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Tc separation/concentration technology from 
Mo by (n, 
) methodFujita, Yoshitaka; Hu, X.*; Takeuchi, Tomoaki; Takeda, Ryoma; Fujihara, Yasuyuki*; Yoshinaga, Hisao*; Hori, Junichi*; Suzuki, Tatsuya*; Suematsu, Hisayuki*; Ide, Hiroshi
KURNS Progress Report 2022, P. 110, 2023/07
no abstracts in English
Nuclear Science and Engineering Center; Fuel Cycle Design Office; Plutonium Fuel Development Center; Nuclear Plant Innovation Promotion Office; Fast Reactor Cycle System Research and Development Center; J-PARC Center
JAEA-Review 2022-052, 342 Pages, 2023/02
JAEA-Review-2022-052.pdf:18.05MB
This report summarizes the current status and future plans of research and development (R&D) on partitioning and transmutation technology in Japan Atomic Energy Agency, focusing on the results during the 3rd Medium- to Long-term Plan period (FY 2015-2021). Regarding the partitioning technology, R&D of the solvent extraction method and the extraction chromatography method are described, and regarding the minor actinide containing fuel technology, R&D of the oxide fuel production using the simplified pellet method, the nitride fuel production using the external gelation method, and pyrochemical reprocessing of the nitride fuel were summarized. Regarding transmutation technology, R&D of technology using fast reactors and accelerator drive systems were summarized. Finally, the new facilities necessary for the future R&D were mentioned.
Mo/Tc generator by (n, ) method, 3Fujita, Yoshitaka; Seki, Misaki; Namekawa, Yoji*; Nishikata, Kaori; Daigo, Fumihisa; Ide, Hiroshi; Tsuchiya, Kunihiko; Sano, Tadafumi*; Fujihara, Yasuyuki*; Hori, Junichi*; et al.
KURNS Progress Report 2020, P. 136, 2021/08
no abstracts in English
Shimojo, Kojiro
Analytical Sciences, 34(12), p.1345 - 1346, 2018/12
Solvent extraction is one of the most effective analytical methods for separation, purification, and removal of target metal ions (e.g. valuable metal ions, toxic metal ions and radioactive fission products) from aqueous solutions containing various metal ions. In this paper, we introduce the papers related to (1) novel extractant, (2) ionic liquids and deep eutectic solvents, (3) new extractors, among papers on solvent extraction published between 2016 and 2018.
Morita, Yasuji; Yamagishi, Isao
JAEA-Research 2017-006, 27 Pages, 2017/06
JAEA-Research-2017-006.pdf:1.83MB
Separation of Pd by extraction with 5,8-diethyl-7-hydroxy-6-dodecanone oxime (DEHDO) was examined by batch and continuous tests for the purpose of developing Pd separation process. Batch extraction tests using n-dodecane solution of DEHDO revealed that Pd, Zr and Mo were extracted from simulated high-level radioactive liquid wastes (HLLW) and other elements were not, and also showed that the extraction rate was a little slow and a white precipitate appeared in the aqueous phase but its formation could be avoided by raising temperature. The extracted Pd was found to be back-extracted with sodium nitrite. In the continuous extraction tests with simulated HLLW without Zr and Mo, about 98% of Pd were extracted with DEHDO-n-dodecane and 95% of the extracted Pd were back-extracted with sodium nitrite and nitric acid. Continuous extraction test with simulated HLLW with Zr and Mo showed the possibility of the simultaneous separation of Pd and Mo by DEHDO extraction.
pellets for Mo-99 production, 3Ishida, Takuya; Suzuki, Yoshitaka; Nishikata, Kaori; Yonekawa, Minoru; Kato, Yoshiaki; Shibata, Akira; Kimura, Akihiro; Matsui, Yoshinori; Tsuchiya, Kunihiko; Sano, Tadafumi*; et al.
KURRI Progress Report 2015, P. 64, 2016/08
no abstracts in English
Tc solution from Mo to be obtained by (
) reaction; A Preliminary study using inactive Re instead of TcTanase, Masakazu*; Fujisaki, Saburo*; Ota, Akio*; Shiina, Takayuki*; Yamabayashi, Hisamichi*; Takeuchi, Nobuhiro*; Tsuchiya, Kunihiko; Kimura, Akihiro; Suzuki, Yoshitaka; Ishida, Takuya; et al.
