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Xe ions on proton, deuteron, and carbon targetsSun, X. H.*; Wang, H.*; Otsu, Hideaki*; Sakurai, Hiroyoshi*; Ahn, D. S.*; Aikawa, Masayuki*; Fukuda, Naoki*; Isobe, Tadaaki*; Kawakami, Shunsuke*; Koyama, Shumpei*; et al.
Physical Review C, 101(6), p.064623_1 - 064623_12, 2020/06
Times Cited Count：5 Percentile：52.72(Physics, Nuclear)The spallation and fragmentation reactions of Xe induced by proton, deuteron and carbon at 168 MeV/nucleon were studied at RIKEN Radioactive Isotope Beam Factory via the inverse kinematics technique. The cross sections of the lighter products are larger in the carbon-induced reactions due to the higher total kinetic energy of carbon. The energy dependence was investigated by comparing the newly obtained data with previous results obtained at higher reaction energies. The experimental data were compared with the results of SPACS, EPAX, PHITS and DEURACS calculations. These data serve as benchmarks for the model calculations.
Wang, H.*; Otsu, Hideaki*; Chiga, Nobuyuki*; Kawase, Shoichiro*; Takeuchi, Satoshi*; Sumikama, Toshiyuki*; Koyama, Shumpei*; Sakurai, Hiroyoshi*; Watanabe, Yukinobu*; Nakayama, Shinsuke; et al.
Communications Physics (Internet), 2(1), p.78_1 - 78_6, 2019/07
Times Cited Count：8 Percentile：56.2(Physics, Multidisciplinary)Searching for effective pathways for the production of proton- and neutron-rich isotopes through an optimal combination of reaction mechanism and energy is one of the main driving forces behind experimental and theoretical nuclear reaction studies as well as for practical applications in nuclear transmutation of radioactive waste. We report on a study on incomplete fusion induced by deuteron, which contains one proton and one neutron with a weak binding energy and is easily broken up. This reaction study was achieved by measuring directly the cross sections for both proton and deuteron for 
Pd at 50 MeV/u via inverse kinematics technique. The results provide direct experimental evidence for the onset of a cross-section enhancement at high energy, indicating the potential of incomplete fusion induced by loosely-bound nuclei for creating proton-rich isotopes and nuclear transmutation of radioactive waste.
-ray fields with novel nuclear emulsion techniqueIshihara, Kohei*; Takagi, Keisuke*; Minato, Haruna*; Kawarabayashi, Jun*; Tomita, Hideki*; Maeda, Shigetaka; Naka, Tatsuhiro*; Morishima, Kunihiro*; Nakano, Toshiyuki*; Nakamura, Mitsuhiro*; et al.
Radiation Measurements, 55, p.79 - 82, 2013/08
Times Cited Count：1 Percentile：10.69(Nuclear Science & Technology)In order to measure the neutron under a condition of high intensity of -ray background, we made new nuclear emulsion based on non-sensitized OPERA emulsion which had small AgBr grain size (AgBr grain size of 60, 90 and 160 nm). The sensitivity of this new emulsion, which was a correlation between stopping power and grain density, was estimated experimentally by irradiating neutrons with several energies. We also simulated the response to -ray induced electrons and compared with some experimental results by using 
Co source. The results showed that there might be a threshold energy deposited in one AgBr grain under which it was impossible to develop. We estimated efficiency to the -ray and the neutron with this obtained response of the new emulsion.
Kaminuma, Takuya*; Suzuki, Yoshiyuki*; Shirai, Katsuyuki*; Mizui, Toshiyuki*; Noda, Shinei*; Yoshida, Yukari*; Funayama, Tomoo; Takahashi, Takeo*; Kobayashi, Yasuhiko; Shirao, Tomoaki*; et al.
Journal of Radiation Research, 51(6), p.627 - 631, 2010/11
Times Cited Count：9 Percentile：33.86(Biology)Shirasu, Noriko; Kuramoto, Kenichi; Nakano, Yoshihiro; Yamashita, Toshiyuki; Kimura, Yasuhiko; Nihei, Yasuo; Ogawa, Toru
Journal of Nuclear Materials, 376(1), p.88 - 97, 2008/05
Times Cited Count：13 Percentile：64.63(Materials Science, Multidisciplinary)The concept of the rock-like oxide (ROX) fuel has been developed for the annihilation of excess plutonium in light water reactors. Irradiation tests and post-irradiation examinations were carried out on candidate ROX fuels. The ternary fuel of YSZ-spinel-corundum system, the single-phase fuels of YSZ, the particle dispersed fuels of YSZ in spinel or corundum matrix, and the blended fuels of YSZ and spinel or corundum matrix were fabricated and submitted to irradiation tests. The fuels containing spinel showed chemical instabilities with the vaporization of MgO component, which caused fuel restructuring. The swelling behavior was improved with the particle-dispersed fuels. However, the particle-dispersed fuels showed higher fractional gas release (FGR) than blended type fuels. The FGR of YSZ single-phase fuels were comparable to what would be expected for UO
fuels. The YSZ single-phase fuel showed the best irradiation performance among the ROX fuels investigated.
