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Ohara, Yoshihiro
JAEA-Review 2006-042, 240 Pages, 2007/02
JAEA Takasaki annual report 2005 describes research and development activities performed from April 1, 2005 to March 31, 2006 with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and those in a recent few years with electron/-ray irradiation facilities (an electron accelerator and three Co -ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: (1) nuclear and energy engineering, (2) environmental conservation and resource security, (3) biotechnology and medical application, (4) advanced materials, analysis and novel technology. This annual report contains 182 reports consisting of 174 research papers and 8 status reports on operation/maintenance of above irradiation facilities, and a list of publications, related press-releases, TV programs, patents, and the type of research collaborations as Appendices.
Kasahara, Mikio*; Ma, C.-J.*; Okumura, Motonori*; Kojima, Takuji; Hakoda, Teruyuki; Taguchi, Mitsumasa; Sakai, Takuro; Ohara, Yoshihiro
JAEA-Review 2005-001, TIARA Annual Report 2004, p.293 - 295, 2006/01
Artificial cloud generation experiment was performed using a huge vertical pit located in Kamaishi iron-copper mine to investigate the characteristics of cloud. The physical and chemical properties of individual cloud droplets were examined by microscopic analysis at Kyoto university and micro-PIXE analysis at TIARA. The process of growth of cloud was clarified based on the result on droplet size, its distribution, droplet number concentration, and the change in distribution of chlorine in droplet as the function of size.
Yokota, Wataru; Ohara, Yoshihiro; Arakawa, Kazuo
Proceedings of 36th ICFA Advanced Beam Dynamics Workshop (NANOBEAM 2005) (CD-ROM), 6 Pages, 2005/10
no abstracts in English
Kasahara, Mikio*; Ma, C.-J.*; Okumura, Motonori*; Kojima, Takuji; Hakoda, Teruyuki; Taguchi, Mitsumasa; Sakai, Takuro; Ohara, Yoshihiro
JAERI-Review 2004-025, TIARA Annual Report 2003, p.256 - 258, 2004/11
As the source of Asian dust particles, the sands at four different desert areas in China were to be the target of bulk and single analyses by means of PIXE and micro-PIXE analyses, respectively. The physical properties of desert sands like morphology, color, and size were basically determined. Also the chemical characteristics of bulk sands of each desert were specified as the relative elemental mass. The elemental maps and spectra for individual sands allow us to understand the nature of individual sands. Consequently, the physicochemical properties of desert sands obtained from this study can be helpful to understand what kinds of man-made pollutants and sea-salts are incorporated into natural Asian dust particles.
Kuriyama, Masaaki; Akino, Noboru; Ebisawa, Noboru; Grisham, L. R.*; Honda, Atsushi; Ito, Takao; Kawai, Mikito; Kazawa, Minoru; Mogaki, Kazuhiko; Ohara, Yoshihiro; et al.
Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.410 - 423, 2002/09
Times Cited Count:49 Percentile:93.19(Nuclear Science & Technology)no abstracts in English
Kakuta, Toshiya*; Hirata, Shingo*; Mori, Seiji*; Konishi, Satoshi; Kawamura, Yoshinori; Nishi, Masataka; Ohara, Yoshihiro
Fusion Science and Technology, 41(3), p.1069 - 1073, 2002/05
Research-and-development of the supercritical water-cooled prototype fusion reactor which has cost competitiveness has been performed in Japan Atomic Energy Research Institute (JAERI). It is necessary to establish immediately the design concept of the blanket tritium recovery system which collects tritium continuously and safely from the supercritical water-cooled blanket because fuel self-sufficiency is inevitable in the prototype reactor. The candidate systems are; 1) batch-processing cryogenic molecular sheave bed recovery system with cryogenic temperature operation, 2) continuous processing Pd membrane penetration recovery system with high vacuum operation. In the present study, however, the third candidate system, the hydrogen pump system with protonic conductors, was investigated. As a result of the study, it was made clear that the system with minimized energy consumption and minimized accidental tritium release could be realized by using the hydrogen pump for the blanket tritium recovery system of the prototype fusion reactor.
Enoeda, Mikio; Ohara, Yoshihiro; Akiba, Masato; Sato, Satoshi; Hatano, Toshihisa; Kosaku, Yasuo; Kuroda, Toshimasa*; Kikuchi, Shigeto*; Yanagi, Yoshihiko*; Konishi, Satoshi; et al.
JAERI-Tech 2001-078, 120 Pages, 2001/12
This report is a summary of the design works, which was discussed in the design workshop held in 2000 for the demonstration (DEMO) blanket aimed to strengthen the commercial competitiveness and technical feasibility simultaneously. The DEMO blanket must supply the feasibility and experience of the total design of the power plant and the materials. This conceptual design study was performed to determine the updated strategy and goal of the R&D of the DEMO blanket which applies the supercritical water cooling proposed in A-SSTR, taking into account the recent progress of the plasma research and reactor engineering technology.
