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Nakamichi, Masaru; Kim, Jae-Hwan; Miyamoto, Mitsutaka*
Nuclear Materials and Energy (Internet), 9, p.55 - 58, 2016/12
Times Cited Count：23 Percentile：86.30(Nuclear Science & Technology)Kim, Jae-Hwan; Nakamichi, Masaru
Fusion Engineering and Design, 109-111(Part B), p.1764 - 1768, 2016/11
Times Cited Count：16 Percentile：76.97(Nuclear Science & Technology)Kawamura, Yoshinori; Tanigawa, Hisashi; Hirose, Takanori; Enoeda, Mikio; Sato, Satoshi; Ochiai, Kentaro; Konno, Chikara; Edao, Yuki; Hayashi, Takumi; Hoshino, Tsuyoshi; et al.
Fusion Engineering and Design, 109-111(Part B), p.1637 - 1643, 2016/11
Times Cited Count：28 Percentile：90.18(Nuclear Science & Technology)The development of a Water Cooled Ceramic Breeder (WCCB) Test Blanket Module (TBM) is being performed as one of the most important steps toward DEMO blanket in Japan. For the TBM testing and development of DEMO blanket, R&D has been performed on the module fabrication technology, breeder and multiplier pebble fabrication technology, tritium production rate evaluation, as well as structural design activities. This paper provides an overview of the recent achievements of the development of the WCCB Blanket in Japan.
Nakamichi, Masaru; Kim, Jae-Hwan; Ochiai, Kentaro
Fusion Engineering and Design, 109-111(Part B), p.1719 - 1723, 2016/11
Times Cited Count：14 Percentile：72.93(Nuclear Science & Technology)Kim, Jae-Hwan; Nakamichi, Masaru
JAEA-Review 2015-044, 260 Pages, 2016/03
JAEA-Review-2015-044.pdf:121.42MB
The 12th International Workshop on Beryllium Technology (BeWS-12) was held on 10-11 September at the International Convention Center Jeju (ICCJEJU) in Jeju Island, Korea within a framework created by the International Energy Agency (IEA) Energy Technology Initiative on Fusion Materials. This workshop has been holding every 2 years from 1993. The objective of this workshop is to disseminate results of research and technology development in areas relevant to beryllium utilization in fusion nuclear power systems. In this workshop, a lot of researchers and technicians engaged in R&D on beryllium related materials and fusion engineering attended and discussed. This JAEA-Conf has been compiled the manuscripts and the presentation files in the BeWS-12.
Ti
intermetallic compoundsKim, Jae-Hwan; Iwakiri, Hirotomo*; Furugen, Tatsuaki*; Nakamichi, Masaru
Fusion Engineering and Design, 102, p.44 - 49, 2016/01
Times Cited Count：7 Percentile：43.06(Nuclear Science & Technology)Kim, Jae-Hwan; Nakamichi, Masaru
Fusion Engineering and Design, 100, p.614 - 618, 2015/11
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)Nakamichi, Masaru; Kim, Jae-Hwan
Fusion Engineering and Design, 98-99, p.1838 - 1842, 2015/10
Times Cited Count：17 Percentile：76.04(Nuclear Science & Technology)Advanced neutron multipliers with high stability at high temperatures are desired for the pebble bed blankets of DEMO reactors. Beryllium intermetallic compounds (beryllides) are the most promising material for this purpose. To fabricate the beryllide pebbles, a new granulation process has been established that combines a plasma sintering method for beryllide synthesis and a rotating electrode method using a plasma-sintered electrode for granulation. In granulation examinations, prototypic pebbles 1 mm in diameter of Be-V beryllide as well as Be-Ti beryllide were successfully fabricated. This study performed not only granulation of binary beryllides but also its characterization of the hydrogen generation reaction with water vapor compared with those of pure Be pebbles.