Shirasu, Noriko; Kuramoto, Kenichi; Nakano, Yoshihiro; Yamashita, Toshiyuki; Ogawa, Toru
Journal of Power and Energy Systems (Internet), 2(1), p.145 - 152, 2008/00
To evaluate the irradiation behavior of the rock-like oxide fuel, irradiation experiments were carried out. Three fuels were prepared; a single phase fuel of yttria-stabilized zirconia containing UO (U-YSZ) and two types of particle-dispersed fuels of U-YSZ particles in spinel or corundum matrix. These fuels were irradiated in JRR-3 for about 280 days. The burnups were about 11% FIMA. The fission gas release rate (FGR) was determined by puncture test and gas analysis. Corundum-based fuel showed extremely high FGR (88%). The temperature of U-YSZ single-phase fuel pellets was highest among the fuels, because of its low thermal conductivity. Nevertheless the U-YSZ single-phase fuel showed very low FGR (5%). Microstructure analyses of irradiated fuel pellets were carried out by ceramography and EPMA. The restructuring of fuel pellet was not observed in the spinel-based fuel irradiated below 1400 K.
Shirasu, Noriko; Kuramoto, Kenichi; Nakano, Yoshihiro; Yamashita, Toshiyuki; Ogawa, Toru
Proceedings of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), 7 Pages, 2007/04
To evaluate the irradiation behavior of the rock-like oxide fuel, irradiation experiments were carried out. Three fuels were prepared; a single phase fuel of yttria-stabilized zirconia containing UO (U-YSZ) and two particle-dispersed fuels of U-YSZ particles in spinel or corundum matrix. These fuels were irradiated in JRR-3 for about 280 days. The burnups were about 11% FIMA. The fission gas release rate (FGR) was determined by puncture test and gas analysis. Corundum-based fuel showed extremely high FGR (88%). On the other hand, the U-YSZ single-phase fuel showed very low FGR (5%). Microstructure analyses for irradiated fuel pellets were carried out by ceramography and EPMA. The restructuring of fuel pellet was not observed in the spinel-based fuel irradiated below 1400 K. Significant appearance changes were not also observed for corundum-based fuel.
Suzuki, Yoshiyuki*; Yoshida, Yukari*; Shirai, Katsuyuki*; Hamada, Nobuyuki*; Mizui, Toshiyuki*; Noda, Shinei*; Funayama, Tomoo; Sakashita, Tetsuya; Kobayashi, Yasuhiko; Shirao, Tomoaki*; et al.
JAEA-Review 2006-042, JAEA Takasaki Annual Report 2005, P. 107, 2007/02
Shirai, Katsuyuki*; Mizui, Toshiyuki*; Suzuki, Yoshiyuki*; Kobayashi, Yasuhiko; Nakano, Takashi*; Shirao, Tomoaki*
Neuroscience Letters, 399(1-2), p.57 - 60, 2006/05
Times Cited Count：21 Percentile：34.97(Neurosciences)no abstracts in English
Yamashita, Toshiyuki; Kuramoto, Kenichi; Shirasu, Noriko; Nakano, Yoshihiro; Akie, Hiroshi; Nagashima, Hisao; Kimura, Yasuhiko; Omichi, Toshihiko*
Journal of Nuclear Materials, 320(1-2), p.126 - 132, 2003/07
Times Cited Count：10 Percentile：56.43(Materials Science, Multidisciplinary)Two irradiation tests on the rock-like oxide (ROX) fuels, small disk-shape fuel targets and pellet-type fuels, were performed in order to clarify in-pile irradiation stabilities. Swelling, fractional fission gas release (FGR) and phase change were examined by puncture test, profilometry and ceramography. YSZ single-phase fuel showed an excellent irradiation behavior, ie. low fission gas release (less than 3%), negligible swelling and no appreciable restructuring. The particle dispersed fuels showed lower swelling and higher fission gas release than those of mechanically blended fuels. Spinel decomposition and subsequence restructuring in the spinel matrix fuels was observed for the first time in the present investigation. It would be possible to reduce the FGR of the spinel matrix fuels, if the maximum fuels temperature is limited below 1700 K where neither spinel decomposition nor restructuring was observed. Damaged area of spinel matrix due to fission fragment irradiation seemed to be confined to thin layers around the surface of YSZ particles.
