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Oshima, Takeshi; Yokoseki, Takashi; Murata, Koichi; Matsuda, Takuma; Mitomo, Satoshi; Abe, Hiroshi; Makino, Takahiro; Onoda, Shinobu; Hijikata, Yasuto*; Tanaka, Yuki*; et al.
Japanese Journal of Applied Physics, 55(1S), p.01AD01_1 - 01AD01_4, 2016/01
Times Cited Count：14 Percentile：54.92(Physics, Applied)Hijikata, Yasuto*; Mitomo, Satoshi*; Matsuda, Takuma*; Murata, Koichi*; Yokoseki, Takashi*; Makino, Takahiro; Takeyama, Akinori; Onoda, Shinobu; Okubo, Shuichi*; Tanaka, Yuki*; et al.
Proceedings of 11th International Workshop on Radiation Effects on Semiconductor Devices for Space Applications (RASEDA-11) (Internet), p.130 - 133, 2015/11
Takeyama, Akinori; Matsuda, Takuma; Yokoseki, Takashi; Mitomo, Satoshi; Murata, Koichi; Makino, Takahiro; Onoda, Shinobu; Tanaka, Yuki*; Kandori, Mikio*; Yoshie, Toru*; et al.
Proceedings of 11th International Workshop on Radiation Effects on Semiconductor Devices for Space Applications (RASEDA-11) (Internet), p.134 - 137, 2015/11
Yokoseki, Takashi; Abe, Hiroshi; Makino, Takahiro; Onoda, Shinobu; Tanaka, Yuki*; Kandori, Mikio*; Yoshie, Toru*; Hijikata, Yasuto*; Oshima, Takeshi
Materials Science Forum, 821-823, p.705 - 708, 2015/07
TiO
pebble bed under cyclic loadsTanigawa, Hisashi; Tanaka, Yuichiro*; Enoeda, Mikio
Journal of Nuclear Materials, 417(1-3), p.703 - 705, 2011/10
Times Cited Count：5 Percentile：38.65(Materials Science, Multidisciplinary)In the temperature range from room temperature to 973 K and the mechanical loading range from 0.1 MPa to 3 MPa, LiTiO pebble bed is successively loaded and the packing behaviour of the bed is observed. Deformation caused by the mechanical loadings is partly relaxed when the bed is heated without the load. After large numbers of thermal and mechanical loadings, the packing factor of the bed with the initial packing factor of 66.9% finally reaches about 68.5%. The progress of packing leads to production of a void region at the top of the pebble bed and it is important to obtain a high packing factor for the initial packing.
Akiba, Masato; Enoeda, Mikio; Tanaka, Satoru*
Fusion Engineering and Design, 85(10-12), p.1766 - 1771, 2010/12
Times Cited Count：16 Percentile：72.36(Nuclear Science & Technology)As the primary candidate of ITER Test Blanket Module (TBM) for the first day of ITER operation, development of Water Cooled Solid Breeder (WCSB) TBM has been performed toward the TBM milestones, which are necessary for acceptance of the TBM in ITER for testing from the first day of plasma operation. Regarding the liquid breeder blanket development, universities and NIFS are conducting the development. This paper overviews the recent achievements of the TBMs and DEMO blankets.
SiO pebble bedTanigawa, Hisashi; Tanaka, Yuichiro*; Enoeda, Mikio; Akiba, Masato
Journal of Nuclear Science and Technology, 46(6), p.553 - 556, 2009/06
Times Cited Count：6 Percentile：41.05(Nuclear Science & Technology)Effective thermal conductivity of a LiSiO pebble bed was measured by the hot wire method. The bare and the silica-coated Nichrome heaters were used as the hot wire. At 975 K, the effective thermal conductivity was not measured correctly by the bare hot wire. This is caused by that the electrical signal of the bare thermocouple is distorted due to electrical conductivity of LiSiO. Using the silica-coated hot wire, the effective thermal conductivity can be measured at temperatures ranging from room temperature to 975 K. The effect of the coating layer on the measured effective thermal conductivity was estimated to be small and corresponded to the experimental data. The hot wire method with silica-coating can be applied to the other ceramic breeder materials.
Ioki, Kimihiro; Elio, F.*; Barabash, V.*; Chuyanov, V.*; Rozov, V.*; Wang, X.*; Chen, J.*; Wang, L.*; Lorenzetto, P.*; Peacock, A.*; et al.
