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Takemoto, Noriyuki; Izumo, Hironobu; Inoue, Shuichi; Abe, Shinichi; Naka, Michihiro; Akashi, Kazutomo; Omi, Masao; Miyazawa, Masataka; Baba, Osamu*; Nagao, Yoshiharu
JAEA-Review 2008-051, 36 Pages, 2008/10
JAEA-Review-2008-051.pdf:3.14MB
The JMTR has been refurbished to restart operation in FY2011. The restarted JMTR plays roles of (1) measures for long-term operation of light water reactors, (2) improvement in scientific technique, (3) increase of industrial use, (4) training of human resources, etc. It is needed to operate the restarted JMTR safety and stably and maintain high available factor (50
70%) because of increasing of irradiation utilization demand. In this report, measures for training of reactor operators, organization for operating, etc were proposed to operate reactor safety and smoothly. And also reactor operation procedure was examined to improve available factor up to world level for materials testing reactor. As a result, it was turned out to be possible to realize stably 210 days operation per year (available factor: 60%).
Iigaki, Kazuhiko; Saikusa, Akio; Sawahata, Hiroaki; Shinozaki, Masayuki; Tochio, Daisuke; Homma, Fumitaka; Tachibana, Yukio; Iyoku, Tatsuo; Kawasaki, Kozo; Baba, Osamu*
JAEA-Review 2006-010, 90 Pages, 2006/07
JAEA-Review-2006-010.pdf:5.65MB
Gas Cooled Reactor has long history of nuclear development, and High Temperature Gas Cooled Reactor (HTGR) has been expected that it can be supply high temperature energy to chemical industry and to power generation from the points of view of the safety, the efficiency, the environment and the economy. The HTGR design is tried to installed passive safety equipment. The current licensing review guideline was made for a Low Water Reactor (LWR) on safety evaluation therefore if it would be directly utilized in the HTGR it needs the special consideration for the HTGR. This paper describes that investigation result of the safety design and the safety evaluation traditions for the HTGR, comparison the safety design and safety evaluation feature for the HTGT with it's the LWR, and reflection for next HTGR based on HTTR operational experiment.
Nishitani, Tomohiro; Nakanishi, Tsutomu*; Yamamoto, Masahiro*; Okumi, Shoji*; Furuta, Fumio*; Miyamoto, Masaharu*; Kuwahara, Makoto*; Yamamoto, Naoto*; Naniwa, Kenichi*; Watanabe, Osamu*; et al.
Journal of Applied Physics, 97(9), p.094907_1 - 094907_6, 2005/05
Times Cited Count：67 Percentile：87.41(Physics, Applied)no abstracts in English
Kawano, Toshihiko*; Matsunobu, Hiroyuki*; Murata, Toru*; Zukeran, Atsushi*; Nakajima, Yutaka*; Kawai, Masayoshi*; Iwamoto, Osamu; Shibata, Keiichi; Nakagawa, Tsuneo; Osawa, Takaaki*; et al.
JAERI-Research 2003-026, 53 Pages, 2003/12
JAERI-Research-2003-026.pdf:2.48MB
New evaluations of neutron nuclear data for Uranium, Plutonium, and Thorium isotopes which are essential for applications to nuclear technology were carried out for the Japanese Evaluated Nuclear Data Library, JENDL-3.3. The objectives of the current release of JENDL were to fix several problems which have been reported for the previous version, to improve the accuracy of the data, and to evaluate covariances for the important nuclides. Quantities in JENDL-3.2 were extensively re-evaluated or replaced by more reliable values. The heavy nuclide data in JENDL-3.3 were validated with several benchmark tests, and it was reported that the current release gave a good prediction of criticalities.
Shibata, Keiichi; Kawano, Toshihiko*; Nakagawa, Tsuneo; Iwamoto, Osamu; Katakura, Junichi; Fukahori, Tokio; Chiba, Satoshi; Hasegawa, Akira; Murata, Toru*; Matsunobu, Hiroyuki*; et al.
Journal of Nuclear Science and Technology, 39(11), p.1125 - 1136, 2002/11
Times Cited Count：674 Percentile：93.94(Nuclear Science & Technology)Evaluation for JENDL-3.3 has been performed by considering the accumulated feedback information and various benchmark tests of the previous library JENDL-3.2. The major problems of the JENDL-3.2 data were solved by the new library: overestimation of criticality values for thermal fission reactors was improved by the modifications of fission cross sections and fission neutron spectra for 
U; incorrect energy distributions of secondary neutrons from important heavy nuclides were replaced with statistical model calculations; the inconsistency between elemental and isotopic evaluations was removed for medium-heavy nuclides. Moreover, covariance data were provided for 20 nuclides. The reliability of JENDL-3.3 was investigated by the benchmark analyses on reactor and shielding performances. The results of the analyses indicate that JENDL-3.3 predicts various reactor and shielding characteristics better than JENDL-3.2.
