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Journal Articles

Treatment of U contaminated waste generated from nuclear fuel fabrication process, 1; Ce(IV) recovery by temperature swing extraction with monoamides

Iwamoto, Toshihiro; Saito, Madoka*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Naruse, Atsuki*; Tsukahara, Takehiko*

Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 4 Pages, 2023/05

Applicability of temperature swing extraction technology employing monoamides was examined for uranium contaminated waste treatment procedure. Separation experiments on simulated target solution with three kinds of monoamides with different structure showed that Ce(IV) in the solution was selectively recovered by the temperature swing extraction operation. Based on the experiments, an appropriate monoamide for the procedure was selected.

Journal Articles

Acid dissociation constant of bis(2-ethylhexyl) hydrogen phosphate impregnated in a polymer layer coated on silica microparticles

Miyagawa, Akihisa*; Takeuchi, Masayuki; Arai, Tsuyoshi*; Watanabe, So; Sano, Yuichi; Nakatani, Kiyoharu*

Bulletin of the Chemical Society of Japan, 95(4), p.566 - 568, 2022/04

 Times Cited Count:3 Percentile:40.16(Chemistry, Multidisciplinary)

We demonstrate that pKa of extractant impregnated in a polymer phase varies with the cross-linking degree and the coexistence of other extractants, which induces a change in the hydrophobicity of the polymer phase. The results presented herein will be beneficial for the development of novel solid-extraction adsorbents.

Journal Articles

Separation of light and middle lanthanides using multistage extraction with diglycolamide extractant

Matsutani, Takafumi; Sasaki, Yuji; Katsuta, Shoichi*

Analytical Sciences, 37(11), p.1603 - 1609, 2021/11

 Times Cited Count:7 Percentile:52.9(Chemistry, Analytical)

We investigated the chemical behavior of lanthanides (Ln) using diglycolamide extractant with multistage extraction. We obtained the breakthrough curves for light and middle Ln. Our study reveals that the metal extraction limit depends on their $$D$$ values and metal concentrations used in the experiments. From the multistage extractions of 15 aqueous phases and 15 organic phases, three curves (extraction curves, back-extraction curves, and separation curves) were obtained by changing the nitric acid concentration. As an example, under a condition of the separation curve experiment (aqueous phase: 0.5 M HNO$$_{3}$$, organic phase: 0.1 M TDDGA ($$N,N,N',N'$$-tetradecyl-diglycolamide) in $$n$$-dodecane), a recovery of more than 99% of Sm in the organic phase with less than 1% Nd can be obtained.

Journal Articles

Minor actinides recovery from irradiated fuel for SmART cycle test

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

Journal Articles

Highly practical and simple ligand for separation of Am(III) and Eu(III) from highly acidic media

Suzuki, Hideya; Tsubata, Yasuhiro; Kurosawa, Tatsuya; Shibata, Mitsunobu; Kawasaki, Tomohiro; Urabe, Shunichi*; Matsumura, Tatsuro

Analytical Sciences, 32(4), p.477 - 479, 2016/04

 Times Cited Count:24 Percentile:68.22(Chemistry, Analytical)

An impeccable, high-performance new reagent called alkyl diamide amine (ADAAM) was examined from the viewpoint of mutual separation of Am(III) and Eu(III). ADAAM has three donor atoms, one soft N-donor atom and two hard O-donor atoms, in the central frame. The combination of soft and hard atoms affords a tridentate donor set of atoms that ensures remarkable extractability and selectivity of Am(III) and Eu(III) in highly acidic media.

Journal Articles

Journal Articles

Radiation damage to amine extractants, 1; Effect on the extraction behavior of uranium and fission products

Ishihara, Takehiko;

Nihon Genshiryoku Gakkai-Shi, 4(5), p.307 - 312, 1962/00

no abstracts in English

Oral presentation

Uranium recovery from the solution originated sludge waste, 3; Evaluation of several extractants on cerium (IV) nitrate separation using thermoresponsive polymer

Iwamoto, Toshihiro; Saito, Madoka*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Naruse, Atsuki*; Tsukahara, Takehiko*

no journal, , 

The sludge generated production of nuclear fuel contained uranium has been storage. The sludge is immersed in some kinds of solution. After immersion, uranium is recovered from the solution. Cerium extractive tests using thermoresponsive polymer was carried out on two kinds of extractants. C14-BAMA was found to be superior, and we plan to conduct a uranium study on this extractant.

Oral presentation

Uranium recovery from the solution originated sludge waste, 2; Comparison study of uranyl nitrate separation methods by monoamide extractant

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.

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