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Nakamichi, Masaru; Kim, Jae-Hwan
Fusion Engineering and Design, 98-99, p.1838 - 1842, 2015/10
Times Cited Count：15 Percentile：77.56(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.
Tsuchiya, Kunihiko; Uchida, Munenori*; Kawamura, Hiroshi
Fusion Engineering and Design, 81(8-14), p.1057 - 1063, 2006/02
Times Cited Count：11 Percentile：60.27(Nuclear Science & Technology)no abstracts in English
Sato, Satoshi; Verzilov, Y. M.; Ochiai, Kentaro; Nakao, Makoto*; Wada, Masayuki*; Kubota, Naoyoshi; Kondo, Keitaro; Yamauchi, Michinori*; Nishitani, Takeo
Fusion Engineering and Design, 81(8-14), p.1183 - 1193, 2006/02
Times Cited Count：19 Percentile：77.5(Nuclear Science & Technology)no abstracts in English
Hasegawa, Akira*; Tsuchiya, Kunihiko; Ishitsuka, Etsuo
Nihon Genshiryoku Gakkai-Shi, 47(8), p.536 - 544, 2005/08
no abstracts in English
Yamauchi, Michinori*; Nishitani, Takeo; Nishio, Satoshi
Purazuma, Kaku Yugo Gakkai-Shi, 80(11), p.952 - 954, 2004/11
Considering the geometrical characteristics of tokamak reactors with low aspect ratio, a basic neutronics strategy was derived to construct the inboard structure mainly for neutron shielding and produce enough tritium in the outboard blanket. The designs for optimal inboard shield were surveyed and necessary thickness was estimated to make the neutron flux low enough on the super-conducting magnet. In addition, the outer blanket designs were studied to attain the tritium breeding ratio (TBR) large enough for a self-sustaining fusion reactor on the basis of the advanced fusion reactor materials.
Kawamura, Hiroshi; Takahashi, Heishichiro*; Yoshida, Naoaki*; Mishima, Yoshinao*; Ishida, Kiyohito*; Iwadachi, Takaharu*; Cardella, A.*; Van der Laan, J. G.*; Uchida, Munenori*; Munakata, Kenzo*; et al.
Journal of Nuclear Materials, 329-333(1), p.112 - 118, 2004/08
Times Cited Count：33 Percentile：87.58(Materials Science, Multidisciplinary)no abstracts in English
Munakata, Kenzo*; Kawamura, Hiroshi; Uchida, Munenori*
Journal of Nuclear Materials, 329-333(Part2), p.1357 - 1360, 2004/08
Times Cited Count：14 Percentile：63.95(Materials Science, Multidisciplinary)no abstracts in English
Munakata, Kenzo*; Kawamura, Hiroshi; Uchida, Munenori*
JAERI-Conf 2004-006, p.210 - 215, 2004/03
no abstracts in English
Onuma, Ikuo*; Kainuma, Ryosuke*; Uda, Minoru*; Iwadachi, Takaharu*; Uchida, Munenori*; Kawamura, Hiroshi; Ishida, Kiyohito*
JAERI-Conf 2004-006, p.172 - 183, 2004/03
no abstracts in English
Sato, Yoshiyuki*; Uchida, Munenori*; Kawamura, Hiroshi
JAERI-Conf 2004-006, p.203 - 209, 2004/03
no abstracts in English
TiShibayama, Tamaki*; Nakamichi, Masaru*; Uchida, Munenori*; Kawamura, Hiroshi; Kinoshita, Hiroshi*; Kiyanagi, Yoshiaki*; Takahashi, Heishichiro*; Nomura, Naoyuki*
JAERI-Conf 2004-006, p.216 - 219, 2004/03
no abstracts in English
Uchida, Munenori*; Uda, Minoru*; Iwadachi, Takaharu*; Nakamichi, Masaru; Kawamura, Hiroshi
Journal of Nuclear Materials, 329-333(Part2), p.1342 - 1346, 2004/00
Times Cited Count：5 Percentile：35.25(Materials Science, Multidisciplinary)In this paper, an elemental technology to fabricate beryllide rods by the vacuum casting was researched. Furnace material study to prevent the chemical reaction with beryllide and casting procedure study to cast durable ingot without any shrinkages and cracks were performed. From the results of the reactivity test of refractory material with BeTi, it was clear that the BeO crucible had less reactivity with melt and no contamination. From the results of casting tests with a MgO cylindrical mold in a vacuum chamber, it was revealed that the mold dimension was critical to minimize shrinkages and cracks. It was also found that the forced cooling by the MgO cylindrical sleeve with water-cooled copper mold on the bottom was efficient to improve the shrinkages and the cracks.
