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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:27 Percentile:94.83(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:11 Percentile:59.93(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:28 Percentile:85.28(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
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Arai, Yoichi; Ogino, Hideki; Takeuchi, Masayuki; Kase, Takeshi; Koizumi, Tsutomu
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no abstracts in English
Ogino, Hideki; Arai, Yoichi; Takeuchi, Masayuki; Kase, Takeshi; Koizumi, Tsutomu
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no abstracts in English
Okamura, Nobuo; Ogino, Hideki; Arai, Yoichi; Kase, Takeshi; Koizumi, Tsutomu; Idesaki, Akira; Morishita, Norio; Oshima, Takeshi; Kojima, Takuji
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no abstracts in English
Ogino, Hideki; Takeuchi, Masayuki; Arai, Yoichi; Okamura, Nobuo; Washiya, Tadahiro; Kase, Takeshi; Koizumi, Tsutomu
no journal, ,
no abstracts in English
Arai, Yoichi; Ogino, Hideki; Onose, Tsutomu*; Koizumi, Satoshi*; Fujisaku, Kazuhiko*; Yokoyama, Yoshitomo*
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no abstracts in English
Ogino, Hideki; Okamura, Nobuo; Kase, Takeshi; Nakajima, Yasuo; Fujisaku, Kazuhiko*
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no abstracts in English
Arai, Yoichi; Ogino, Hideki; Onose, Tsutomu*; Kase, Takeshi; Nakajima, Yasuo
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Sano, Yuichi; Ogino, Hideki; Washiya, Tadahiro; Myochin, Munetaka
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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.
Arai, Yoichi; Ogino, Hideki; Onose, Tsutomu*; Hoshino, Takanori; Kase, Takeshi; Nakajima, Yasuo
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no abstracts in English
Hoshino, Takanori; Ogino, Hideki; Arai, Yoichi; Kase, Takeshi; Nakajima, Yasuo
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Ogino, Hideki; Nakajima, Yasuo; Kase, Takeshi; Koizumi, Satoshi*; Ishii, Hideyuki*
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no abstracts in English