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Kitagaki, Toru; Ikeuchi, Hirotomo; Yano, Kimihiko; Ogino, Hideki; Haquet, J.-F.*; Brissonneau, L.*; Tormos, B.*; Piluso, P.*; Washiya, Tadahiro
Progress in Nuclear Science and Technology (Internet), 5, p.217 - 220, 2018/11
Kitagaki, Toru; Yano, Kimihiko; Ogino, Hideki; Washiya, Tadahiro
Journal of Nuclear Materials, 486, p.206 - 215, 2017/04
Times Cited Count：34 Percentile：94.96(Materials Science, Multidisciplinary)Koma, Yoshikazu; Ogino, Hideki; Sakamoto, Atsushi; Nakabayashi, Hiroki; Shibata, Atsuhiro; Nakahara, Masaumi; Washiya, Tadahiro
Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 6 Pages, 2011/12
Arai, Yoichi; Ogino, Hideki; Takeuchi, Masayuki; Kase, Takeshi; Nakajima, Yasuo
Proceedings in Radiochemistry, 1(1), p.71 - 74, 2011/09
Solvent cleanup method using activated alumina was discussed in this study. This method was one of candidate to remove TBP/
-dodecane degradation products. The degradation sample of 30% TBP/-dodecane was prepared by irradiation (1.6 MGy) using 
Co 
-source. The absorbed dose for sample was almost 1.6 MGy. The degradation products were qualitatively analyzed by gas chromatography-mass spectrometer (GC-MS). After the irradiation, solvent cleanup was performed by activated alumina and the cleanup using alumina was examined by phase separation test with 3M HNO
. As the result, it was found that hexane and long-chain alcohols were mainly generated as the n-dodecane degradation products by irradiation, and almost 70% of the TBP/-dodecane degradation products were removed and the phase separation performance were improved by the cleanup using activated alumina.
Takeuchi, Masayuki; Ogino, Hideki; Nakabayashi, Hiroki; Arai, Yoichi; Washiya, Tadahiro; Kase, Takeshi; Nakajima, Yasuo
Journal of Nuclear Science and Technology, 46(3), p.217 - 225, 2009/03
Times Cited Count：12 Percentile：61.38(Nuclear Science & Technology)Okamura, Nobuo; Takeuchi, Masayuki; Ogino, Hideki; Kase, Takeshi; Koizumi, Tsutomu
Proceedings of International Conference on Advanced Nuclear Fuel Cycles and Systems (Global 2007) (CD-ROM), p.1070 - 1075, 2007/09
no abstracts in English
Washiya, Tadahiro; Takeuchi, Masayuki; Ogino, Hideki; Aose, Shinichi
Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6 Pages, 2005/10
Japan Nuclear Cycle Development Institute (JNC) has been developing centrifugal contactors which are compact and high performance for solvent extraction process in industrial reprocessing plant. Centrifugal contactor has some advantages which are more compact, smaller holdup volume and higher separation performance than conventional contactor such as mixer-settler or pulse column and contributes to economic advantage and reduction of solvent waste. In addition, the compact contactor is easy to manage the critical safety, and the operation ratio for fuel treatment can be improved because of short start-up and shut-down time. Since 1985, JNC stared the development of centrifugal contactor and then fundamental design was established for engineering scale hot test plant (RETF). The life time was evaluated by the result of endurance test, and system performance of multi-stages contactor on engineering scale was demonstrated. [1] In addition, several types of advanced contactors have been developing. This paper introduces the development of centrifugal contactor in JNC
Takata, Takeshi; Koma, Yoshikazu; Sato, Koji; Kamiya, Masayoshi; Shibata, Atsuhiro; Nomura, Kazunori; Ogino, Hideki; Koyama, Tomozo; Aose, Shinichi
Journal of Nuclear Science and Technology, 41(3), 307 Pages, 2004/00
