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Journal Articles

Solvent extraction in analytical separation techniques

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.

JAEA Reports

Development of separation process for Pd by extraction with 5,8-diethyl-7-hydroxy-6-dodecanone oxime

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.

Journal Articles

Neutron irradiation effect of high-density MoO$$_{3}$$ pellets for Mo-99 production, 3

Ishida, 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

Journal Articles

Technical estimation for mass production of highly-concentrated $$^{rm 99m}$$Tc solution from $$^{99}$$Mo to be obtained by ($$n,gamma$$) reaction; A Preliminary study using inactive Re instead of $$^{rm 99m}$$Tc

Tanase, 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

JAEA Reports

None

PNC-TJ1615 93-002, 13 Pages, 1993/03

PNC-TJ1615-93-002.pdf:0.35MB

no abstracts in English

Journal Articles

2.2,On-line chemical separation methods

Usuda, Shigekazu

Dai-4-Pan Jikken Kagaku Kouza, 14; Kaku, Hoshasen, p.124 - 140, 1992/00

no abstracts in English

JAEA Reports

Development of Separation Technique of Radioisotopes from Fuel Reprocessing Waste

; ; ; ; ; ;

JAERI-M 6958, 40 Pages, 1977/03

JAERI-M-6958.pdf:1.25MB

no abstracts in English

Journal Articles

Preparation of $$^{3}$$$$^{2}$$P by solvent extraction method

Nippon Genshiryoku Gakkai-Shi, 10(1), p.2 - 6, 1968/00

no abstracts in English

Journal Articles

Nuclear fuel reprocessing using a solvent extraction method, 1

Genshiryoku Hatsuden, 2(2), P. 9, 1958/00

no abstracts in English

Oral presentation

Development of new separation and analytical systems on green chemistry

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.

Oral presentation

Extractant and stripping reagents used in the novel separation process, single-cycle process, for the partitioning of high level liquid waste

Sasaki, Yuji; Tsubata, Yasuhiro; Morita, Keisuke; Shirasu, Noriko; Shimazaki, Shoma; Kitatsuji, Yoshihiro

no journal, , 

no abstracts in English

Oral presentation

R&D on separation, concentration and recovery of $$^{99m}$$Tc from $$^{99}$$Mo for commercial production

Shiina, 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 $$^{99}$$Mo/$$^{99m}$$Tc generator and $$^{99m}$$Tc injections ($$^{99m}$$Tc labeled pharmaceuticals) continues to account for approximately 80% of the entire in-vivo supply in Japan. Furthermore, the number of $$^{99m}$$Tc injection supplies is approximately four times larger than that of the $$^{99}$$Mo/$$^{99m}$$Tc generator. Therefore, Chiyoda Technol Co. have performed a research and development (R&D) for the domestic production of $$^{99m}$$Tc in cooperation with the Japan Atomic Energy Agency (JAEA) and FUJIFILM RI pharma Co., Ltd. to ensure a constant and reliable supply of $$^{99m}$$Tc. CTC therefore has a plan to stably produce $$^{99m}$$Tc from $$^{99}$$Mo, which can be produced by the $$^{98}$$Mo(n,$$gamma$$) reaction using the Japan Materials Testing Reactor (JMTR) and by the $$^{100}$$Mo(n,2n) reaction using some new cyclotrons, and thereby to meet the Japanese demand for $$^{99m}$$Tc together with pharmaceutical companies in Japan. These production methods of $$^{99}$$Mo were selected from viewpoints of safety, nuclear proliferation resistance and waste management. The specific activity of $$^{99}$$Mo produced by these methods, however, is very low compared with that of (n,f)$$^{99}$$Mo. Therefore, it is essential to develop some techniques for separation, concentration and recovery of $$^{99m}$$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 $$^{99}$$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 $$^{99m}$$Tc.

Oral presentation

Development of computer simulation technology in JAEA for study on new solvent extraction processes

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.

Oral presentation

R&D on $$^{99}$$Mo/$$^{99m}$$Tc separation-concentration apparatus based on solvent extraction and column chromatography

Tsuchiya, 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

Oral presentation

Adsorption and elution mechanism of Nd(III) by adsorbent with CMPO-HDEHP mixture

Sakurai, Tomoaki*; Nagoshi, Kohei*; Arai, Tsuyoshi*; Watanabe, So; Sano, Yuichi; Takeuchi, Masayuki

no journal, , 

no abstracts in English

Oral presentation

Development of treatment technology for spent solvent generated from fuel reprocessing process, 3; Oxidative decomposition treatment of the spent phosphoric acid extracting agent

Yasuda, Masaki*; Arai, Tsuyoshi*; Watanabe, So; Arai, Yoichi; Nomura, Kazunori

no journal, , 

no abstracts in English

17 (Records 1-17 displayed on this page)
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