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-rays after neutron capture by 
La for a T-violation searchOkudaira, Takuya; Shimizu, Hirohiko*; Kitaguchi, Masaaki*; Hirota, Katsuya*; Haddock, C. C.*; Ito, Ikuya*; Yamamoto, Tomoki*; Endo, Shunsuke*; Ishizaki, Kohei*; Sato, Takumi*; et al.
EPJ Web of Conferences, 219, p.09001_1 - 09001_6, 2019/12
Parity violating effects enhanced by up to 10
times have been observed in several neutron induced compound nuclei. There is a theoretical prediction that time reversal (T) violating effects can also be enhanced in these nuclei implying that T-violation can be searched for by making very sensitive measurements. However, the enhancement factor has not yet been measured in all nuclei. The angular distribution of the (n,) reaction was measured with La by using a germanium detector assembly at J-PARC, and the enhancement factor was obtained. From the result, the measurement time to achieve the most sensitive T-violation search was estimated as 1.4 days, and a 40% polarized La target and a 70% polarized 
He spin filter whose thickness is 70 atm
cm are needed. Therefore high quality He spin filter is developed in JAEA. The measurement result of the (n,) reaction at J-PARC and the development status of the He spin filter will be presented.
Yamagishi, Isao; Odakura, Makoto; Ichige, Yoshiaki; Kuroha, Mitsuhiko; Takano, Masahide; Akabori, Mitsuo; Yoshioka, Masahiro*
Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.1113 - 1119, 2015/09
The characteristics of insoluble residues in fine suspension at the Rokkasho Reprocessing Plant were analyzed. The insoluble residues were washed with oxalic acid solution to dissolve zirconium molybdate residues. XRD profiles of unwashed residues showed the presence of a noble metal alloy, zirconium molybdate, and zirconia, but zirconium molybdate was not found after washing. More than 50% of the Sb-125 and Pu in thee residues was washed out as well. The noble metal alloy composed of Mo, Tc, Ru, Rh, and Pd occupied more than 90% of the total weight of 12 elements (Ca, Cr, Fe, Ni, Zr, Mo, Tc, Ru, Rh, Pd, Te, and U) found in the residues. In consideration of the chemical forms of 12 elements, the alloy-to-residue weight ratio was evaluated to be 64% and 78% with and without 18% of an unknown component, respectively.
Yoshioka, Kenichi*; Kikuchi, Tsukasa*; Gunji, Satoshi*; Kumanomido, Hironori*; Mitsuhashi, Ishi*; Umano, Takuya*; Yamaoka, Mitsuaki*; Okajima, Shigeaki; Fukushima, Masahiro; Nagaya, Yasunobu; et al.
Journal of Nuclear Science and Technology, 52(2), p.282 - 293, 2015/02
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)We have developed a void reactivity evaluation method by using modified conversion ratio measurements in a light water reactor (LWR) critical lattice. Assembly-wise void reactivity is evaluated from the "finite neutron multiplication factor", 
, deduced from the modified conversion ratio of each fuel rod. The distributions of modified conversion ratio and on a reduced-moderation LWR lattice, for which the improvement of negative void reactivity is a serious issue, were measured. Measured values were analyzed with a continuous-energy Monte Carlo method. The measurements and analyses agreed within the measurement uncertainty. The developed method is useful for validating the nuclear design methodology concerning void reactivity.
Yoshioka, Kenichi*; Kikuchi, Tsukasa*; Gunji, Satoshi*; Kumanomido, Hironori*; Mitsuhashi, Ishi*; Umano, Takuya*; Yamaoka, Mitsuaki*; Okajima, Shigeaki; Fukushima, Masahiro; Nagaya, Yasunobu; et al.
Journal of Nuclear Science and Technology, 50(6), p.606 - 614, 2013/06
Times Cited Count：1 Percentile：10.69(Nuclear Science & Technology)We have developed an intra-pellet neutron flux and conversion ratio distribution measurement method. A foil activation method with special foils was used for the neutron flux distribution measurement. A -ray spectrum analysis method with special collimators was used for the conversion ratio distribution measurement. Using the developed methods, intra-pellet neutron flux distributions and conversion ratio distributions were measured in critical experiments on a reduced-moderation LWR. Measured values were analyzed with a deterministic method and a Monte Carlo method. The neutron flux distribution measurements and analyses agreed within the range of 1% to 2%. The conversion ratio distribution measurements and analyses were consistent with each other. We found that the measurement methods are useful for the validation of neutron behavior in a fuel pellet, which is known as micro reactor physics.