Yamashita, Toshiyuki; Kuramoto, Kenichi; Akie, Hiroshi; Nakano, Yoshihiro; Shirasu, Noriko; Nakamura, Takehiko; Kusagaya, Kazuyuki*; Omichi, Toshihiko*
Journal of Nuclear Science and Technology, 39(8), p.865 - 871, 2002/08
Times Cited Count：25 Percentile：81.52(Nuclear Science & Technology)Research on the plutonium rock-like oxide (ROX) fuels and their once-through burning in light water reactors has been performed to establish an option for utilizing and disposing effectively the excess plutonium. The ROX fuel is a sort of the inert matrix fuels and consists of mineral-like compounds such as yttria stabilized zirconia, spinel and corundum. A particle-dispersed fuel was devised to reduce damage by heavy fission fragments. Some preliminary results on swelling, fractional gas release and microstructure change for five ROX fuels were obtained from the irradiation test and successive post-irradiation examinations. Inherent disadvantages of the Pu-ROX fuel cores could be improved by adding 238U or 232Th as resonant materials, and all improved cores showed a nearly the same characteristics as the conventional UO2 core during transient conditions. The threshold enthalpy of the ROX fuel rod failure was found to be comparable to the fresh UO2 rod by pulse-irradiation tests simulating reactivity initiated accident conditions.
Yamashita, Toshiyuki; Akie, Hiroshi; Nakano, Yoshihiro; Kuramoto, Kenichi; Nitani, Noriko; Nakamura, Takehiko
Progress in Nuclear Energy, 38(3-4), p.327 - 330, 2001/02
Times Cited Count：12 Percentile：64.73(Nuclear Science & Technology)no abstracts in English
Yamashita, Toshiyuki; Kuramoto, Kenichi; Akie, Hiroshi; Nakano, Yoshihiro; Nitani, Noriko; Nakamura, Takehiko; Kusagaya, Kazuyuki*; Omichi, Toshihiko*
Proceedings of Workshop on Advanced Reactors with Innovative Fuels (ARWIF 2001) (CD-ROM), 10 Pages, 2001/00
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：26.42(Nuclear Science & Technology)no abstracts in English
Yamashita, Toshiyuki; Akie, Hiroshi; Nitani, Noriko; Nakano, Yoshihiro; Nakamura, Takehiko; Shiratori, Tetsuo; Suzuki, Yasufumi
Proceedings of International Conference on Future Nuclear Systems (GLOBAL '99) (CD-ROM), p.8 - 0, 1999/00
no abstracts in English
Kunitomi, Kazuhiko; Tachibana, Yukio; *; Nakano, Masaaki*; Saikusa, Akio; Takeda, Takeshi; Iyoku, Tatsuo; ; Sawahata, Hiroaki; Okubo, Minoru; et al.
JAERI-Tech 97-040, 91 Pages, 1997/09
no abstracts in English
Suzuki, Yoshiyuki*; Shirai, Katsuyuki*; Yoshida, Yukari*; Mizui, Toshiyuki*; Kiyohara, Hiroki*; Noda, Shinei*; Ishizaki, Yasuki*; Ozawa, Seiji*; Nakano, Takashi*; Hamada, Nobuyuki*; et al.
no journal, ,
no abstracts in English
Suzuki, Yoshiyuki*; Shirai, Katsuyuki*; Mizui, Toshiyuki*; Hamada, Nobuyuki*; Noda, Shinei*; Funayama, Tomoo; Yoshida, Yukari*; Kobayashi, Yasuhiko; Shirao, Tomoaki*; Nakano, Takashi*
no journal, ,
no abstracts in English
Suzuki, Yoshiyuki*; Shirai, Katsuyuki*; Mizui, Toshiyuki*; Hamada, Nobuyuki*; Noda, Shinei*; Funayama, Tomoo; Yoshida, Yukari*; Kobayashi, Yasuhiko; Shirao, Tomoaki*; Nakano, Takashi*
no journal, ,
no abstracts in English
Shirai, Katsuyuki*; Suzuki, Yoshiyuki*; Mizui, Toshiyuki*; Hamada, Nobuyuki*; Noda, Shinei*; Funayama, Tomoo; Yoshida, Yukari*; Kobayashi, Yasuhiko; Shirao, Tomoaki*; Nakano, Takashi*
no journal, ,
no abstracts in English
