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Osaka, Masahiko; Takano, Sho*; Yamane, Yoshihiro*; Misawa, Tsuyoshi*
Progress in Nuclear Energy, 50(2-6), p.212 - 218, 2008/03
Times Cited Count：6 Percentile：39.07(Nuclear Science & Technology)Concept of fast reactor cycle scheme that incorporates a thoria-based minor actinide-containing cermet fuel is given. The present cermet fuel consists of oxide solid solution of Th and minor actinides and Mo inert matrix. It has been proposed as a high-performance device that can enhance minor actinide transmutation in the fast reactor cycle. It is used in an independent small cycle, whereby dedicated cycle process are adopted. Two-steps process for reprocessing of the present cermet fuel was proposed; it consists of pre-removal of Mo-inert matrix and actinide recovery. A preliminary test for pre-removal of Mo-inert matrix using surrogate cermet fuel was carried out. It was done by dissolution in nitric acid at room temperature. Results showed that Mo-inert matrix was largely dissolved, while oxide remained. Burnup characteristics of a fast reactor core loaded with the cermet fuel were investigated by using neutronic calculation codes. It was revealed that a heterogeneous composition of Mo-inert matrix in inner and outer cores could lead to effective transmutation and flattened power density. It was concluded that the present cermet fuel is potentially a promising one as a high-performance transmutation device for the fast reactor.
Sono, Hiroki; Ono, Akio; Kojima, Takuji; Yamane, Yoshihiro*
Journal of Nuclear Science and Technology, 44(1), p.43 - 53, 2007/01
Times Cited Count：2 Percentile：18.33(Nuclear Science & Technology)A practical method is proposed for retrospective estimation of the spatial dose distribution and the number of fissions in a typical criticality accident. In this method, two kinds of low-fading and tissue-equivalent dosimeters are used as area dosimeters: an alanine dosimeter and a thermoluminescence dosimeter made of enriched lithium tetra borate. The procedure of the method consists of four parts: (1) dosimetry using area dosimeters (2) search for the center of the radiation source, (3) estimation of the spatial dose distribution, and (4) estimation of the number of fissions. Dosimetry of criticality accident situations simulated at the TRACY facility demonstrates the practicability of the method. Although a post-hoc analysis in principle, this method gives useful information on the magnitude and hazard level of the accident to determine the strategy of radiation emergency medicine and other post-accident measures if the area dosimeters are retrieved immediately after the accident.
Osaka, Masahiko; Koi, Mamoru; Takano, Sho*; Yamane, Yoshihiro*; Misawa, Tsuyoshi*
Journal of Nuclear Science and Technology, 43(4), p.367 - 374, 2006/04
Times Cited Count：13 Percentile：64.80(Nuclear Science & Technology)The low oxygen potential target, which consist of (Th,Am)Ox dispersed in Mo, as a high performance Am-containing target for fast reactors is proposed. Effects of Mo isotopic ratio on the core characteristics are evaluated with various Mos having different isotopic composition.
Sono, Hiroki; Ono, Akio*; Kojima, Takuji; Takahashi, Fumiaki; Yamane, Yoshihiro*
Journal of Nuclear Science and Technology, 43(3), p.276 - 284, 2006/03
Times Cited Count：1 Percentile：9.69(Nuclear Science & Technology)For a study on the applicability of a personal dosimetry method to criticality accident dosimetry, an assessment of the human body surface and internal dose estimations was performed by experimental and computational simulations. The experimental simulation was carried out in a criticality accident situation at the TRACY facility. The neutron and 
-ray absorbed doses in muscle tissue were separately estimated by a dosimeter set of an alanine dosimeter and a thermoluminescence dosimeter made of enriched lithium tetra borate with a phantom. The computational simulation was conducted with a Monte Carlo code taking account of dose components of neutrons, prompt -rays and delayed -rays. The computational simulation was ascertained to be valid by comparison between the calculated dose distributions in the phantom and the measured ones. The assessment based on the experimental and computational simulations confirmed that the personal dosimetry using the dosimeter set provided a first estimation of the body surface and internal doses with precision.