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：64 Percentile：87.31(Physics, Applied)no abstracts in English
Igarashi, Hiroshi; Saito, Shinichi*; Takahashi, Takeshi; Yoshioka, Masahiro
PNC TN8600 90-010, 72 Pages, 1990/09
no abstracts in English
Niwa, Hajime; Kurisaka, Kenichi; Sato, Ikken; Tobita, Yoshiharu; Kamiyama, Kenji; Yamano, Hidemasa; Miyahara, Shinya; Ohno, Shuji; Seino, Hiroshi; Ishikawa, Hiroyasu; et al.
no journal, ,
In order to develop the core damage evaluation technology (level 2 PSA) for sodium-cooled fast reactors, we develop the new analysis codes of post accident material relocation phase and of ex-vessel events, and we develop the technical bases that is necessary for level 2 PSA. In this presentation, summary and scope of the entire study is introduced as a part of the 4 series presentations.
Nakai, Ryodai; Kurisaka, Kenichi; Sato, Ikken; Tobita, Yoshiharu; Kamiyama, Kenji; Yamano, Hidemasa; Miyahara, Shinya; Ohno, Shuji; Seino, Hiroshi; Ishikawa, Hiroyasu; et al.
no journal, ,
To develop a core damage evaluation technology (level-2 PSA) in sodium-cooled fast reactors, a new analysis method is developed for core-material relocation phase and internal containment vessel event. This study also develop technical basis necessary for the level-2 PSA.
Iida, Yasuhiko*; Paudyal, P.*; Yoshioka, Hiroki*; Tominaga, Hideyuki*; Hanaoka, Hirofumi*; Zhang, S.*; Hosaka, Masahiro*; Takeuchi, Toshiyuki*; Tobita, Seiji*; Watanabe, Satoshi; et al.
no journal, ,
no abstracts in English
Takano, Masahide; Yamagishi, Isao; Akabori, Mitsuo; Minato, Kazuo; Fukui, Toshiki*; Yoshioka, Masahiro*
no journal, ,
no abstracts in English
Takano, Masahide; Yamagishi, Isao; Akabori, Mitsuo; Minato, Kazuo; Yoshioka, Masahiro*; Ochi, Eiji*; Fukui, Toshiki*; Komamine, Satoshi*
no journal, ,
no abstracts in English
Yamagishi, Isao; Morita, Yasuji; Takano, Masahide; Akabori, Mitsuo; Minato, Kazuo; Fukui, Toshiki*; Yoshioka, Masahiro*
no journal, ,
no abstracts in English
Minato, Kazuo; Komamine, Satoshi*; Fukui, Toshiki*; Ochi, Eiji*; Yoshioka, Masahiro*
no journal, ,
Characteristics of the fine produced during the reprocessing of the spent fuel in the Rokkasho Reprocessing Plant are inevitable data to understand the behavior of the fine in the glass melter. It is also necessary to obtain the characteristic data of the fine to judge the validity of vitrification tests with simulated fine in KMOC facility. The property measurements and chemical reaction tests with simulated fine are valuable to obtain fundamental data that is necessary for the development of a new type of glass melter. With these objectives, the fine was transported from the Rokkasho Reprocessing Plant to the Tokai Research Center of the Japan Atomic Energy Agency and the fine and simulated fine were characterized.
Odakura, Makoto; Ichige, Yoshiaki; Kuroha, Mitsuhiko; Yamagishi, Isao; Ishihara, Miho; Fukui, Toshiki*; Yoshioka, Masahiro*
no journal, ,
no abstracts in English
Yamagishi, Isao; Morita, Yasuji; Takano, Masahide; Akabori, Mitsuo; Minato, Kazuo; Fukui, Toshiki*; Yoshioka, Masahiro*
no journal, ,
no abstracts in English
Akabori, Mitsuo; Takano, Masahide; Yamagishi, Isao; Minato, Kazuo; Yoshioka, Masahiro*; Ochi, Eiji*; Fukui, Toshiki*; Komamine, Satoshi*
no journal, ,
Properties of real insoluble residues generated at Rokkasho Reprocessing Plant were measured by using SEM/EPMA. The simulated insoluble residues were prepared by conventional powder metallurgy technique, and properties such as particle size were compared with those of real ones.
Yoshioka, Masahiro*; Fukui, Toshiki*; Miura, Nobuyuki; Tsukada, Takeshi*
no journal, ,
The basic research programs for the next generation vitrification technology, which are commissioned project from Ministry of Economy, Trade and Industry of Japan to IHI Corporation (IHI), Japan Nuclear Fuel Limited (JNFL), Japan Atomic Energy Agency (JAEA) and Central Research Institute of Electric Power Industry (CRIEPI), have been implemented from 2014 for developing the advanced vitrification technology of low level wastes and high level liquid wastes (HLLW). In these programs, the developmental works such as the high waste loading glass, the alternate glasses of current borosilicate glasses including glass-ceramics and the minor actinide adsorbent glasses have been entrusted with the above organizations.
Kobayashi, Kensuke*; Ooka, Tokunao*; Kanematsu, Manabu*; Suzuki, Hiroshi; Tateyama, Soichi*; Nagai, Tomoya*; Nishio, Yuhei*; Hirata, Yoshikazu*; Yoshioka, Masahiro*
no journal, ,
no abstracts in English
