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Suzuki, Hideya; Tsubata, Yasuhiro; Kurosawa, Tatsuya*; Sagawa, Hiroshi*; Matsumura, Tatsuro
Journal of Nuclear Science and Technology, 54(11), p.1163 - 1167, 2017/11
Times Cited Count：26 Percentile：93.3(Nuclear Science & Technology)A highly practical diamide-type extractant, which is an alkyl diamide amine with 2-ethylhexyl alkyl chains (ADAAM(EH)), was investigated for mutual separation of Am(III) and Cm(III). ADAAM(EH) is a multidentate ligand with one soft N-donor atom and two hard O-donor atoms in its central frame. This tridentate arrangement of donor atoms provides selective binding to Am(III) compared to that with Cm(III) in highly acidic media, resulting in separation factors of up to 5.5. A continuous liquid-liquid extraction and stripping test was conducted using a multistage countercurrent mixer-settler extractor with ADAAM(EH) in n-dodecane. In this test, separation of Am(III) and Cm(III) was achieved with very high yield.
Kibe, Satoshi; Fujisaku, Kazuhiko*; Sakamoto, Atsushi; Sano, Yuichi; Takeuchi, Masayuki; Suzuki, Hideya; Tsubata, Yasuhiro; Matsumura, Tatsuro
JAEA-Research 2016-024, 40 Pages, 2017/02
JAEA-Research-2016-024.pdf:6.73MB
The Japan Atomic Energy Agency has been developing some flowsheets with TDdDGA (N,N,N,Ntetradodecyldiglycolamide) extractant to recover MA (minor actinide) from raffinate. In this study, countercurrent experiments with the improved flowsheet, e.g. the addition of alcohol into the solvent for preventing the precipitation, were performed using miniature centrifugal contactors in order to compare the extraction/stripping behavior of each element with the mixer-settler type. As a result, no entrainments were observed and sufficient phase separation was achieved by centrifugal contactors without any abnormal fluid behavior, such as overflow. The extraction and stripping of Ln(III) which show the similar tendencies as MA could be achieved successfully, especially their stripping proceeded more efficiently in centrifugal contactors. This might be due to the increase in stripping rates by improving the flowsheet and to superior phase separation performance of centrifugal contactors.
Kibe, Satoshi; Fujisaku, Kazuhiko*; Ambai, Hiromu; Sakamoto, Atsushi; Sano, Yuichi; Takeuchi, Masayuki; Suzuki, Hideya; Tsubata, Yasuhiro; Matsumura, Tatsuro
JAEA-Research 2015-021, 40 Pages, 2016/02
JAEA-Research-2015-021.pdf:2.3MB
The flowsheet with TDdDGA extractant has been being developed for recovering MA from PUREX raffinate. In the previous study, the yields of MA and other elements in countercurrent extraction/stripping experiments using mixer-settlers were not enough for the target and it would be due to the insufficient phase (aqueous/organic) separation. In this study, we carried out countercurrent experiments with surrogate PUREX raffinate using centrifugal contactors which had superior phase separation ability, and evaluated the extraction/stripping behavior of each element. During the operation, abnormal fluid behavior, such as overflow and entrainment, was not observed, and sufficient phase separation was achieved by centrifugal contactors. Extraction behavior of lanthanides was similar to that in mixer-settlers, but their stripping efficiencies decreased. This would be due to shorter residence time in mixing zone.
Ban, Yasutoshi; Asakura, Toshihide; Morita, Yasuji
Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 5 Pages, 2005/10
An idea for controlling Np behavior in the Purex process is that Np(VI) extracted by TBP is selectively reduced to Np(V) by salt-free reagents and separated from U and Pu. Allylhydrazine is expected as a selective Np(VI) reductant from a view point of reduction rates for Np(VI) and Pu(IV). To confirm the applicability of allylhydrazine, a continuous counter-current back-extraction test of Np(VI) has been carried out using a miniature mixer-settler that consists of two steps: U-Pu recovery (3 stages) and Np separation (4 stages). Experimental results show that at least 90% of Np in feed are back-extracted and separated from U and Pu, therefore, it is confirmed that allylhydrazine is expected to be a selective salt-free reductant of Np(VI).
Imaizumi, Hirobumi; Ban, Yasutoshi; Sato, Makoto; Asakura, Toshihide; Morita, Yasuji
JAERI-Research 2005-025, 94 Pages, 2005/09
JAERI-Research-2005-025.pdf:13.61MB
Washing properties of n-butylamine compounds, which are decomposable by burning or electrolysis, for dibutylphosphoric acid (DBP) and Zr in real and simulated degraded solvents have been investigated. In experiments with simulated degraded solvents, basic properties of n-butylamine compounds for washing DBP and Zr were examined and optimum condition was obtained. It was confirmed from the simulated degraded solvent washing tests that 0.25 mol/dm
n-butylamine oxalate of pH 2 could effectively remove Zr from the degraded solvent and the solution of pH 4 was effective for DBP, 95% removal of Zr and DBP were obtained by batch washing. The validity of n-butylamine as a degraded solvent wash reagent was shown by the washing test for real degraded solvent that was performed by continuous counter current flow using a miniature mixer-settler. The present study was carried out as a part of the joint study "Research and Development of Process Elements in an Advanced Aqueous Reprocessing" between Japan Nuclear Cycle Development Institute and JAERI.