Kim, Jae-Hwan; Nakamichi, Masaru
Fusion Engineering and Design, 98-99, p.1812 - 1816, 2015/10
Times Cited Count：9 Percentile：54.29(Nuclear Science & Technology)Kim, Jae-Hwan; Nakamichi, Masaru
Journal of Alloys and Compounds, 640, p.285 - 289, 2015/08
Times Cited Count：4 Percentile：19.85(Chemistry, Physical)Kim, Jae-Hwan; Nakamichi, Masaru
Journal of Alloys and Compounds, 638, p.277 - 281, 2015/07
Times Cited Count：7 Percentile：31.66(Chemistry, Physical)Kim, Jae-Hwan; Nakamichi, Masaru
Journal of Nuclear Materials, 455(1-3), p.26 - 30, 2014/12
Times Cited Count：14 Percentile：67.44(Materials Science, Multidisciplinary)Kim, Jae-Hwan; Nakamichi, Masaru
Fusion Engineering and Design, 89(7-8), p.1440 - 1443, 2014/10
Times Cited Count：8 Percentile：48.30(Nuclear Science & Technology)Nakamichi, Masaru; Kim, Jae-Hwan
Fusion Engineering and Design, 89(7-8), p.1304 - 1308, 2014/10
Times Cited Count：18 Percentile：73.70(Nuclear Science & Technology)Enoeda, Mikio; Tanigawa, Hisashi; Hirose, Takanori; Nakajima, Motoki; Sato, Satoshi; Ochiai, Kentaro; Konno, Chikara; Kawamura, Yoshinori; Hayashi, Takumi; Yamanishi, Toshihiko; et al.
Fusion Engineering and Design, 89(7-8), p.1131 - 1136, 2014/10
Times Cited Count：22 Percentile：81.23(Nuclear Science & Technology)The development of a Water Cooled Ceramic Breeder (WCCB) Test Blanket Module (TBM) is being performed as one of the most important steps toward DEMO blanket in Japan. Regarding the fabrication technology development using F82H, the fabrication of a real scale mockup of the back wall of TBM was completed. Also the assembling of the complete box structure of the TBM mockup and planning of the pressurization testing was studied. The development of advanced breeder and multiplier pebbles for higher chemical stability was performed for future DEMO blanket application. From the view point of TBM test result evaluation and DEMO blanket performance design, the development of the blanket tritium simulation technology, investigation of the TBM neutronics measurement technology and the evaluation of tritium production and recovery test using D-T neutron in the Fusion Neutronics Source (FNS) facility has been performed.
Nishitani, Takeo; Yamanishi, Toshihiko; Tanigawa, Hiroyasu; Nakamichi, Masaru; Nozawa, Takashi; Hoshino, Tsuyoshi; Ochiai, Kentaro
Fusion Engineering and Design, 89(7-8), p.1699 - 1703, 2014/10
Times Cited Count：13 Percentile：64.60(Nuclear Science & Technology)On the Broader Approach framework, R&D on the blanket related materials and technologies have been carried out between the EU and Japan. Those activities are implemented mainly at the Rokkasho BA site in Japan. In the R&D on SiC/SiC composites for an advanced blanket material, CVI-SiC/SiC composites have been obtained in high temperature vacuum environment up to 1000
C. As the R&D on the tritium technology, tritium retention of the fine-grained re-crystallized tungsten has been evaluated. On reduced activation ferritic/martensitic (RAFM) steels as the blanket structural material, 20-ton heat of the F82H RAFM steel has been successfully conducted by an electric arc furnace. Advanced neutron multiplier pebbles of beryllide have been fabricated with dedicated rotating electrode apparatus followed by annealing. Also advance tritium breeder has been fabricated by an emulsion method, where the grain size is confirmed by the SEM to be smaller than 5 
-m.
Kim, Jae-Hwan; Nakamichi, Masaru
Journal of Nuclear Materials, 453(1-3), p.22 - 26, 2014/10
Times Cited Count：19 Percentile：76.99(Materials Science, Multidisciplinary)Nakamichi, Masaru; Kim, Jae-Hwan
Fusion Science and Technology, 66, p.157 - 162, 2014/08
Times Cited Count：1 Percentile：7.63(Nuclear Science & Technology)Kim, Jae-Hwan; Nakamichi, Masaru
Journal of Alloys and Compounds, 585, p.63 - 68, 2014/02
Times Cited Count：16 Percentile：54.94(Chemistry, Physical)Kim, Jae-Hwan; Nakamichi, Masaru
Journal of Alloys and Compounds, 577, p.90 - 96, 2013/11
Times Cited Count：11 Percentile：46.96(Chemistry, Physical)