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Fukushima, Masahiro; Kitamura, Yasunori; Kugo, Teruhiko; Yamane, Tsuyoshi; Ando, Masaki; Chiba, Go; Ishikawa, Makoto; Okajima, Shigeaki
Progress in Nuclear Science and Technology (Internet), 2, p.306 - 311, 2011/10
Fukushima, Masahiro; Kitamura, Yasunori; Kugo, Teruhiko; Yamane, Tsuyoshi; Ando, Masaki; Chiba, Go; Ishikawa, Makoto; Okajima, Shigeaki
Proceedings of Joint International Conference of 7th Supercomputing in Nuclear Application and 3rd Monte Carlo (SNA + MC 2010) (USB Flash Drive), 6 Pages, 2010/10
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:39.17(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.
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:64.88(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.
Fukushima, Masahiro; Okajima, Shigeaki; Ando, Masaki; Yamane, Tsuyoshi; Kataoka, Masaharu*
JAERI-Research 2005-008, 57 Pages, 2005/03
no abstracts in English
Kojima, Kensuke; Okajima, Shigeaki; Yamane, Tsuyoshi; Ando, Masaki; Kataoka, Masaharu*; Iwanaga, Kohei
JAERI-Tech 2004-016, 38 Pages, 2004/03
To investigate the void coefficient in the Reduced-Moderation Water Reactor (RMWR), an infinite multiplication factor was measured in the FCA-XXII-1 (65V) core. Axial and radial fission rate distributions were measured by micro fission chambers with four different kinds of nuclides. The infinite multiplication factor was derived from the material buckling, which was obtained from both the axial and radial fission rate distributions, and the migration area calculated. The value of it in the test region of the FCA-XXII-1 (65V) core was 1.3440.034. It was compared with the calculation, the ratio of the calculation to the measurement was 1.008
0.026. The improvement in measurement accuracy was also considered.
Suzuki, Katsuo; Nabeshima, Kunihiko; Yamane, Tsuyoshi; Fujii, Yoshio*
Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.408 - 417, 2003/12
On-line and real-time estimation of time-varying reactivity in a nuclear reactor is necessary for early detection of reactivity anomaly and safe operation. Using a digital nonlinear H estimator, an experiment of real-time dynamic reactivity estimation was carried out in the VHTRC of JAERI. Some technical issues of the experiment are described, such as reactivity insertion, data sampling frequency, anti-aliasing filter, experimental circuit and digitalizing nonlinear H
reactivity estimator, and so on. Then, we discussed the experimental results obtained by the digital nonlinear H
estimator with sampled data of the nuclear instrumentation signal for the power responses under various reactivity insertions. Good performances of estimated reactivity were observed, with almost no delay to the true reactivity and sufficient accuracy between 0.05cent and 0.1cent. From the results of the experiment, it is concluded that the digital nonlinear H
reactivity estimator can be applied as on-line real-time reactivity meter for actual nuclear plants.
Iwanaga, Kohei; Yamane, Tsuyoshi; Nishihara, Kenji; Okajima, Shigeaki; Sekimoto, Hiroshi*; Asaoka, Takumi*
Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), 10 Pages, 2003/04
no abstracts in English
Nishihara, Kenji; Iwanaga, Kohei; Yamane, Tsuyoshi; Okajima, Shigeaki
JAERI-Research 2002-030, 63 Pages, 2002/12
During the experiments using the critical assembly such that reactivity is added to the stationary state and the core shifts to the other stationary state, the neutron flux transitionally changes after some change of the reactivity or source. Inverse kinetics method (IK method) can generally adopted as the technique of obtaining the reactivity and/or source by analyzing the neutron flux. However, the conventional analysis method was not able to obtain the solution with the maximum likelihood considering the error of the measured neutron flux and to estimate the error of the solution. In the present research, by adopting the maximum likelihood methodology to the problem, developed is the technique to obtain the reactivity and source intensity with maximum likelihood and the errors of them. Moreover, the technique is applied to the rod drops experiment in FCA, and the validity of a technique is checked.
Yoshida, Tadashi*; Okajima, Shigeaki; Sakurai, Takeshi; Nakajima, Ken; Yamane, Tsuyoshi; Katakura, Junichi; Tahara, Yoshihisa*; Zukeran, Atsushi*; Oyamatsu, Kazuhiro*; Osawa, Takaaki*; et al.
Journal of Nuclear Science and Technology, 39(Suppl.2), p.136 - 139, 2002/08
no abstracts in English
Tsunoda, Hirokazu*; Sato, Osamu*; Okajima, Shigeaki; Yamane, Tsuyoshi; Iijima, Susumu; Kobe, Mitsuru*
Proceedings of International Congress on Advanced Nuclear Power Plants (ICAPP) (CD-ROM), 6 Pages, 2002/00
no abstracts in English
Kaneko, Yoshihiko*; Nagao, Yoshiharu; Yamane, Tsuyoshi; Takeuchi, Mitsuo
JAERI-Conf 99-006, p.316 - 321, 1999/08
no abstracts in English
Yamane, Tsuyoshi;
JAERI-Data/Code 99-011, 46 Pages, 1999/03
no abstracts in English
Maekawa, Hiroshi; Mukaiyama, Takehiko; Yamane, Tsuyoshi; ; ; Suzuki, Atsuyuki*; Takeda, Renzo*; ; Kawashima, Masatoshi*; ; et al.
Nihon Genshiryoku Gakkai-Shi, 40(12), p.963 - 965, 1998/12
no abstracts in English
Yamane, Tsuyoshi; Yamashita, Kiyonobu; Fujimoto, Nozomu
New approaches to the nuclear fuel cycles and related disposal schemes, 1, p.267 - 277, 1998/00
no abstracts in English
Yamane, Tsuyoshi; Takeuchi, Mitsuo; Shimakawa, Satoshi; Kaneko, Yoshihiko*
Nihon Genshiryoku Gakkai-Shi, 40(2), p.122 - 123, 1998/00
Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)no abstracts in English
Akino, Fujiyoshi; Yamane, Tsuyoshi
Nihon Genshiryoku Gakkai-Shi, 40(4), p.262 - 264, 1998/00
no abstracts in English
Nojiri, Naoki; Yamashita, Kiyonobu; Fujimoto, Nozomu; Nakano, Masaaki*; Yamane, Tsuyoshi; Akino, Fujiyoshi
JAERI-Tech 97-060, 34 Pages, 1997/11
no abstracts in English
Kaneko, Yoshihiko*; Shimakawa, Satoshi; Nagao, Yoshiharu; Yamashita, Kiyonobu; ; Yamane, Tsuyoshi
JAERI-Research 97-003, 70 Pages, 1997/02
no abstracts in English
Yamashita, Kiyonobu; Ando, Hiroei; Nojiri, Naoki; Fujimoto, Nozomu; Nakata, Tetsuo*; Watanabe, Takashi*; Yamane, Tsuyoshi; Nakano, Masaaki*
Proc. of SARATOGA 1997, 2, p.1557 - 1566, 1997/00
no abstracts in English