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Kim, Jae-Hwan; Nakamichi, Masaru
Fusion Engineering and Design, 109-111(Part B), p.1764 - 1768, 2016/11
Times Cited Count:13 Percentile:76.68(Nuclear Science & Technology)Kim, Jae-Hwan; Nakamichi, Masaru
JAEA-Review 2015-044, 260 Pages, 2016/03
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.
Kim, Jae-Hwan; Nakamichi, Masaru
Fusion Engineering and Design, 100, p.614 - 618, 2015/11
Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)Nakamichi, Masaru; Kim, Jae-Hwan
Fusion Engineering and Design, 98-99, p.1838 - 1842, 2015/10
Times Cited Count:15 Percentile:77.17(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:7 Percentile:50.83(Nuclear Science & Technology)Kim, Jae-Hwan; Nakamichi, Masaru
Journal of Alloys and Compounds, 640, p.285 - 289, 2015/08
Times Cited Count:3 Percentile:17.70(Chemistry, Physical)Kim, Jae-Hwan; Nakamichi, Masaru
Journal of Alloys and Compounds, 638, p.277 - 281, 2015/07
Times Cited Count:5 Percentile:27.23(Chemistry, Physical)Kim, Jae-Hwan; Nakamichi, Masaru
Journal of Nuclear Materials, 455(1-3), p.26 - 30, 2014/12
Times Cited Count:11 Percentile:64.16(Materials Science, Multidisciplinary)Nakamichi, Masaru; Kim, Jae-Hwan
Fusion Engineering and Design, 89(7-8), p.1304 - 1308, 2014/10
Times Cited Count:17 Percentile:78.02(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:21 Percentile:83.69(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.
Kim, Jae-Hwan; Nakamichi, Masaru
Fusion Engineering and Design, 89(7-8), p.1440 - 1443, 2014/10
Times Cited Count:7 Percentile:48.01(Nuclear Science & Technology)Kim, Jae-Hwan; Nakamichi, Masaru
Journal of Nuclear Materials, 453(1-3), p.22 - 26, 2014/10
Times Cited Count:18 Percentile:79.80(Materials Science, Multidisciplinary)Nakamichi, Masaru; Kim, Jae-Hwan
Fusion Science and Technology, 66, p.157 - 162, 2014/08
Times Cited Count:1 Percentile:8.75(Nuclear Science & Technology)Kim, Jae-Hwan; Nakamichi, Masaru
Journal of Alloys and Compounds, 585, p.63 - 68, 2014/02
Times Cited Count:14 Percentile:55.09(Chemistry, Physical)Kim, Jae-Hwan; Nakamichi, Masaru
Journal of Alloys and Compounds, 577, p.90 - 96, 2013/11
Times Cited Count:10 Percentile:48.14(Chemistry, Physical)Nakamichi, Masaru; Kim, Jae-Hwan; Munakata, Kenzo*; Shibayama, Tamaki*; Miyamoto, Mitsutaka*
Journal of Nuclear Materials, 442(1-3), p.S465 - S471, 2013/11
Times Cited Count:11 Percentile:63.81(Materials Science, Multidisciplinary)Kim, Jae-Hwan; Nakamichi, Masaru
Journal of Nuclear Materials, 442(1-3), p.S461 - S464, 2013/11
Times Cited Count:17 Percentile:77.87(Materials Science, Multidisciplinary)Kim, Jae-Hwan; Nakamichi, Masaru
Fusion Engineering and Design, 88(9-10), p.2215 - 2218, 2013/10
Times Cited Count:7 Percentile:48.84(Nuclear Science & Technology)Nakamichi, Masaru; Kim, Jae-Hwan; Yonehara, Kazuo
Fusion Engineering and Design, 88(6-8), p.611 - 615, 2013/10
Times Cited Count:35 Percentile:92.80(Nuclear Science & Technology)Advanced neutron multipliers with lower swelling and higher stability at high temperature are desired in pebble-bed blankets, which would have a big impact on the design of a DEMO reactor, especially on the blanket operating temperature. Development of advanced neutron multipliers has been started by Japan and EU in the DEMO R&D as a part of the Broader Approach (BA) activities. Beryllium intermetallic compounds (beryllides) such as BeTi are one of the most promising advanced neutron multipliers. In order to fabricate the beryllide pebbles, beryllide with shapes of block and/or rod is necessary when a melting granulation process is applied such as a rotating electrode method. However, beryllide is too brittle for the fabrication of blocks or rods by these methods. A plasma sintering method has been proposed as new technique which uses a non conventional consolidation process, because this method is simple, and is easy to control. It was clarified that the beryllide could be simultaneously synthesized and jointed by the plasma sintering method in the insert material region between two beryllide blocks, with no variation of the phase and hardness. Beryllide rod of BeTi with 10 mm in diameter and 60 mm in length has been successfully fabricated by the plasma sintering method. Using this plasma-sintered beryllide rod, prototype pebble of beryllide was performed by a rotating electrode method. The prototype pebbles of BeTi with 1 mm in average diameter were successfully fabricated. The present paper describes novel granulation process of beryllide using these methods including fabrication and granulation techniques.
Nakamichi, Masaru; Kim, Jae-Hwan
Journal of Nuclear Materials, 440(1-3), p.530 - 533, 2013/09
Times Cited Count:24 Percentile:86.72(Materials Science, Multidisciplinary)DEMO reactors require advanced neutron multiplier that has higher stability at high temperature. Beryllides such as BeTi are the most promising materials. A plasma sintering method has been proposed as new technique for rod fabrication. It was clarified that the beryllide could be simultaneously synthesized and jointed by the plasma sintering method. Using this plasma-sintered beryllide rod, prototype pebble of Be-Ti beryllide was fabricated by a rotating electrode method. The prototype pebbles with 1 mm in average diameter were successfully fabricated. However, compositional structure was changed by re-melting. These Be and BeTi phases in addition to BeTi phase were separated in the prototype pebble. From the result of annealing treatment of prototype pebble, prototype pebble phase was becoming single phase of BeTi by annealing above 1473K.