TiIwakiri, Hirotomo*; Yasunaga, Kazufumi*; Yoshida, Naoaki*; Uchida, Munenori*; Kawamura, Hiroshi
Journal of Nuclear Materials, 329-333(Part A), p.880 - 884, 2004/00
Times Cited Count：8 Percentile：48.81(Materials Science, Multidisciplinary)no abstracts in English
Department of JMTR, Oarai
JAERI-Review 2003-026, 163 Pages, 2003/09
JAERI-Review-2003-026.pdf:16.05MB
no abstracts in English
Yamada, Hirokazu*; Nagao, Yoshiharu; Kawamura, Hiroshi; Nakao, Makoto*; Uchida, Munenori*; Ito, Haruhiko
Fusion Engineering and Design, 69(1-4), p.269 - 273, 2003/09
Times Cited Count：14 Percentile：66.94(Nuclear Science & Technology)no abstracts in English
Ti and Li
TiO
Nakamichi, Masaru; Kawamura, Hiroshi; Uchida, Munenori*
Fusion Engineering and Design, 69(1-4), p.257 - 261, 2003/09
Times Cited Count：9 Percentile：49.89(Nuclear Science & Technology)no abstracts in English
TiUchida, Munenori*; Ishitsuka, Etsuo; Kawamura, Hiroshi
Fusion Engineering and Design, 69(1-4), p.499 - 503, 2003/09
Times Cited Count：26 Percentile：82.89(Nuclear Science & Technology)no abstracts in English
Uchida, Munenori*; Kawamura, Hiroshi; Uda, Minoru*; Ito, Yoshio*
Fusion Engineering and Design, 69(1-4), p.491 - 498, 2003/09
Times Cited Count：15 Percentile：69.06(Nuclear Science & Technology)no abstracts in English
Kawamura, Hiroshi; Ishitsuka, Etsuo; Tsuchiya, Kunihiko; Nakamichi, Masaru; Uchida, Munenori*; Yamada, Hirokazu*; Nakamura, Kazuyuki; Ito, Haruhiko; Nakazawa, Tetsuya; Takahashi, Heishichiro*; et al.
Nuclear Fusion, 43(8), p.675 - 680, 2003/08
Times Cited Count：28 Percentile：64.08(Physics, Fluids & Plasmas)no abstracts in English
TiUchida, Munenori*; Ishitsuka, Etsuo; Kawamura, Hiroshi
Journal of Nuclear Materials, 307-311(Part1), p.653 - 656, 2002/12
Times Cited Count：29 Percentile：84.88(Materials Science, Multidisciplinary)BeTi has high melting point and good chemical stability and is expected as the advanced material for the neutron multiplier of DEMO-Reactor that requires higher temperature than 600
C in a blanket. To evaluate the tritium inventory in the breeding blanket, tritium release experiment of the neutron irradiated BeTi irradiated with a total fast neutron fluence of about 4 x 10
n/cm
(E
1MeV) at 330, 400 and 500C, was carried out. It was clear that tritium could be released easier than beryllium, and the apparent diffusion coefficient of BeTi was about two orders larger than that of beryllium at 600
1100C. In addition to good tritium release property, the swelling calculated from the density change of the specimens up to 1100C in this test was smaller than that of beryllium.
