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Watanabe, So; Senzaki, Tatsuya; Shibata, Atsuhiro; Nomura, Kazunori; Takeuchi, Masayuki; Nakatani, Kiyoharu*; Matsuura, Haruaki*; Horiuchi, Yusuke*; Arai, Tsuyoshi*
Journal of Radioanalytical and Nuclear Chemistry, 322(3), p.1273 - 1277, 2019/12
Times Cited Count：4 Percentile：31.89(Chemistry, Analytical)
-P adsorbent for MA(III) recoveryKofuji, Hirohide; Watanabe, So; Takeuchi, Masayuki; Suzuki, Hideya; Matsumura, Tatsuro; Shiwaku, Hideaki; Yaita, Tsuyoshi
Progress in Nuclear Science and Technology (Internet), 5, p.61 - 65, 2018/11
Abe, Ryoji*; Nagoshi, Kohei*; Arai, Tsuyoshi*; Watanabe, So; Sano, Yuichi; Matsuura, Haruaki*; Takagi, Hideaki*; Shimizu, Nobutaka*; Koka, Masashi*; Sato, Takahiro*
Nuclear Instruments and Methods in Physics Research B, 404, p.173 - 178, 2017/08
Times Cited Count：5 Percentile：44.54(Instruments & Instrumentation)Takeuchi, Masayuki; Sano, Yuichi; Watanabe, So; Nakahara, Masaumi; Aihara, Haruka; Kofuji, Hirohide; Koizumi, Tsutomu; Mizuno, Tomoyasu
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 6 Pages, 2017/04
Watanabe, So; Nomura, Kazunori; Kitawaki, Shinichi; Shibata, Atsuhiro; Kofuji, Hirohide; Sano, Yuichi; Takeuchi, Masayuki
Procedia Chemistry, 21, p.101 - 108, 2016/12
Times Cited Count：14 Percentile：99.14(Chemistry, Inorganic & Nuclear)Sato, Takahiro; Yokoyama, Akihito; Kitamura, Akane; Okubo, Takeru; Ishii, Yasuyuki; Takahatake, Yoko; Watanabe, So; Koma, Yoshikazu; Kada, Wataru*
Nuclear Instruments and Methods in Physics Research B, 371, p.419 - 423, 2016/03
Times Cited Count：7 Percentile：55.03(Instruments & Instrumentation)Watanabe, So; Sano, Yuichi; Kofuji, Hirohide; Takeuchi, Masayuki; Koizumi, Tsutomu
NEA/NSC/R(2015)2 (Internet), p.338 - 344, 2015/06
Tolmachyov, S.; Kuwabara, Jun*; Noguchi, Hiroshi
Journal of Radioanalytical and Nuclear Chemistry, 261(1), p.125 - 131, 2004/07
Times Cited Count：23 Percentile：80.21(Chemistry, Analytical)A method based on flow injection extraction chromatography coupled with on-line ICP-MS (FI-EC-ICPMS) for simultaneous thorium and uranium determination in human body fluids (urine and blood) has been developed and validated. By using extraction chromatography, the limits of detection for 
Th, 
U and 
U were achieved 0.06 ng l
, 0.0014 ng l and 0.05 ng l, respectively. The FI-EC-ICPMS method accuracy was 102.4% and 101.5% with overall precision (RSDmax at 95% CI) of 5.3% and 4.9% for Th and U, respectively. The U/U atom ratio is measured with 1.8% precision. The technique was employed for simultaneous thorium and uranium analyses in human urine and blood samples after microwave digestion.
