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Sano, Yuichi; Sakamoto, Atsushi; Kofuji, Hirohide; Takeuchi, Masayuki
Proceedings of 21st Pacific Basin Nuclear Conference (PBNC 2018) (USB Flash Drive), p.314 - 318, 2018/09
The effect of operational condition of the annular centrifugal contactor (ACC) on U extraction behavior was investigated by computational fluid dynamics (CFD) analysis considering mass transfer between aqueous and organic phases, and the calculation results were validated experimentally. The CFD analysis with ANSYS FLUENT was carried out using the Eulerian multi-fluid approach with a standard k- turbulence model. In order to calculate the droplet size of the dispersed phase and mass transfer between aqueous and organic phases, user-defined functions (UDF) were created. The changes of U extraction performance, i.e. U stage efficiency, with the rotor speed and the O/A ratio (= organic flowrate / aqueous flowrate) were calculated, and these showed a good agreement with experimental results.
Kudo, Atsunari; Kurabayashi, Kazuaki; Yanagibashi, Futoshi; Sasaki, Shunichi; Sato, Takehiko; Fujimoto, Ikuo; Obu, Tomoyuki
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 6 Pages, 2017/04
The Co-processing process is the extraction process to recover Pu/U mixed product solution with given Pu/U ratio for improving of nuclear proliferation resistance. In addition, Np is also recovered with U and Pu because Np is one of minor actinides and a long-lived radionuclide and Np has the extractability into TBP solvent. Development of its flowsheet achieves to decrease environmental effect of waste materials. The orientation of development about Co-processing process is to demonstrate of reprocessing the future spent fuels from a LWR, a LWR-MOX hybrid, and a FR-MOX with one cycle. We demonstrated by use of miniature reflux-type centrifugal contactors at the partitioning unit. The test conditions of the Pu/U ratio in the loaded solvents were 1%, 3%, and 5% considering the composition of spent fuels. We used the HAN as the reductant of Np (VI) for back extraction. The results of these tests were very good. We got the prospect of U, Pu, and Np Co-processing flowsheet.
Sakamoto, Atsushi; Sano, Yuichi; Takeuchi, Masayuki; Okamura, Nobuo; Koizumi, Kenji
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 5 Pages, 2015/05
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JNC TN9400 2000-034, 48 Pages, 2000/03
The study and the development to put FBR (Fast Breeder Reactor) to practical use have been doing. So many kinds of technologies are investigated to construct nuclear fuel recycle received to the society. The most important aim of reprocessing has been to extract U and Pu from spent fuels effectively, but, now, the demands for reprocessing are many kinds on nuclear fuel recycle system's construction. These need to be accepted sufficiently. The system that consists of electrolysis, extraction, with molten salt and melting metal, volatilization and condensation using the difference of vapor pressure is suggested, because, differently from LWR (Light Water Reactor), FBR can use the low decontamination factor's fuel. When the engineering scale plant is designed, the dry reprocessing has unsolved problems(ex. process flow) because of less demonstrative scale plants of the dry reprocessing than ones of the wet reprocessing. So the analysis and the estimation of mass balance that is most fundamental in the dry reprocessing system's design need to keep up with the system's alteration (to add new processes etc.) flexibly. This study aim is to develop the mass balance estimation code of dry reprocessing that satisfies the demand mentioned above.
Koga, Jiro*; Shinzato, Takushi*
JNC TJ8400 2000-054, 48 Pages, 2000/02
The "STELLA" which is a tool for simulation of dynamical systems applied to the numerical simulation of the behavior of minor constituent, such as hydrazoic acid, forming and extinguishing on the operation of reprocessing process. The concentration of hydrazoic acid forming by the reaction of nitrite and hydrazine were determined by use of STELLA after the determination of concentration of main constituents by MIXSET-X. The results from simulation is shown that the STELLA is applicable to the numerical simulation of the behavior of minor constituent.
Homma, Shunji*; Tajima, Yasunori*; Koga, Jiro*; Matsumoto, Shiro*
PNC TJ1609 97-001, 47 Pages, 1997/02
no abstracts in English
Morita, Yasuji; J.-P.Glatz*; Kubota, Masumitsu; L.Koch*; G.Pagliosa*; K.Roemer*; A.Nicholl*
Solvent Extr. Ion Exch., 14(3), p.385 - 400, 1996/00
Times Cited Count:87 Percentile:92.96(Chemistry, Multidisciplinary)no abstracts in English
Sakamoto, Atsushi; Takeuchi, Masayuki; Ogino, Hideki; Koizumi, Kenji; Sawahata, Osamu*; Sakamoto, Yukio*; Akutsu, Koichi*
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Arai, Yoichi; Takeuchi, Masayuki; Sakamoto, Atsushi; Ohata, Fumikazu; Okamura, Nobuo; Ogino, Hideki; Koizumi, Kenji
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Sakamoto, Atsushi; Sano, Yuichi; Takeuchi, Masayuki; Ito, Kazuyuki*; Sekita, Satoshi*; Sakamoto, Yukio*; Akutsu, Koichi*
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Sakamoto, Atsushi; Okamura, Nobuo; Sano, Yuichi; Takeuchi, Masayuki
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Kudo, Atsunari; Yanagibashi, Futoshi; Hoshi, Takahiro; Tada, Kazuhito; Sato, Takehiko; Fujimoto, Ikuo; Obu, Tomoyuki
no journal, ,
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Takeuchi, Masayuki; Sakamoto, Atsushi; Sano, Yuichi; Ito, Kazuyuki*; Sekita, Satoshi*; Sakamoto, Yukio*; Akutsu, Koichi*
no journal, ,
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Sakamoto, Atsushi; Sano, Yuichi; Takeuchi, Masayuki; Ito, Kazuyuki*; Sekita, Satoshi*; Sakamoto, Yukio*; Akutsu, Koichi*
no journal, ,
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Kibe, Satoshi; Fujisaku, Kazuhiko*; Sakamoto, Atsushi; Sano, Yuichi; Takeuchi, Masayuki; Suzuki, Hideya; Tsubata, Yasuhiro; Matsumura, Tatsuro
no journal, ,
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Kudo, Atsunari; Kurabayashi, Kazuaki; Yanagibashi, Futoshi; Sato, Takehiko; Fujimoto, Ikuo; Obu, Tomoyuki
no journal, ,
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Sakamoto, Atsushi; Sano, Yuichi; Takeuchi, Masayuki; Matsuura, Takanobu*; Sakamoto, Yukio*; Sekita, Satoshi*
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Kudo, Atsunari; Nagaoka, Shinichi; Kurabayashi, Kazuaki; Yanagibashi, Futoshi; Obu, Tomoyuki
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Sakamoto, Atsushi; Sano, Yuichi; Takeuchi, Masayuki; Watanabe, Masayuki; Koizumi, Kenji
no journal, ,
no abstracts in English