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Toh, Yosuke; Ozu, Akira; Tsuchiya, Harufumi; Furutaka, Kazuyoshi; Kitatani, Fumito; Komeda, Masao; Maeda, Makoto; Koizumi, Mitsuo
Proceedings of INMM & ESARDA Joint Virtual Annual Meeting (Internet), 8 Pages, 2021/08
Furutaka, Kazuyoshi; Ozu, Akira; Toh, Yosuke
Proceedings of INMM & ESARDA Joint Virtual Annual Meeting (Internet), 9 Pages, 2021/08
Rossi, F.; Bogucarska, T.*; Koizumi, Mitsuo; Lee, H.-J.; Pedersen, B.*; Rodriguez, D.; Takahashi, Tone; Varasano, G.*
Nuclear Instruments and Methods in Physics Research A, 977, p.164306_1 - 164306_7, 2020/10
Times Cited Count：4 Percentile：36.4(Instruments & Instrumentation)Koizumi, Mitsuo
Proceedings of 41st ESARDA Annual Meeting (Internet), p.260 - 267, 2019/05
Koizumi, Mitsuo; Harada, Hideo; Schillebeeckx, P.*
Nihon Genshiryoku Gakkai-Shi ATOMO
, 58(9), p.563 - 567, 2016/09
no abstracts in English
Surugaya, Naoki; Hiyama, Toshiaki; Verbruggen, A.*; Wellum, R.*
Analytical Sciences, 24(2), p.247 - 252, 2008/02
Times Cited Count：7 Percentile：23.3(Chemistry, Analytical)A stable solid spike for the measurement of uranium and plutonium content in nitric acid solutions of spent nuclear fuel by isotope dilution mass spectrometry has been prepared at the European Commission Institute for Reference Materials and Measurements in Belgium. The spike contains about 50 mg of uranium with a 19.838% 
U enrichment and 2 mg of plutonium with a 97.766% 
Pu abundance in each individual ampoule. The dried materials were covered with a thin film of cellulose acetate butyrate as a protective organic stabilizer to resist shocks encountered during transportation and to eliminate flaking-off during long-term storage. It was found that the cellulose acetate butyrate has good characteristics, maintaining a thin film for a long time, but readily dissolving on heating with nitric acid solution. The solid spike containing cellulose acetate butyrate was certified as reference material IRMM-1027f with certified quantities: U and Pu amounts and uranium and plutonium amount ratios, and was validated by analyzing spent fuel dissolver solutions of the Tokai reprocessing plant in Japan.
Okubo, Ayako; Mayer, K.*
no journal, ,
Under the collaboration between EC-JRC and JAEA, the in-situ age dating method was subject to joint validation, and six different uranium materialswere used for this purpose. The age dating result by in-situ isotope method was consistent with known production dates of the respective samples. The uncertainty evaluation according to GUM for the in-situ isotope method indicates that the measured 
Th/
Th ratio provides the highest contribution. The accuracy of in-situ isotope method can be improved by higher precision in Th/Th measurement.
Furutaka, Kazuyoshi; Ozu, Akira; Toh, Yosuke
no journal, ,
no abstracts in English
Tsuchiya, Harufumi; Kitatani, Fumito; Toh, Yosuke
no journal, ,
no abstracts in English
Toh, Yosuke; Tsuchiya, Harufumi; Ozu, Akira; Furutaka, Kazuyoshi; Kitatani, Fumito; Komeda, Masao; Maeda, Makoto; Koizumi, Mitsuo
no journal, ,
no abstracts in English
