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Minowa, Kazuki*; Watanabe, So; Nakase, Masahiko*; Takahatake, Yoko; Miyazaki, Yasunori; Ban, Yasutoshi; Matsuura, Haruaki*
Nuclear Instruments and Methods in Physics Research B, 556, p.165496_1 - 165496_6, 2024/11
Times Cited Count：0 Percentile：0.00(Instruments & Instrumentation)In this study, X-ray absorption near edge structure (XANES) spectral analysis and column experiments were used to verify the selectivity of rare earth (RE) ions by alkyl diamide amine (ADAAM) adsorbent. In addition, the interactions between the N atoms of ADAAM and RE ions were evaluated to determine whether any of the RE ions are a valid simulant for developing a mutual separation process for minor actinides (MAs) in highly radioactive liquid waste. It was confirmed that La and Ce interacted with the amine N atom of ADAAM and they showed a peak shift of the N-K edge XANES spectrum; this finding suggested that a soft interaction is an essential factor influencing ion selectivity. Therefore, the selection factor of RE ions by ADAAM adsorbent was similar to that of MAs. It was concluded that RE ions are reasonable species to simulate MAs.
Arai, Yoichi; Hasegawa, Kenta; Watanabe, So; Watanabe, Masayuki; Minowa, Kazuki*; Matsuura, Haruaki*; Hagura, Naoto*; Katsuki, Kenta*; Arai, Tsuyoshi*; Konishi, Yasuhiro*
Journal of Radioanalytical and Nuclear Chemistry, 333(7), p.3585 - 3593, 2024/07
Times Cited Count：1 Percentile：13.88(Chemistry, Analytical)Yamamoto, Yuri*; Minowa, Kazuki*; Takahatake, Yoko; Watanabe, So; Nakamura, Masahiro; Matsuura, Haruaki*
Electrochemistry (Internet), 92(4), p.043019_1 - 043019_4, 2024/04
Times Cited Count：0 Percentile：0.00(Electrochemistry)In the pyro-reprocessing of spent nuclear fuel, salt bath is normally used in several times, but at final moment, spent salt containing small amount of chloride nuclear fuel material is generated. In terms of managing nuclear fuel materials, it is desirable that the nuclear fuel materials should be recovered from the spent salt. We are proposing methods for recovering nuclear fuel materials using precipitation by oxide addition and distillation for reducing pressure techniques. In this study, we have focused on the behavior of manganese(II), which is one of the radioactivated products. As a result of experiments and thermodynamic simulation, it was found that manganese(II) is likely to be entrained in nuclear fuel materials. Therefore, it is necessary to add a step to separate manganese(II) from nuclear fuel materials.
Yamamoto, Yuri*; Yokoi, Yuki*; Minowa, Kazuki*; Takahatake, Yoko; Watanabe, So; Nakamura, Masahiro; Matsuura, Haruaki*
no journal, ,
no abstracts in English
Yamamoto, Yuri*; Yokoi, Yuki*; Minowa, Kazuki*; Takahatake, Yoko; Watanabe, So; Nakamura, Masahiro; Matsuura, Haruaki*
no journal, ,
no abstracts in English
Minowa, Kazuki
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no abstracts in English
Minowa, Kazuki*; Watanabe, So; Ban, Yasutoshi; Nakase, Masahiko*; Watanabe, Shinta*; Matsuura, Haruaki*
no journal, ,
no abstracts in English
Ouchi, Kazuki; Naito, Sho*; Hiruma, Yusuke*; Minowa, Kazuki*; Kitatsuji, Yoshihiro
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We attempted to downsize the pretreatment of separation process to reduce the risk of radiation exposure in radioactive waste analysis. The geometry (inner diameter and length) for separation was investigated to design a micro tube column packed with UTEVA resin as a selective solid-phase extractant for uranium. It was found that the uranium adsorption rate depended on the inner diameter and length, and the column volume could be downsized to 4 
L.
Yoshikawa, Masashi*; Minowa, Kazuki*; Matsuura, Haruaki*; Hasegawa, Kenta; Arai, Yoichi; Watanabe, So; Konishi, Yasuhiro*
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no abstracts in English
Yamamoto, Yuri*; Yokoi, Yuki*; Minowa, Kazuki*; Takahatake, Yoko; Watanabe, So; Nakamura, Masahiro; Matsuura, Haruaki*
no journal, ,
In the pyrochemical reprocessing of spent nuclear fuel, salt bath is normally used in several times, but at final moment, spent salt containing small amount of chloride nuclear fuel material is generated. In terms of managing nuclear fuel materials, it is desirable that the nuclear fuel materials should be recovered from the spent salt. We are proposing methods for recovering nuclear fuel materials using precipitation by oxide addition and distillation for reducing pressure techniques. In this study, we have focused on the behavior of Mn, Fe, Co, and Ni, which are representative radioactivated products. As a result of experiments and thermodynamic simulation, it was found that Mn Fe, Co, and Ni are likely to be entrained in nuclear fuel materials. Therefore, it is necessary to add a step to separate Mn, Fe, Co, and Ni from nuclear fuel materials.
Satou, Yukihiko; Sueki, Keisuke*; Matsuo, Kazuki*; Minowa, Haruka*; Yoshikawa, Hideki
no journal, ,
no abstracts in English
Sb and 
I in radioactive particles derived from FDNPPMatsuo, Kazuki*; Sueki, Keisuke*; Satou, Yukihiko; Yoshikawa, Hideki; Minowa, Haruka*; Sasa, Kimikazu*; Matsunaka, Tetsuya*; Matsumura, Masumi*; Takahashi, Tsutomu*; Sakaguchi, Aya*
no journal, ,
no abstracts in English
Sueki, Keisuke*; Matsuo, Kazuki*; Sasa, Kimikazu*; Satou, Yukihiko; Yoshikawa, Hideki; Minowa, Haruka*
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no abstracts in English
Hasegawa, Kenta; Arai, Yoichi; Watanabe, So; Watanabe, Masayuki; Matsuura, Haruaki*; Hagura, Naoto*; Minowa, Kazuki*; Konishi, Yasuhiro*
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