Hoshi, Harutaka*; Wei, Y.*; Kumagai, Mikio*; Asakura, Toshihide; Uchiyama, Gunzo*
Journal of Nuclear Science and Technology, 39(Suppl.3), p.874 - 877, 2002/11
To facilitate the management of high-level liquid waste (HLLW) and minimize its long-term radiological risk in geologic disposal, we have proposed an advanced partitioning process by extraction chromatography using a minimal organic solvent and compact equipment to separate long-lived minor actinides (MA) and specific fission products (FP) such as Zr and Mo from nitrate acidic HLLW solution. Novel silica-based extraction-resin for elemental groups separation was prepared by impregnating CMPO (octyl(phenyl)-N, N-diisobutylcarbamoylmethylphosphine oxide) into a macro-reticular styrene-divinylbenzene copolymer immobilized in porous silica particles with a diameter of 50 
m (SiO-P). Separation experiments for simulated HLLW solutions containing a trace amount of 
Am (III) and macro amounts of typical FP elements were carried out by column chromatography. It was found that the elements in the simulated HLLW were successfully separated to the following three groups: Cs-Sr-Rh-Ru, Pd-Ln-Am and Zr-Mo.
Usuda, Shigekazu; Abe, Hitoshi; Tachimori, Shoichi; Takeishi, Hideyo; *
Solvent Extraction 1990, p.717 - 722, 1992/00
no abstracts in English
;
Journal of Radioanalytical Chemistry, 36, p.133 - 144, 1977/00
no abstracts in English
;
Journal of Radioanalytical Chemistry, 20(2), p.455 - 462, 1974/02
no abstracts in English
Kofuji, Hirohide; Watanabe, So; Goto, Ichiro; Oriuchi, Akio; Takeuchi, Masayuki; Kobayashi, Hidekazu; Sasage, Kenichi
no journal, ,
Vitrification procedure for the extraction chromatography using porous silica covered with extractant were examined. In this method, it was expected that minor actinide (MA) were separated from high level radioactive liquid waste using extractant CMPO and/or HDEHP. In this study, vitrified adsorbent with simulated high level liquid waste were prepared and evaluated from some viewpoints of high level waste form properties. As the results, selected adsorbent were generally well vitrified and had enough chemical durability.
Takeuchi, Masayuki; Watanabe, So; Takahatake, Yoko; Sato, Takahiro; Arai, Tsuyoshi*
no journal, ,
no abstracts in English
Kofuji, Hirohide; Watanabe, So; Goto, Ichiro; Oriuchi, Akio; Takeuchi, Masayuki; Kobayashi, Hidekazu; Sasage, Kenichi
no journal, ,
Vitrification procedure for extraction chromatography using porous silica particles covered with extractant was investigated. In this method, minor actinides (MAs) were separated from high-level radioactive liquid waste by extractant CMPO and/or HDEHP. In this study, thermal degradation behavior and vitrification properties were evaluated from the viewpoints of high-level wasteform properties using porous silica adsorbent impregnated with extractant CMPO and HDEHP. As the results of various experiments, suitable vitrification procedure for MA/RE adsorbents was clarified and selected adsorbent was generally well-vitrified and had enough chemical durability.
Watanabe, So; Senzaki, Tatsuya; Shibata, Atsuhiro; Nomura, Kazunori; Takeuchi, Masayuki; Nakatani, Kiyoharu*; Matsuura, Haruaki*; Horiuchi, Yusuke*; Arai, Tsuyoshi*
no journal, ,
no abstracts in English
-P for Am/Cm Recovery from genuine HLLWSato, Daisuke; Watanabe, So; Arai, Yoichi; Nakamura, Masahiro; Arai, Tsuyoshi*; Sano, Yuichi; Shibata, Atsuhiro; Takeuchi, Masayuki
no journal, ,
Saito, Madoka*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Naruse, Atsuki*; Tsukahara, Takehiko*
no journal, ,
The sludge contained uranium generated production of nuclear fuel has been storage. The sludge is immersed in some kinds of solution. After immersion, uranium is recovered from the solution. Solvent extraction method, extraction chromatography and gelling extraction method were conducted on uranyl nitrate solution using monoamide extractant to compare on amount of waste and running cost on each methods. The gelling extraction method was superior to other two methods.