Times Cited Count：29 Percentile：84.70(Nuclear Science & Technology)The design study of aqueous reprocessing system has been progressed for the feasibility study on commercialized fast reactor cycle systems. Based on the PUREX process,an aqueous reprocessing process with the addition of a uranium crystallization step and
Washiya, Tadahiro; Ogino, Hideki; Takeuchi, Masayuki; Suganuma, T.; Aose, Shinichi
Saikuru Kiko Giho, (21), p.23 - 32, 2003/00
None
Okamura, Nobuo; Ogino, Hideki; Arai, Yoichi; Kase, Takeshi; Koizumi, Tsutomu; Idesaki, Akira; Morishita, Norio; Oshima, Takeshi; Kojima, Takuji
no journal, ,
no abstracts in English
Ogino, Hideki; Nakajima, Yasuo; Kase, Takeshi; Koizumi, Satoshi*; Ishii, Hideyuki*
no journal, ,
no abstracts in English
Sano, Yuichi; Ogino, Hideki; Washiya, Tadahiro; Myochin, Munetaka
no journal, ,
In the FaCT Project, JAEA has been working on the improvement of solvent extraction for U-Pu-Np co-recovery as a part of the advanced aqueous reprocessing process (NEXT process) development. In the process development, the appropriate flowsheet condition was indicated for the efficient Np co-extraction with U and Pu, and their sufficient co-stripping. On the experiments with the engineering-scale centrifugal contactors, excellent extraction and stripping performances were obtained. In addition, the high durability of the centrifugal contactor using the magnetic bearing was confirmed.
Hoshino, Takanori; Ogino, Hideki; Arai, Yoichi; Kase, Takeshi; Nakajima, Yasuo
no journal, ,
no abstracts in English
Kunii, Kanako*; Misumi, Ryuta*; Nishi, Kazuhiko*; Kaminoyama, Meguru*; Hirano, Hiroyasu; Ogino, Hideki; Sano, Yuichi
no journal, ,
The flow patterns at 1750 and 3500 rpm of a rotor speed were compared each other. In both cases, the liquid is flowing along a rotational direction of the rotor in the region surrounded by two vanes on the vessel bottom and the vessel wall, and then the liquid goes into the separation zone in the rotor. At lower speed, the mean velocities are roughly proportional to flow rates. At higher speed, the liquid is separated into two regions in the height direction, that is, one of them is near the vanes and another is around a lower side of the rotor. The mean velocities around the vessel bottom are not proportional to flow rates. The reason is inferred that the liquid fed in the vessel takes a shortcut and goes into the rotor instead of passing through between two vanes.
Ogino, Hideki; Arai, Yoichi; Takeuchi, Masayuki; Kase, Takeshi; Koizumi, Tsutomu
no journal, ,
no abstracts in English
Misumi, Ryuta*; Todoroki, Kei*; Nishi, Kazuhiko*; Kaminoyama, Meguru*; Sano, Yuichi; Sakamoto, Atsushi; Ogino, Hideki; Hirano, Hiroyasu
no journal, ,
Fluid dynamic in two different scales of ACC were analyzed under different rotor speeds and flowrate by PIV measurements.
Ogino, Hideki; Okamura, Nobuo; Kase, Takeshi; Nakajima, Yasuo; Fujisaku, Kazuhiko*
no journal, ,
no abstracts in English
Ambai, Hiromu; Sano, Yuichi; Takeuchi, Masayuki; Sakauchi, Nobuyuki; Hoshi, Masayuki; Ogino, Hideki; Aose, Shinichi
no journal, ,
As a part of studies on corrosion resistance of storage tanks for flock generated in the coagulation process for radioactive contaminated water from the Fukushima Daiichi Nuclear Power Plant, several corrosion tests considering the radiation and the contact with flock were carried out with SS400 in the settling condition. Average corrosion rates of SS400 were around 0.1mm/y and severe corrosion including local corrosion was not observed.
Sakamoto, Atsushi; Sano, Yuichi; Ogino, Hideki; Hirano, Hiroyasu; Todoroki, Kei*; Misumi, Ryuta*; Nishi, Kazuhiko*; Kaminoyama, Meguru*
no journal, ,
no abstracts in English
Hoshino, Takanori; Sato, Takashi; Sano, Yuichi; Ogino, Hideki; Aose, Shinichi
no journal, ,
no abstracts in English