Sato, Satoshi; Enoeda, Mikio; Kuroda, Toshimasa*; Ohara, Yoshihiro; Mori, Kensuke*; Cardella, A.*
Fusion Engineering and Design, 58-59(1-4), p.749 - 754, 2001/11
Times Cited Count:4 Percentile:33.42(Nuclear Science & Technology)no abstracts in English
Enoeda, Mikio; Kuroda, Toshimasa*; Moriyama, Koichi*; Ohara, Yoshihiro
Journal of Nuclear Science and Technology, 38(11), p.921 - 929, 2001/11
Times Cited Count:2 Percentile:19.67(Nuclear Science & Technology)Test module testing in ITER is one of the most important mile-stone for development of the DEMO blanket. In the design of test modules in ITER, it is very important to show that test modules do not cause additional safety concern to ITER. This work has been performed for the evaluation of the substantial safety of Test Module of Water Cooled Solid Blanket, which is the current candidate blanket for the DEMO blanket in Japan. Major issues of the evaluation were establishment of post accident cooling in TM, hydrogen gas generation by Be-steam reaction, and pressure increase and spilled water amount by Loss of Coolant Accident (LOCA) event. The evaluation was performed to derive the upper bound of consequences in significant events, of which scenario can be assumed by the similarity of the safety analysis of Shielding Blanket.
Yanagi, Yoshihiko*; Sato, Satoshi; Enoeda, Mikio; Hatano, Toshihisa; Kikuchi, Shigeto*; Kuroda, Toshimasa*; Kosaku, Yasuo; Ohara, Yoshihiro
Journal of Nuclear Science and Technology, 38(11), p.1014 - 1018, 2001/11
Times Cited Count:24 Percentile:83.32(Nuclear Science & Technology)no abstracts in English
Seki, Masahiro; Hishinuma, Akimichi; Kurihara, Kenichi; Akiba, Masato; Abe, Tetsuya; Ishitsuka, Etsuo; Imai, Tsuyoshi; Enoeda, Mikio; Ohira, Shigeru; Okumura, Yoshikazu; et al.
Kaku Yugoro Kogaku Gairon; Mirai Enerugi Eno Chosen, 246 Pages, 2001/09
no abstracts in English
Enoeda, Mikio; Ohara, Yoshihiro; Roux, N.*; Ying, A.*; Pizza, J.*; Malang, J.*
Fusion Technology, 39(No.2 Part.2), p.612 - 616, 2001/03
no abstracts in English
Seki, Masahiro; Tsuji, Hiroshi; Ohara, Yoshihiro; Akiba, Masato; Okumura, Yoshikazu; Imai, Tsuyoshi; Nishi, Masataka; Koizumi, Koichi; Takeuchi, Hiroshi
Fusion Technology, 39(2-Part.2), p.367 - 373, 2001/03
no abstracts in English
Seki, Masahiro; Ohara, Yoshihiro; Tada, Eisuke; Akiba, Masato
Fusion Engineering and Design, 51-52, p.941 - 948, 2000/11
Times Cited Count:1 Percentile:12.1(Nuclear Science & Technology)no abstracts in English
Nishio, Satoshi; Ushigusa, Kenkichi; Ueda, Shuzo; Polevoi, A.*; Kurita, Genichi; Tobita, Kenji; Kurihara, Ryoichi; Hu, G.; Okada, Hidetoshi*; Murakami, Yoshiki*; et al.
JAERI-Research 2000-029, 105 Pages, 2000/10
no abstracts in English
Kikuchi, Shigeto*; Enoeda, Mikio; Ohara, Yoshihiro
Proceedings of the 9th International Workshop on Ceramic Breeder Blanket Interactions (CBBI-9), p.191 - 198, 2000/09
no abstracts in English
Sato, Satoshi; Furuya, Kazuyuki; Hatano, Toshihisa; Kuroda, Toshimasa*; Enoeda, Mikio; Takatsu, Hideyuki; Ohara, Yoshihiro
JAERI-Tech 2000-042, 121 Pages, 2000/07
no abstracts in English
Watanabe, Kazuhiro; Akiba, Masato; Hatano, Toshihisa; Imai, Tsuyoshi; Kuriyama, Masaaki; Ohara, Yoshihiro; Okumura, Yoshikazu; Tsuji, Hiroshi
Proceedings of 10th International Toki Conference on Plasma Physics and Controlled Nuclear Fusion (ITC-10), p.525 - 529, 2000/00
no abstracts in English
Fujiwara, Yukio; Inoue, Takashi; Miyamoto, Kenji; Miyamoto, Naoki*; Ohara, Yoshihiro; Okumura, Yoshikazu; Watanabe, Kazuhiro
JAERI-Research 99-071, p.33 - 0, 1999/12
no abstracts in English
Matsuda, Shinzaburo; Tsuji, Hiroshi; Koizumi, Koichi; Akiba, Masato; Ohara, Yoshihiro; Shibanuma, Kiyoshi; Nishi, Masataka; Abe, Tetsuya; Okumura, Yoshikazu; Imai, Tsuyoshi; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 75(Suppl.), p.1 - 96, 1999/05
no abstracts in English