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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

Gamma radiation resistance of spin Seebeck devices

Yagmur, A.*; Uchida, Kenichi*; Ihara, Kazuki*; Ioka, Ikuo; Kikkawa, Takashi*; Ono, Madoka*; Endo, Junichi*; Kashiwagi, Kimiaki*; Nakashima, Tetsuya*; Kirihara, Akihiro*; et al.

Applied Physics Letters, 109(24), p.243902_1 - 243902_4, 2016/12

 Times Cited Count:3 Percentile:14.8(Physics, Applied)

Thermoelectric devices based on the spin Seebeck effect (SSE) were irradiated with gamma ($$gamma$$) rays with the total dose of around 3$$times$$10$$^{5}$$ Gy in order to investigate the $$gamma$$-radiation resistance of the devices. To demonstrate this, Pt/Ni$$_{0.2}$$Zn$$_{0.3}$$Fe$$_{2.5}$$O$$_{4}$$/Glass and Pt/Bi$$_{0.1}$$Y$$_{2.9}$$Fe$$_{5}$$O$$_{12}$$/Gd$$_{3}$$Ga$$_{5}$$O$$_{12}$$ SSE devices were used. We confirmed that the thermoelectric, magnetic, and structural properties of the SSE devices are not affected by the $$gamma$$-ray irradiation. This result demonstrates that SSE devices are applicable to thermoelectric generation even in high radiation environments.

Oral presentation

Uranium recovery from the solution originated sludge waste, 1; Selection of some uranium recovery techniques

Takahatake, Yoko; Saito, Madoka*; Iwamoto, Toshihiro; Watanabe, So; Watanabe, Masayuki

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. Survey of uranium recovery methods was conducted for realization of technical scale facility which is treated sludge solution. Result of comparison on facility scale, amount of second waste, maturity, merit and demerit, several methods which have to be considered were selected.

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.

Oral presentation

Uranium recovery from leachate of sludges generated from nuclear fuel fabrication process, 4; Evaluation of oxide conversion condition after temperature swing extraction process

Kai, Masao; Iwamoto, Toshihiro; Saito, Madoka*; Takahatake, Yoko; Watanabe, So; Nakamura, Masahiro; Tsukahara, Takehiko*; Itoda, Naokazu*; Naruse, Atsuki*

no journal, , 

The sludges containing uranium are generated in nuclear fuel fabrication process and have been stored in nuclear fuel fabrication facilities. Uranium is suggested to be selectively recovered from the solution in which the sludges are immersed. In this study, the oxide conversion tests were carried out with the gel obtained by the temperature swing extraction tests with cerium. The most effective heating temperature for the oxide conversion of was determined as 1000 degree Celsius. Based on the results of tests with cerium, the oxide conversion tests with uranium gel were also carried out. The gel was heated at 1000, and products were specified according to analysis data.

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