Okajima, Shigeaki; Yamane, Yoshihiro*; Takemoto, Yoshinari*; Sakurai, Takeshi
Journal of Nuclear Science and Technology, 37(8), p.720 - 723, 2000/08
no abstracts in English
in JAERI-FCASakurai, Takeshi; Okajima, Shigeaki; ; Osugi, Toshitaka; M.Martini*; P.Chaussonnet*; H.Philibert*; I.P.Matveenko*; S.P.Belov*; V.A.Doulin*; et al.
Proc. of Int. Conf. on Physics of Nucl. Science and Technol., 1, p.182 - 189, 1998/00
no abstracts in English
Nishina, Kojiro*; ; Miyoshi, Yoshinori; Suzaki, Takenori; Okuno, Hiroshi; Nomura, Yasushi; Mitake, Susumu*; ; Tonoike, Kotaro; ; et al.
Nihon Genshiryoku Gakkai-Shi, 38(4), p.262 - 271, 1996/00
no abstracts in English
; Nakano, Yoshihiro; Yamane, Yoshihiro*; ;
JAERI-Research 95-059, 83 Pages, 1995/09
JAERI-Research-95-059.pdf:2.24MB
no abstracts in English
Nishina, Kojiro*; Yamane, Yoshihiro*; Kobayashi, Iwao; Tachimori, Shoichi; ; Miyoshi, Yoshinori; Okuno, Hiroshi; Nakajima, Ken; Mitake, Susumu*; ; et al.
Nihon Genshiryoku Gakkai-Shi, 34(4), p.311 - 319, 1992/04
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)no abstracts in English
Okajima, Shigeaki; Nishi, Hiroshi; Kanemoto, Shigeru*; Yamane, Yoshihiro*; Fukushima, Masahiro; Kitamura, Yasunori; Kitano, Akihiro; Suzuki, Takayuki; Ando, Masaki; Yamane, Tsuyoshi
no journal, ,
no abstracts in English
Fukushima, Masahiro; Okajima, Shigeaki; Kitamura, Yasunori; Ando, Masaki; Yamane, Tsuyoshi; Mori, Takamasa; Nishi, Hiroshi; Yamane, Yoshihiro*; Kanemoto, Shigeru*
no journal, ,
no abstracts in English
Okajima, Shigeaki; Nishi, Hiroshi; Yamane, Yoshihiro*; Kanemoto, Shigeru*; Yamane, Tsuyoshi; Mori, Takamasa; Kitamura, Yasunori; Fukushima, Masahiro; Kitano, Akihiro; Ando, Masaki; et al.
no journal, ,
The program was planned and has been carried out to develop of the reactivity feedback effect measurement techniques under sub-critical condition in the start-up experiment for fast reactors. The program includes the demonstration of the developed technique in fast critical assembly (FCA) and the proposal of the appropriate measurement system based on the results. The background and the purposes of the program and the outline of development subjects are presented.
Kitamura, Yasunori; Yamane, Yoshihiro*; Okajima, Shigeaki; Fukushima, Masahiro; Ando, Masaki; Yamane, Tsuyoshi
no journal, ,
no abstracts in English
Yamane, Yoshihiro*; Sugawara, Kei*; Okajima, Shigeaki
no journal, ,
no abstracts in English
Osaka, Masahiko; Miwa, Shuhei; Kurosaki, Ken*; Yamanaka, Shinsuke*; Uno, Masayoshi*; Yamane, Yoshihiro*; Mimura, Hitoshi*; Yano, Toyohiko*
no journal, ,
Inert matrix fuel concept that is adaptable to the fast reactor cycle system was proposed. The concept has unique characteristics of a flexible management of minor actinides and effective utilization of beneficial materials in the nuclear cycle.
Takano, Nao*; Yamamoto, Mitsuru*; Takahashi, Yuko*; Teranishi, Mika*; Sakamoto, Ayako; Hase, Yoshihiro; Tanaka, Atsushi; Wu, J.*; Matsumoto, Takashi*; Toki, Seiichi*; et al.
no journal, ,
no abstracts in English
Kitamura, Yasunori; Fukushima, Masahiro; Ando, Masaki; Okajima, Shigeaki; Yamane, Tsuyoshi; Yamane, Yoshihiro*
no journal, ,
no abstracts in English
Fukushima, Masahiro; Kitamura, Yasunori; Ando, Masaki; Okajima, Shigeaki; Yamane, Tsuyoshi; Yamane, Yoshihiro*
no journal, ,
no abstracts in English
