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JAEA Reports

JAEA Takasaki annual report 2005

Ohara, Yoshihiro

JAEA-Review 2006-042, 240 Pages, 2007/02

JAEA-Review-2006-042.pdf:31.02MB

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/$$gamma$$-ray irradiation facilities (an electron accelerator and three $$^{60}$$Co $$gamma$$-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.

Journal Articles

Micro-PIXE for the study of atmospheric environment

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.

Journal Articles

Microbeam system for heavy ions from cyclotron to irradiate living cells

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

Journal Articles

Micro-PIXE technique for the study of asian dust sources

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.

Journal Articles

Operation and development on the 500-keV negative-ion-based neutral beam injection system for JT-60U

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

Journal Articles

Conceptual design of the blanket tritium recovery system for the prototype fusion reactor

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.

JAEA Reports

Conceptual design of solid breeder blanket system cooled by supercritical water

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

JAERI-Tech-2001-078.pdf:8.3MB

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.

Journal Articles

Characteristic evaluation of HIP bonded SS/DSCu joints for surface roughness

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

Journal Articles

Safety analysis of ITER test blanket module for water cooled blanket with pebble bed breeder

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.

Journal Articles

Nuclear and thermal analyses of supercritical-water-cooled solid breeder blanket for fusion DEMO reactor

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

Journal Articles

Fusion reactor technology; Challenge to future energy

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

Journal Articles

Effective thermal conductivity measurement of the candidate ceramic breeder pebble beds by the hot wire method

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

Journal Articles

Fusion technology development for ITER in JAERI

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

Journal Articles

Development and testing of large-scale nuclear components and remote handling system in JAERI

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

JAEA Reports

Physics design of advanced steady-state tokamak reactor A-SSTR 2

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

JAERI-Research-2000-029.pdf:4.19MB

no abstracts in English

Journal Articles

Basic characteristics of heat transfer in pebble beds with high solid to gas conductivity ratio; A New numerical analysis model for effective thermal conductivity in near wall and bulk region

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

JAEA Reports

Development of ITER shielding blanket prototype mockup by HIP bonding

Sato, Satoshi; Furuya, Kazuyuki; Hatano, Toshihisa; Kuroda, Toshimasa*; Enoeda, Mikio; Takatsu, Hideyuki; Ohara, Yoshihiro

JAERI-Tech 2000-042, 121 Pages, 2000/07

JAERI-Tech-2000-042.pdf:58.33MB

no abstracts in English

Journal Articles

Development of key technologies for steady state tokamak reactor in JAERI

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

JAEA Reports

Experimental study on the influence of radiation on high-voltage insulation gases

Fujiwara, Yukio; Inoue, Takashi; Miyamoto, Kenji; Miyamoto, Naoki*; Ohara, Yoshihiro; Okumura, Yoshikazu; Watanabe, Kazuhiro

JAERI-Research 99-071, p.33 - 0, 1999/12

JAERI-Research-99-071.pdf:1.18MB

no abstracts in English

Journal Articles

ITER technology R&D report

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

168 (Records 1-20 displayed on this page)