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Watanabe, Hitoshi; Nakano, Masanao; Fujita, Hiroki; Kono, Takahiko; Inoue, Kazumi; Yoshii, Hideki*; Otani, Kazunori*; Hiyama, Yoshinori*; Goto, Ichiro*; Kibe, Satoshi*; et al.
JAEA-Review 2014-040, 115 Pages, 2015/01
JAEA-Review-2014-040.pdf:4.26MB
Based on the regulations (the safety regulation of Tokai reprocessing plant, the safety regulation of nuclear fuel material usage facilities, the radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and bylaw of Ibaraki prefecture), the effluent control of liquid waste discharged from the Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency has been performed. This report describes the effluent control results of the liquid waste in the fiscal year 2013. In this period, the concentrations and the quantities of the radioactivity in liquid waste discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other nuclear fuel material usage facilities were much lower than the limits authorized by the above regulations.
Tobita, Kenji; Nishio, Satoshi*; Enoeda, Mikio; Nakamura, Hirofumi; Hayashi, Takumi; Asakura, Nobuyuki; Uto, Hiroyasu; Tanigawa, Hiroyasu; Nishitani, Takeo; Isono, Takaaki; et al.
JAEA-Research 2010-019, 194 Pages, 2010/08
JAEA-Research-2010-019-01.pdf:48.47MBJAEA-Research-2010-019-02.pdf:19.4MB
This report describes the results of the conceptual design study of the SlimCS fusion DEMO reactor aiming at demonstrating fusion power production in a plant scale and allowing to assess the economic prospects of a fusion power plant. The design study has focused on a compact and low aspect ratio tokamak reactor concept with a reduced-sized central solenoid, which is novel compared with previous tokamak reactor concept such as SSTR (Steady State Tokamak Reactor). The reactor has the main parameters of a major radius of 5.5 m, aspect ratio of 2.6, elongation of 2.0, normalized beta of 4.3, fusion out put of 2.95 GW and average neutron wall load of 3 MW/m
. This report covers various aspects of design study including systemic design, physics design, torus configuration, blanket, superconducting magnet, maintenance and building, which were carried out increase the engineering feasibility of the concept.
S
Nakao, Hironori*; Owada, Kenji; Shimomura, Susumu*; Ochiai, Akira*; Namikawa, Kazumichi*; Mizuki, Junichiro; Mimura, Hidekazu*; Yamauchi, Kazuto*; Murakami, Yoichi*
AIP Conference Proceedings 1234, p.935 - 938, 2010/06
Times Cited Count：2 Percentile：66.79(Physics, Applied)
electronic states of the uranium monochalcogenide US as seen via soft X-ray photoemissionTakeda, Yukiharu; Okane, Tetsuo; Okochi, Takuo*; Saito, Yuji; Yamagami, Hiroshi; Fujimori, Atsushi*; Ochiai, Akira*
Physical Review B, 80(16), p.161101_1 - 161101_4, 2009/10
Times Cited Count：8 Percentile：36.58(Materials Science, Multidisciplinary)no abstracts in English
Tobita, Kenji; Nishio, Satoshi; Enoeda, Mikio; Kawashima, Hisato; Kurita, Genichi; Tanigawa, Hiroyasu; Nakamura, Hirofumi; Honda, Mitsuru; Saito, Ai*; Sato, Satoshi; et al.
Nuclear Fusion, 49(7), p.075029_1 - 075029_10, 2009/07
Times Cited Count：139 Percentile：97.7(Physics, Fluids & Plasmas)Recent design study on SlimCS focused mainly on the torus configuration including blanket, divertor, materials and maintenance scheme. For vertical stability of elongated plasma and high beta access, a sector-wide conducting shell is arranged in between replaceable and permanent blanket. The reactor adopts pressurized-water-cooled solid breeding blanket. Compared with the previous advanced concept with supercritical water, the design options satisfying tritium self-sufficiency are relatively scarce. Considered divertor technology and materials, an allowable heat load to the divertor plate should be 8 MW/m or lower, which can be a critical constraint for determining a handling power of DEMO (a combination of alpha heating power and external input power for current drive).
CMatsumura, Takeshi*; Inami, Toshiya; Kosaka, Masashi*; Kato, Yoshiaki*; Inukai, Takaki*; Ochiai, Akira*; Nakao, Hironori*; Murakami, Yoichi*; Katano, Susumu*; Suzuki, Hiroyuki*
Journal of the Physical Society of Japan, 77(10), p.103601_1 - 103601_4, 2008/10
Times Cited Count：14 Percentile：62.88(Physics, Multidisciplinary)
absorption edgesOkane, Tetsuo; Takeda, Yukiharu; Okamoto, Jun*; Mamiya, Kazutoshi*; Okochi, Takuo; Fujimori, Shinichi; Saito, Yuji; Yamagami, Hiroshi; Fujimori, Atsushi; Ochiai, Akira*; et al.
Journal of the Physical Society of Japan, 77(2), p.024706_1 - 024706_6, 2008/02
Times Cited Count：15 Percentile：64.33(Physics, Multidisciplinary)Okane, Tetsuo; Takeda, Yukiharu; Fujimori, Shinichi; Saito, Yuji; Okamoto, Jun*; Mamiya, Kazutoshi*; Muramatsu, Yasuji*; Fujimori, Atsushi; Ochiai, Akira*; Haga, Yoshinori; et al.
