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Horiike, Takumi*; Dotsuta, Yuma*; Nakano, Yuriko*; Ochiai, Asumi*; Utsunomiya, Satoshi*; Onuki, Toshihiko; Yamashita, Mitsuo*
Applied and Environmental Microbiology, 83(20), p.e00855-17_1 - e00855-17_11, 2017/10
Times Cited Count:14 Percentile:59.31(Biotechnology & Applied Microbiology)Radioactive strontium (Sr) leaked into the ocean from the Fukushima Daiichi Nuclear Power Plant after the nuclear accident. Since the removal of Sr using general adsorbents is not efficient at high salinity, this study investigated removal of soluble Sr from a saline solution by biogenic carbonate minerals. An isolate, Bacillus sp. strain TK2d, from marine sediment removed more than 99 % of Sr in a saline solution. Sr adsorbed at the cell surface and then carbonate minerals containing Sr developed outside the cells.
Tanaka, Kosuke; Suto, Mitsuo; Onishi, Takashi; Akutsu, Yoko; Yoshitake, Tsunemitsu; Yamashita, Shinichiro; Sekioka, Ken*; Ishigamori, Toshio*; Obayashi, Hiroshi; Koyama, Shinichi
JAEA-Research 2013-036, 31 Pages, 2013/12
In the accident of Fukushima Daiichi NPPs, the water ingress was performed in order to decrease the reactor temperature. At that time, sea water was temporarily used as a coolant and the water contacted with nuclear fuel directly. It can be supposed that fission products (FP) were easily migrated from the fuel to sea water in this situation and that affect the water quality. The knowledge of leaching behavior, therefore, is necessary for evaluating the integrity of reactor component materials such as steels for pressure containment vessel and for reactor vessel. In order to obtain the fundamental knowledge for leaching behavior of FP in the hot sea water, the leaching tests of irradiated fuel were performed and the leachates were subjected to chemical analysis. It is found that he leaching rate of each nuclides obtained in this study were similar to that of the leaching results simulating the underground water.
Fujimoto, Nozomu; Yamashita, Kiyonobu*; Nojiri, Naoki; Takeuchi, Mitsuo; Fujisaki, Shingo; Nakano, Masaaki*
Nuclear Science and Engineering, 150(3), p.310 - 321, 2005/07
Times Cited Count:6 Percentile:40.53(Nuclear Science & Technology)Annular cores were formed in startup-core-physics tests of the High Temperature Engineering Test Reactor (HTTR) to obtain experimental data for verification of calculation codes. The first criticality, control rod positions at critical conditions, neutron flux distribution, excess reactivity etc. were measured as representative data. These data were evaluated with Monte Carlo code MVP that can consider the heterogeneity of coated fuel particles (CFP) distributed randomly in fuel compacts directly. It was made clear that the heterogeneity effect of CFP on reactivity for annular cores is smaller than that for fully-loaded cores. Measured and calculated effective multiplication factors (k) were agreed with differences less than 1%k. Measured neutron flux distributions agreed with calculated results. The revising method was applied for evaluation of excess reactivity to exclude negative shadowing effect of control rods. The revised and calculated excess reactivity agreed with differences less than 1%k/k.
Fujimoto, Nozomu; Nakano, Masaaki*; Takeuchi, Mitsuo; Fujisaki, Shingo; Yamashita, Kiyonobu
Nihon Genshiryoku Gakkai-Shi, 42(5), p.458 - 464, 2000/05
Times Cited Count:6 Percentile:42.69(Nuclear Science & Technology)no abstracts in English
Yamashita, Kiyonobu; Fujimoto, Nozomu; Takeuchi, Mitsuo; Fujisaki, Shingo; Nakano, Masaaki*; Umeta, Masayuki; Takeda, Takeshi; Mogi, Haruyoshi; Tanaka, Toshiyuki
Nihon Genshiryoku Gakkai-Shi, 42(1), p.30 - 42, 2000/01
Times Cited Count:3 Percentile:26.46(Nuclear Science & Technology)no abstracts in English
Fujimoto, Nozomu; Nakano, Masaaki*; Nojiri, Naoki; Takeuchi, Mitsuo; Fujisaki, Shingo; Yamashita, Kiyonobu
JAERI-Conf 99-006, p.328 - 333, 1999/08
no abstracts in English
Yamashita, Kiyonobu; Takeuchi, Mitsuo; Fujimoto, Nozomu; Fujisaki, Shingo; Nakano, Masaaki*; Nojiri, Naoki; Tamura, Seiji*
Nihon Genshiryoku Gakkai-Shi, 41(1), p.35 - 38, 1999/00
Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)no abstracts in English
Fujimoto, Nozomu; Takeuchi, Mitsuo; Fujisaki, Shingo; Nakano, Masaaki*; Yamashita, Kiyonobu; Mogi, Haruyoshi
UTNL-R-0378, p.5.1 - 5.10, 1999/00
no abstracts in English
Nojiri, Naoki; Nakano, Masaaki; Ando, Hiroei; Fujimoto, Nozomu; Takeuchi, Mitsuo; Fujisaki, Shingo; Yamashita, Kiyonobu
JAERI-Tech 98-032, 59 Pages, 1998/08
no abstracts in English
Fujimoto, Nozomu; Nojiri, Naoki; Nakano, Masaaki*; Takeuchi, Mitsuo; Fujisaki, Shingo; Yamashita, Kiyonobu
JAERI-Tech 98-021, 66 Pages, 1998/06
no abstracts in English
Nakano, Masaaki; Yamashita, Kiyonobu; Fujimoto, Nozomu; Nojiri, Naoki; Takeuchi, Mitsuo; Fujisaki, Shingo; *; Nakata, Tetsuo*
JAERI-Tech 98-017, 61 Pages, 1998/05
no abstracts in English
Yamashita, Kiyonobu; Nojiri, Naoki; Fujimoto, Nozomu; Nakano, Masaaki*; Ando, Hiroei; Nagao, Yoshiharu; Nagaya, Yasunobu; Akino, Fujiyoshi; Takeuchi, Mitsuo; Fujisaki, Shingo; et al.