Radioisotopes, 65(5), p.237 - 245, 2016/05
no abstracts in English
Usuda, Shigekazu
Dai-4-Pan Jikken Kagaku Kouza, 14; Kaku, Hoshasen, p.124 - 140, 1992/00
no abstracts in English
JAERI-M 8339, 89 Pages, 1979/07
no abstracts in English
; ; ; ; ; ;
JAERI-M 6958, 40 Pages, 1977/03
no abstracts in English
P by solvent extraction methodNihon Genshiryoku Gakkai-Shi, 10(1), p.2 - 6, 1968/00
no abstracts in English
Genshiryoku Hatsuden, 2(2), P. 9, 1958/00
no abstracts in English
Shimojo, Kojiro; Sugita, Tsuyoshi; Okamura, Hiroyuki; Naganawa, Hirochika
no journal, ,
Our group has studied solvent extraction as one of novel separation and analytical methods. We introduce three approaches (synthesis of novel extractant, improvement of extraction media, and development of extraction equipment) to progress solvent extraction systems. In this young meeting, we devote much effort to make graduate students understand our research and to recruit excellent young chemists.
Sasaki, Yuji; Tsubata, Yasuhiro; Morita, Keisuke; Shirasu, Noriko; Shimazaki, Shoma; Kitatsuji, Yoshihiro
no journal, ,
no abstracts in English
Tc from Mo for commercial productionShiina, Takayuki*; Tsuchiya, Kunihiko; Nagai, Yasuki; Morikawa, Yasumasa*; Takeuchi, Nobuhiro*
no journal, ,
According to statistical data reported by the Japan Radioisotope Association (JRIA) in 2014, the Mo/Tc generator and Tc injections (Tc labeled pharmaceuticals) continues to account for approximately 80% of the entire in-vivo supply in Japan. Furthermore, the number of Tc injection supplies is approximately four times larger than that of the Mo/Tc generator. Therefore, Chiyoda Technol Co. have performed a research and development (R&D) for the domestic production of Tc in cooperation with the Japan Atomic Energy Agency (JAEA) and FUJIFILM RI pharma Co., Ltd. to ensure a constant and reliable supply of Tc. CTC therefore has a plan to stably produce Tc from Mo, which can be produced by the 
Mo(n,) reaction using the Japan Materials Testing Reactor (JMTR) and by the 
Mo(n,2n) reaction using some new cyclotrons, and thereby to meet the Japanese demand for Tc together with pharmaceutical companies in Japan. These production methods of Mo were selected from viewpoints of safety, nuclear proliferation resistance and waste management. The specific activity of Mo produced by these methods, however, is very low compared with that of (n,f)Mo. Therefore, it is essential to develop some techniques for separation, concentration and recovery of Tc, and it will be necessary to choose the best methods such as a wet method by solvent extraction and a dry method by sublimation, finally. In future, we aim to provide to about 20% of the domestic demand for Mo using the JMTR and cyclotrons, 100-200 6-day Ci per week at the end of irradiation, and will carry out empirical studies for the commercial production of Tc.
Tsubata, Yasuhiro; Suzuki, Hideya; Matsumura, Tatsuro
no journal, ,
In JAEA, research and development activity in simulation technology for solvent extraction processes has been continued for many years. In our laboratory, a computer program PARC has been developed and used for experimental studies on multistage extraction processes. In this paper, outline of the process simulation technology in the JAEA are introduced.
Mo/Tc separation-concentration apparatus based on solvent extraction and column chromatographyTsuchiya, Kunihiko; Suzuki, Yoshitaka; Nishikata, Kaori; Shibata, Akira; Nakamura, Natsuki; Tanase, Masakazu*; Shiina, Takayuki*; Ota, Akio*; Kawabata, Masako*; Takeuchi, Nobuhiro*
no journal, ,
no abstracts in English
Sakurai, Tomoaki*; Nagoshi, Kohei*; Arai, Tsuyoshi*; Watanabe, So; Sano, Yuichi; Takeuchi, Masayuki
no journal, ,
no abstracts in English
Yasuda, Masaki*; Arai, Tsuyoshi*; Watanabe, So; Arai, Yoichi; Nomura, Kazunori
no journal, ,
no abstracts in English