Yamaguchi, Isoo*; Suzuki, Shinichi; Sasaki, Yuji; Yamagishi, Isao; Matsumura, Tatsuro; Kimura, Takaumi
JAERI-Tech 2005-037, 56 Pages, 2005/07
JAERI-Tech-2005-037.pdf:2.31MB
For the development of the reprocessing of spent nuclear fuels, the solvent extraction using the mixer-settler equipment is greatly available. This method has the advantages of the treatment of the large mass of materials and continuous operations. In case of the application of the mixer-settler devise, the precise calculation using the distribution ratio of metals in order to determine the metal concentration at each stage is indispensable. This calculation is performed in the development of ARTIST process. The metal concentration in each stage of ARTIST process is calculated by the simulation using excel software equipped with counter-current equations. This method is not taken into consideration of the change of acid concentration, therefore, we developed the new method to calculate the metal concentration even after acidity change. This method can calculate not only the metal concentration at each extraction step but also at each stage of mixer-settler. Using this calculation, we evaluated the optimum condition of solvent extraction in ARTIST process.
Hotoku, Shinobu; Asakura, Toshihide; Mineo, Hideaki; Uchiyama, Gunzo
Journal of Nuclear Science and Technology, 39(Suppl.3), p.313 - 316, 2002/11
no abstracts in English
Uchiyama, Gunzo; Kihara, Takehiro; Hotoku, Shinobu; Fujine, Sachio; Maeda, Mitsuru
Radiochimica Acta, 81(1), p.29 - 32, 1998/00
no abstracts in English
Uchiyama, Gunzo; Fujine, Sachio; Maeda, Mitsuru; Sugikawa, Susumu; Tsujino, Takeshi
Solvent Extr. Ion Exch., 13(1), p.59 - 82, 1995/00
Times Cited Count：1 Percentile：13.34(Chemistry, Multidisciplinary)no abstracts in English
Maeda, Mitsuru; Fujine, Sachio; Uchiyama, Gunzo; *; *; ; *; *
Solvent Extraction in the Process Industries, Vol. 3, p.1517 - 1523, 1993/00
no abstracts in English
Maeda, Mitsuru; Fujine, Sachio; *; *
Transactions of the American Nuclear Society, 66, p.78 - 80, 1992/11
no abstracts in English
Uchiyama, Gunzo; Hotoku, Shinobu; Kihara, Takehiro; Fujine, Sachio; Maeda, Mitsuru
Solvent Extraction 1990, Part A, p.675 - 680, 1992/00
no abstracts in English
Fujine, Sachio; M.Kluth*; J.Lamla*; H.Goldacker*
Proc. of the Symp. on Solvent Extraction 1989, p.141 - 146, 1989/00
no abstracts in English
M.Y.Ballinger*; P.C.Owczarski*; ; ; S.Jordan*; W.Lindner*
Nuclear Technology, 81, p.278 - 292, 1988/00
Times Cited Count：13 Percentile：76.29(Nuclear Science & Technology)no abstracts in English
; ; ; *
JAERI-M 86-168, 90 Pages, 1986/11
no abstracts in English
Sano, Yuichi; Kibe, Satoshi; Sakamoto, Atsushi; Takeuchi, Masayuki; Suzuki, Hideya; Tsubata, Yasuhiro; Matsumura, Tatsuro
no journal, ,
The flowsheet with TDdDGA extractant for recovering MA(III) from PUREX raffinate was evaluated by counter-current trials with surrogate PUREX raffinate using mixer-settlers and centrifugal contactors. The extraction and back-extraction of Ln(III) which show the similar tendencies as MA(III) could be achieved successfully, especially their back-extraction proceeded more efficiently in centrifugal contactors, which might be due to superior phase separation performance of centrifugal contactors.
and Cm using a high-performance ligandSuzuki, Hideya; Tsubata, Yasuhiro; Toigawa, Tomohiro; Matsumura, Tatsuro
no journal, ,
The separation of minor actinide (MA) from HLLW is an important task in the partitioning and transmutation. After MA are separated from HLLW, the mutual separation of Am and Cm (Am/Cm separation) can be conducted. A highly practical reagent, called alkyl diamide amine (ADAAM), was developed. ADAAM gives the maximum separation factor up to 5.5. A continuous extraction test was conducted using a multistage countercurrent mixer-settler extractor with ADAAM in n-dodecane. Separation of Am and Cm was demonstrated in very high yield.
Tsubata, Yasuhiro
no journal, ,
Various solvent extraction processes, such as PUREX for U-Pu recovery, minor actinides recovery, fission products separation, have been studied in JAEA. We developed the PARC program for simulation of these processes. In this presentation, mathematical models of mass transfer and chemical reactions in the PARC are described.