Proc. of IAEA TCM on High Temperature Gas Cooled Reactor Applications and Future Prospects, p.185 - 197, 1998/00
no abstracts in English
Hayashi, Kimio; Shiozawa, Shusaku; Fukuda, Kosaku; Tsuruta, Harumichi; Ikawa, Katsuichi; *; ; Tobita, Tsutomu; Shiratori, Tetsuo; Akabori, Mitsuo; et al.
JAERI-M 90-115, 77 Pages, 1990/07
no abstracts in English
Nishimoto, Wataru*; Kimuro, Harumi*; Ishibashi, Seijiro*; Miyahara, Shuji*; Yamashita, Saburo*; Hayashi, Mitsuo*; Suzuki, Yoji*; Hirose, Yasuo*
PNC TJ118 85-06VOL2, 221 Pages, 1985/04
None
Nishimoto, Wataru*; Kimuro, Harumi*; Ishibashi, Seijiro*; Miyahara, Shuji*; Yamashita, Saburo*; Hayashi, Mitsuo*; Suzuki, Yoji*; Hirose, Yasuo*
PNC TJ118 85-06VOL1, 21 Pages, 1985/04
no abstracts in English
Shimizu, Makoto*; Kimuro, Harumi*; Ayabe, Muneo*; Kouno, Yasumasa*; Miyahara, Shuji*; Yamashita, Saburo*; Kanazawa, Kazuo*; Hayashi, Mitsuo*; Yoshizaki, Masato*
PNC TJ118 83-05VOL2, 222 Pages, 1984/03
None
Shimizu, Makoto*; Kimuro, Harumi*; Ayabe, Muneo*; Kouno, Yasumasa*; Miyahara, Shuji*; Yamashita, Saburo*; Kanazawa, Kazuo*; Hayashi, Mitsuo*; Yoshizaki, Masato*
PNC TJ118 83-05VOL1, 42 Pages, 1984/03
None
Yamashita, Mitsuo*; Saruwatari, Mitsuyoshi*; Shigi, Tadasuke*; Nishikawa, Akira*; Hara, Masatsugu*
PNC TN251 75-21, 40 Pages, 1975/05
Boron carbide pellets (BC pellets), having 90% relative density, were experimentally fabricated and characterized to be applied to the control rods of the experimental fast reactor "JOYO" MK-II. Raw BC pellets were hot-pressed from natural BC powder and then finished pellets were prepared by burnishing them to adjust their dimensions. Their dimensions, weights, densities, X-ray diffraction patterns, microscopies, chemical compositions and adsorbed gases were measured. Finished BC pellets are concluded to satisfy their requirements such as dimension, weight, density, chemical composition and impurity levels. However, density was presumed to be heterogeneous inside pellets, since heterogeneous distribution of pore was observed under microscope.
Yamashita, Junichi*; Fukasawa, Tetsuo*; Kawamura, Fumio*; Hoshino, Kuniyoshi*; Sasahira, Akira*; Minato, Kazuo; Akabori, Mitsuo; Arai, Yasuo
no journal, ,
no abstracts in English
Tanaka, Kosuke; Suto, Mitsuo; Onishi, Takashi; Akutsu, Yoko; Obayashi, Hiroshi; Koyama, Shinichi; Yoshitake, Tsunemitsu; Yamashita, Shinichiro; Sekioka, Ken*; Ishigamori, Toshio*
no journal, ,
Chemical analysis of artificial seawater after immersion tests of irradiated fuel was carried out.