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Sanada, Yukihisa; Urabe, Yoshimi*; Saito, Madoka*; Shiribiki, Takehiko*; Misono, Toshiharu; Funaki, Hironori
Kankyo Gijutsu, 53(4), p.188 - 193, 2024/07
no abstracts in English
Iwamoto, Toshihiro; Saito, Madoka*; Takahatake, Yoko; Watanabe, So; Watanabe, Masayuki; Naruse, Atsuki*; Tsukahara, Takehiko*
Mechanical Engineering Journal (Internet), 11(2), p.23-00444_1 - 23-00444_7, 2024/04
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.
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：13.98(Physics, Applied)Thermoelectric devices based on the spin Seebeck effect (SSE) were irradiated with gamma (
) rays with the total dose of around 3
10
Gy in order to investigate the -radiation resistance of the devices. To demonstrate this, Pt/Ni
Zn
Fe
O
/Glass and Pt/Bi
Y
Fe
O
/Gd
GaO SSE devices were used. We confirmed that the thermoelectric, magnetic, and structural properties of the SSE devices are not affected by the -ray irradiation. This result demonstrates that SSE devices are applicable to thermoelectric generation even in high radiation environments.
Misono, Toshiharu; Sanada, Yukihisa; Nakanishi, Takahiro; Urabe, Yoshimi*; Shiribiki, Takehiko*; Saito, Madoka*; Funaki, Hironori
no journal, ,
Thirteen years have passed since the accident at TEPCO's Fukushima Daiichi Nuclear Power Station, but the concentration of radioactive materials has not returned to pre-accident levels in some coastal areas. Therefore, continuous monitoring of radioactive materials is being conducted by ministries, local governments, and electric power companies. In the future, it will be important to centralize the monitoring data collected by each organization and evaluate the results. In addition, unmanned monitoring data acquisition itself has been attracting attention in recent years. In this presentation, we will report on JAEA's efforts to create a database of radioactive materials in coastal area and to develop a technology for measuring radioactivity by unattended vessel.
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.
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.
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.
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.
Kai, Masao; Sato, Takanori*; Iwamoto, Toshihiro; Saito, Madoka*; Nakahara, Masaumi; Takahatake, Yoko; Watanabe, So; Nakamura, Masahiro; Naruse, Atsuki*; Itoda, Naokazu*; et al.
no journal, ,
The sludges containing uranium are generated in the nuclear fuel fabrication facilities. Uranium is planned to be selectively recovered from the sludge leachate. The temperature swing extraction method was selected for the selective recovery of uranium. In this study, a small-scale testing system was developed, and the performances of the agitation, the transportation of the gel-containing solution, and the separation of the gel were experimentally examined. Cerium(IV) was used instead of uranium, and agitator blades were selected to agitate the gel solution effectively. The gel solution was transferred through the self-feeding pump and was successfully separated into the gel and the solution using the spin dryer with a filter cloth.
