile stress and fracture strength. For the fabrication technology development of beryllide neutron multiplayer pebbles, Be- Ti inter-metallic pebbles have been sintered directly from the mixed powder of Be and Ti in Japan.
Ozeki, Takahisa; Clement Lorenzo, S.*; Nakajima, Noriyoshi*
no journal, ,
no abstracts in English
Ozeki, Takahisa; Clement Lorenzo, S.*; Nakajima, Noriyoshi*
no journal, ,
Yamanishi, Toshihiko; Nishitani, Takeo; Tanigawa, Hiroyasu; Nozawa, Takashi; Nakamichi, Masaru; Hoshino, Tsuyoshi; Hayashi, Kimio; Araki, Masanori; Hino, Tomoaki*; Clement Lorenzo, S.*
no journal, ,
As a part of the Broader Approach (BA) program, R&D on DEMO blanket related materials and tritium technology has been started in 2007 by both the EU and Japan. In accordance with the common interest of the EU and Japan, the followings subjects have been applied: reduced activation ferritic martensitic steels; silicon carbide composites: advanced tritium breeders and neutron multiplier; and tritium. These R&D studies are mainly carried out in Rokkasho site in Japan. Hence, we defined the period of 2007 to 2009 as Phase 1, and have carried out the design and fabrication of the equipment at Rokkasho. Activities for the licensing of the equipment for tritium and beryllium handling have also been carried out. The equipment is the first and quite unique facility in Japan, where tritium, 
and 
RI species, and beryllium can simultaneously be used. It has also the first challenge in Japan that researchers in various fields of blanket join R&D program at a facility.
Hayashi, Kimio; Nakajima, Noriyoshi*; Clement Lorenzo, S.*; Baluc, N.*; Nishitani, Takeo; Yamanishi, Toshihiko; Morono, A.*; Hernandez, T.*; Moriani, A.*; Tosti, S.*; et al.
no journal, ,
The DEMO R&D activities are intended to support the design activities of fusion demonstration reactor (DEMO) in the Broader Approach (BA). Recent progress in the DEMO R&D activities, particularly the status and plan for EU/JA collaboration activities, is presented in this conference. Equipment for investigation of the erosion /corrosion behavior of SiC/SiC composites in Pb-
Li is under fabrication for installation and experiments at the Rokkasho site. Irradiation of reduced activation ferritic /martensitic steels (EUROFER and F82H) in a Belgian reactor, BR2, is being prepared. Exchange of RAFM, neutron multiplier and tritium breeder samples between EU and JA is planned for collaborative characterization. Thus, the R&D activities are being upgraded.