Fusion Engineering and Design, 82(15-24), p.1774 - 1780, 2007/10
Times Cited Count：13 Percentile：66.15(Nuclear Science & Technology)In December 2005, the new procurement allocation plan of the ITER components among the seven Parties was prepared. The need to qualify for procurement of the specific components was especially introduced in the document. The main features and milestones of the qualification program are described in "Procurement Plan" for each specific component. Due to the complicated features of FW procurement, the procurement document has to be developed precisely. To guarantee high quality of 1700 FW panels produced by 6 different Parties, a qualification program is essential. The qualification mock-up is 80 mm wide, 240 mm long and 81 mm thick with 3 beryllium tiles 10 mm thick. Heat load tests will be performed on the qualification mock-ups in 2007 in EU and USA facilities. The maximum design heat load on the ITER FW is 0.5 MW/m 
(steady state) 
30,000 shots. Mechanical tests of joints are also required using standardized methods. Only Parties which have satisfied the acceptance criteria of the qualification tests can proceed to the procurement stage of the ITER FW. Semi-prototypes (roughly 1000 mm 200 mm) are also requested before the ITER FW manufacturing.
Enoeda, Mikio; Akiba, Masato; Tanaka, Satoru*; Shimizu, Akihiko*; Hasegawa, Akira*; Konishi, Satoshi*; Kimura, Akihiko*; Koyama, Akira*; Sagara, Akio*; Muroga, Takeo*
Fusion Engineering and Design, 81(1-7), p.415 - 424, 2006/02
Times Cited Count：62 Percentile：96.4(Nuclear Science & Technology)no abstracts in English
Enoeda, Mikio; Akiba, Masato; Tanaka, Satoru*; Shimizu, Akihiko*; Hasegawa, Akira*; Konishi, Satoshi*; Kimura, Akihiko*; Koyama, Akira*; Sagara, Akio*; Muroga, Takeo*
Fusion Science and Technology, 47(4), p.1023 - 1030, 2005/05
Times Cited Count：4 Percentile：30.51(Nuclear Science & Technology)The Fusion Council of Japan has established the long-term research and development program of the blanket in 1999. In the program, the solid breeder blanket was selected as the primary candidate blanket of the fusion power demonstration plant in Japan. In the program, Japan Atomic Energy Research Institute (JAERI) has been nominated as a leading institute of the development of solid breeder blankets, in collaboration with universities, for the near term power demonstration plant, while, universities including National Institute for Fusion Science (NIFS) are assigned mainly to develop advanced blankets for longer term power plant development. In the long term research and development program, ITER blanket module testing is identified as the most important milestone, by which integrity of candidate blanket concepts and structures are evaluated. In Japan, universities, NIFS and JAERI cover a variety of types of blanket development. This paper presents a plan and strategy for ITER blanket module testing in Japan.
Co
O
:Magnetic circular X-ray dichroism studyOkamoto, Jun*; Mamiya, Kazutoshi*; Fujimori, Shinichi; Okane, Tetsuo; Saito, Yuji; Muramatsu, Yasuji*; Yoshii, Kenji; Fujimori, Atsushi*; Tanaka, Arata*; Abbate, M.*; et al.
Physical Review B, 71(10), p.104401_1 - 104401_5, 2005/03
Times Cited Count：20 Percentile：61.94(Materials Science, Multidisciplinary)The antiferromagnetic-to-ferromagnetic transition in SrFeCoO (
0.15) induced by Co doping has been studied by magnetic circular X-ray dichroism. The orbital and spin magnetic moments of the Fe and Co 3
states under the magenetic field of 2 T are found to show different 
dependences: The spin polarization of Fe 3 gradually increases with Co concentration; On the other hand, a large spin polarization of Co 3 is induced already in the antiferromagnetic phase, indicating that the Co moment is nearly fully alligned already in the antiferromagnetic phase. This suggests that the alignment of the Fe magnetic moment in SrFeCoO is induced by interaction with doped Co magnetic moment. Possible formation of ferromagnetic Co rich region is discussed.
OTanigawa, Hisashi; Tanaka, Satoru*; Enoeda, Mikio; Akiba, Masato
Journal of Nuclear Materials, 329-333(2), p.1291 - 1294, 2004/08
Times Cited Count：4 Percentile：29.26(Materials Science, Multidisciplinary)In order to elucidate the interaction of hydrogen isotopes with irradiation defects, infrared absorption spectroscopy was conducted for a single crystal of LiO. Using FT-IR, O-D stretching vibration from the bulk LiO was observed under deutron irradiation. Under and after the irradiation, several peaks were observed in the O-D stretching vibration region and these peaks had different dependence on conditions of the irradiation. From the observed behaviour of the peaks, it was suggested that most of the irradiated deutron existed in LiO without O-D bonding because of interaction with the defects.