Kawasaki, Kozo; Iyoku, Tatsuo; Nakazawa, Toshio; Okubo, Minoru; Baba, Osamu
Nihon Genshiryoku Gakkai-Shi, 44(4), P. 310, 2002/04
no abstracts in English
Kawasaki, Kozo; Iyoku, Tatsuo; Nakazawa, Toshio; Okubo, Minoru; Baba, Osamu
Nihon Genshiryoku Gakkai-Shi, 44(1), P. 2, 2002/01
no abstracts in English
Ebisawa, Katsumi; Yamada, Hiroyuki; Tsutsumi, Hideaki*; Shibata, Katsuyuki; Ando, Kazuhiro*; Baba, Osamu; Suzuki, Hideyuki
JAERI-Data/Code 2001-009, 96 Pages, 2001/03
JAERI-Data-Code-2001-009.pdf:4.14MB
no abstracts in English
Kawano, Toshihiko*; Matsunobu, Hiroyuki*; Murata, Toru*; Zukeran, Atsushi*; Nakajima, Yutaka*; Kawai, Masayoshi*; Iwamoto, Osamu; Shibata, Keiichi; Nakagawa, Tsuneo; Osawa, Takaaki*; et al.
Journal of Nuclear Science and Technology, 37(4), p.327 - 334, 2000/04
no abstracts in English
U,U,
U,
Pu,
Pu,and 
PuKawano, Toshihiko*; Matsunobu, Hiroyuki*; Murata, Toru*; Zukeran, Atsushi*; Nakajima, Yutaka*; Kawai, Masayoshi*; Iwamoto, Osamu; Shibata, Keiichi; Nakagawa, Tsuneo; Osawa, Takaaki*; et al.
JAERI-Research 2000-004, p.76 - 0, 2000/02
JAERI-Research-2000-004.pdf:2.39MB
no abstracts in English
Kaieda, Keisuke; Baba, Osamu
Proceedings of 7th Meeting of the International Group on Research Reactors (IGORR-7) (CD-ROM), p.7 - 0, 1999/00
no abstracts in English
Naka, Michihiro; ; Ooka, Norikazu; ; Ito, Haruhiko; Baba, Osamu
Proc. of CORENDE, 3 Pages, 1997/00
no abstracts in English
Tanaka, Toshiyuki; Baba, Osamu; ; Shiozawa, Shusaku; Okubo, Minoru
10th Pacific Basin Nuclear Conf. (10-PBNC), 1, p.811 - 818, 1996/10
no abstracts in English
Tanaka, Toshiyuki; Baba, Osamu; Shiozawa, Shusaku; Okubo, Minoru;
JAERI-Conf 96-010, 0, p.97 - 104, 1996/07
no abstracts in English
Kanda, Keiji*; ; Isshiki, Masahiko; Baba, Osamu; Tsuruta, Harumichi
1996 Int. Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), 0, 8 Pages, 1996/00
no abstracts in English
Baba, Osamu; Kunitomi, Kazuhiko; Kawaji, Satoshi; Tanaka, Toshiyuki; Shiozawa, Shusaku; Okubo, Minoru
Proc. of ASME
JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 2, p.281 - 287, 1996/00
no abstracts in English
Kunitomi, Kazuhiko; Shiozawa, Shusaku; Baba, Osamu
Proc. of ASMEJSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 2, p.303 - 307, 1996/00
no abstracts in English
Baba, Osamu
Sci. Technol. Jpn., 15(58), p.7 - 9, 1996/00
no abstracts in English
; Baba, Osamu; Suzuki, Hideyuki; ; ;
Dai-23-Kai Jishin Kogaku Kenkyu Happyokai Koen Gaiyoshu, 0, p.53 - 56, 1995/00
no abstracts in English
Tanaka, Toshiyuki; Baba, Osamu; Shiozawa, Shusaku; Okubo, Minoru; Tobioka, Toshiaki
The 3rd JSME/ASME Joint Int. Conf. on Nuclear Enginering (ICONE), Vol. 2, 0, p.745 - 750, 1995/00
no abstracts in English