Journal of the Physical Society of Japan, 75(Suppl.), p.105 - 106, 2006/08
no abstracts in English
Kiuchi, Kiyoshi; Ioka, Ikuo; Tanabe, Makoto*; Nanjo, Yoshiyasu*; Ogawa, Hiroaki; Ishijima, Yasuhiro; Tsukatani, Ichiro; Ochiai, Takamasa; Kizaki, Minoru; Kato, Yoshiaki; et al.
JAEA-Research 2006-023, 173 Pages, 2006/03
JAEA-Research-2006-023.pdf:20.51MB
The research concerning new cladding materials for ultra-high burnup of fuel elements with MOX fuels aiming at 100 GWd/t of BWR was pursued for 5 years from 2001 to 2005. On the Phase 1, the modified stainless steel of Fe-25Cr-35Ni-0.2Ti as fuel claddings and Nb-Mo alloy as a liner for inhibiting the pellet- clad interaction were selected as candidate materials, by evaluating fundamental properties required to BWR cladding materials, that are the nuclear economy, radioactivity, mass-transfer, irradiation properties, mechanical properties so on. On the present study, the making process of cladding tubes, lining by diffusion bonding, end plug by laser welding were developed and optimized, by considering the practical use of fuel elements consists of these candidates. The practical applicability was basically examined by irradiation tests using the accelerator of TIARA and the research reactor of JRR-3, for mainly confirming the resistance to IGSCC as one of the current important issues of BWR core materials of low carbon grade stainless steels. Creep and fatigue testing data were also obtained for evaluating the long performance of candidate materials. The behavior as fuel elements was analyzed with the safety calculation code for BWRs. The obtained results were established as a data base system, by considering the applicability to the fuel design and in-pile loop tests.
edges of uranium monochalcogenides US, USe and UTeOkane, Tetsuo; Okamoto, Jun; Mamiya, Kazutoshi; Fujimori, Shinichi; Saito, Yuji; Muramatsu, Yasuji; Fujimori, Atsushi; Ochiai, Akira*
Physica B; Condensed Matter, 345(1-4), p.221 - 224, 2004/03
Times Cited Count：6 Percentile：33.98(Physics, Condensed Matter)Magnetic circular dichroism (MCD) has been measured at the U absorption edges of ferromagnetic uranium monochalcogenides US, USe and UTe. The MCD signals are weaker in US than in USe and UTe. Both the spin and orbital moments are increased in going from US to USe, and then reduced from USe to UTe.
(
=Pt, Pd; 
=P, As, Sb)Iwasaki, T.*; Sekiyama, Akira*; Yamasaki, Atsushi*; Okazaki, Makoto*; Kadono, Koji*; Utsunomiya, Hiroshi*; Imada, Shin*; Saito, Yuji; Muro, Takayuki*; Matsushita, Tomohiro*; et al.
Physical Review B, 65(19), p.195109_1 - 195109_9, 2002/05
Times Cited Count：24 Percentile：71.8(Materials Science, Multidisciplinary)no abstracts in English
Yabuuchi, Noriaki; Takahashi, Masao*; Nakazawa, Toshio; Sato, Kazuo*; Shimazaki, Junya; Ochiai, Masaaki
JAERI-Research 2000-064, 76 Pages, 2001/02
JAERI-Research-2000-064.pdf:5.88MB
no abstracts in English
Yabuuchi, Noriaki; Takahashi, Masao*; Nakazawa, Toshio; Sato, Kazuo*; Shimazaki, Junya; Ochiai, Masaaki
JAERI-Research 2000-063, 69 Pages, 2001/02
JAERI-Research-2000-063.pdf:4.41MB
no abstracts in English
Takahashi, Teruo; Shimazaki, Junya; Nakazawa, Toshio; Yabuuchi, Noriaki; Fukuhara, Yoshifumi*; Kusunoki, Tsuyoshi; Ochiai, Masaaki
JAERI-Tech 2000-039, p.94 - 0, 2000/03
no abstracts in English
Torii, Yoshiya; Horiguchi, Yoji; ; ; ; Shigemoto, Masamitsu; Isshiki, Masahiko
UTNL-R-0333, 0, p.9.1 - 9.10, 1996/00
no abstracts in English
Ishida, Toshihisa; Kusunoki, Tsuyoshi; ; *; Inoue, Kimio*
Journal of Nuclear Science and Technology, 32(8), p.740 - 751, 1995/08
Times Cited Count：33 Percentile：93.13(Nuclear Science & Technology)no abstracts in English
Tsubota, Koji*; Ochiai, Yoji*; Hasegawa, Ken*; Nagasaki, Yasushi*; Yamagishi, Akiko*; Nakano, Katsushi*; Muneto, Masaru*
JNC TN7400 2005-021, 166 Pages, 1995/04
JNC-TN7400-2005-021.PDF:7.06MB
None
Ishida, Toshihisa; Kusunoki, Tsuyoshi; ; *; *; Inoue, Kimio*
Journal of Nuclear Science and Technology, 30(2), p.116 - 130, 1993/02
Times Cited Count：7 Percentile：60.37(Nuclear Science & Technology)no abstracts in English
Ishida, Toshihisa; Kusunoki, Tsuyoshi; *; Inoue, Kimio*; *; ; *; Kitamura, Toshikatsu
JAERI-M 92-123, 108 Pages, 1992/08
no abstracts in English
Ishida, Toshihisa; Kusunoki, Tsuyoshi; *; *; Inoue, Kimio*; ;
Proc. of the lst JSME/ASME Joint Int. Conf. on Nuclear Engineering, p.521 - 526, 1991/00
no abstracts in English