Kondo, Yasuhiro; Akikawa, Hisashi; Anami, Shozo*; Asano, Hiroyuki*; Fukui, Yuji*; Igarashi, Zenei*; Ikegami, Kiyoshi*; Ikegami, Masanori*; Ito, Takashi; Kawamura, Masato*; et al.
Proceedings of 1st Annual Meeting of Particle Accelerator Society of Japan and 29th Linear Accelerator Meeting in Japan, p.156 - 158, 2004/08
A commissioning of the J-PARC linac DTL1 is now under way at KEK. A 30mA H
beam was accelerated to 19.7-MeV, and 100% transmission was obtained with a 20-msec-pulse-width and 12.5-Hz-repetition beam. In this paper, present status of the DTL1 commissioning and preliminary results of the commissioning, such as emittance measurements, are presented.
Sato, Susumu; Tomisawa, Tetsuo; Hiroki, Fumio; Lee, S.*; Igarashi, Zenei*; Ikegami, Masanori*; Ueno, Akira; Kondo, Yasuhiro; Hasegawa, Kazuo; Toyama, Takeshi*; et al.
Proceedings of 1st Annual Meeting of Particle Accelerator Society of Japan and 29th Linear Accelerator Meeting in Japan, p.467 - 469, 2004/08
As a joint project of KEK and JAERI, a MW class of high intensity proton accelerator (J-PARC), consisting of Linac, 3 GeV-RCS, 50 GeV-MR, is under construction. For this accelerator, it is required to minimize the beam loss (typically, lower than0.1
1 W/m at the linac). To achieve the requirement, beam trajectory needs to be controlled with accuracy of some 100 
m. The first stage of the acceleration (up to 181 MeV during the first stage of construction) is done by linac. The beam position monitor (BPM) in the linac utilizes 4 stripline pickups (50 ohm) on the beam transportation chamber. In this paper, systematic calibration of the BPM is described.
Sato, Susumu; Igarashi, Zenei*; Lee, S.*; Tomisawa, Tetsuo; Hiroki, Fumio; Kishiro, Junichi; Ikegami, Masanori*; Kondo, Yasuhiro; Hasegawa, Kazuo; Ueno, Akira; et al.
Proceedings of 22nd International Linear Accelerator Conference (LINAC 2004), p.429 - 431, 2004/00
As a joint project of KEK and JAERI, a MW class of high intensity proton accelerator (J-PARC), consisting of Linac, 3 GeV-RCS, 50 GeV-MR, is under construction at Tokai, Japan. For this accelerator, it is required to minimize the beam loss (typically, lower than 0.11 W/m at the linac). To achieve the requirement, beam trajectory needs to be controlled with accuracy of some 100 micro-meter. The first stage of the acceleration (up to 181 MeV during the first stage of construction) is done by linac. The beam position monitor (BPM) in the linac utilizes 4 strip-line pickups (50 ohm) on the beam transportation chamber. In this paper, systematic calibration of the BPM is described.
tritium recovery experiments of blanket in-pile mockup with LiTiO pebble bed in JapanTsuchiya, Kunihiko; Nakamichi, Masaru; Nagao, Yoshiharu; Enoeda, Mikio; Osaki, Toshio*; Tanaka, Satoru*; Kawamura, Hiroshi
Journal of Nuclear Science and Technology, 38(11), p.996 - 1003, 2001/11
Times Cited Count：23 Percentile：82.42(Nuclear Science & Technology)no abstracts in English
Miura, H.*; Sato, Satoshi; Enoeda, Mikio; Kuroda, Toshimasa*; Takatsu, Hideyuki; Kawamura, Yoshinori; Tanaka, Satoru*
JAERI-Tech 97-051, 51 Pages, 1997/10
no abstracts in English
Enoeda, Mikio; Kawamura, Yoshinori; Okuno, Kenji; Tanaka, Kenichi*; Uetake, Mitsuru*; Nishikawa, Masabumi*
Fusion Technology, 28(3), p.591 - 596, 1995/10
no abstracts in English
Enoeda, Mikio; Kawamura, Yoshinori; Okuno, Kenji; Tanaka, Kenichi*; Uetake, Mitsuru*; Nishikawa, Masabumi*
Proceedings of 4th International Workshop on Ceramic Breeder Blanket Interface (CBBI-4), p.356 - 372, 1995/10
no abstracts in English
Enoeda, Mikio; Kawamura, Yoshinori; Okuno, Kenji; Nishikawa, Masabumi*; Tanaka, Kenichi*
Fusion Technology, 26(3), p.664 - 667, 1994/11
no abstracts in English
