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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.
-treated column study of Hanford 300 area sediment using a simple ion exchange and immobile domain modelSaito, Tatsuo; Sato, Kazuhiko; Yamazawa, Hiromi*
Journal of Environmental Radioactivity, 237, p.106708_1 - 106708_9, 2021/10
Times Cited Count：2 Percentile：12.7(Environmental Sciences)We succeeded at numerical reproduction of dissolved U concentrations from column experiments with PO-treated Hanford 300 Area sediment. The time-series curves of dissolved U concentrations under various Darcy flow rate conditions were reproduced by the numerical model in the present study through optimization of the following parameters:(i) the mass of U in mobile domain (on surface soil connected to the stream) and the rest of the total U left as precipitation in immobile domain (isolated in deep soil);(ii) the mixing ratio between immobile and mobile domains, to fit the final recovering curve of concentration; and (iii) the cation exchange capacity (CEC
) and equilibrium constant (k) of the exchange reaction of UO
and H
on simulated soil surface (
), to fit the transient equilibrium concentration, forming the bed of the bathtub curve.
Asakura, Toshihide; Hotoku, Shinobu; Ban, Yasutoshi; Matsumura, Masakazu; Morita, Yasuji
Journal of Nuclear and Radiochemical Sciences, 6(3), p.271 - 274, 2005/12
Tc extraction and separation experiments were performed basing on PUREX technique with using spent UO fuel with burn-up of 44 GWd/t. The experimental results were examined with performing calculations by a simulation code ESSCAR (Extraction System Simulation Code for Advanced Reprocessing). It was demonstrated that Tc can be almost quantitatively extracted from a dissolver solution and that Tc can also be almost quantitatively recovered by scrubbing. Further, it was clearly presented from the calculation results of ESSCAR that the extraction mechanism of Tc is dominated by the synergistic effect of Zr and U.
Uozumi, Koichi*; Iizuka, Masatoshi*; Kato, Tetsuya*; Inoue, Tadashi*; Shirai, Osamu*; Iwai, Takashi; Arai, Yasuo
Journal of Nuclear Materials, 325(1), p.34 - 43, 2004/02
Times Cited Count：111 Percentile：98.54(Materials Science, Multidisciplinary)Experiments were conducted on simultaneous recovering of uranium and plutonium electrochemically into laboratory scale liquid cadomium cathodes(LCCs) at different U/Pu ratios in the salt phase. The influence of the salt composition on the recovered amount of uranium and plutonium, the morphology of uranium and plutonium in the LCCs, and the behavior of americium were examined. It was shouwn that there is a threshold in the U/Pu ratio in the salt phase for the successful simultaneous recovery of uranium and plutonium up to 10wt% in high current efficiencies.
Seko, Noriaki; Katakai, Akio; Hasegawa, Shin; Tamada, Masao; Kasai, Noboru; Takeda, Hayato*; Sugo, Takanobu; Saito, Kyoichi*
Nuclear Technology, 144(2), p.274 - 278, 2003/11
Times Cited Count：129 Percentile：98.72(Nuclear Science & Technology)The total amount of uranium dissolved in seawater at a uniform concentration of 3 mg-U/m
in the world's oceans is 4.5 billion tons. An adsorption method using polymeric adsorbents capable of specifically recovering uranium from seawater is reported to be economically feasible. A uranium-specific non-woven fabric was used as the adsorbent packed in an adsorption cage. We submerged adsorption cages, 16 m
in cross-sectional area and 16 cm in height, in the Pacific Ocean at a depth of 20 m at 7 km offshore of Japan. The cage consisted of stacks of 52,000 sheets of the uranium-specific non-woven fabric with a total mass of 350 kg. The total amount of uranium recovered by the non-woven fabric was more than one kg in terms of yellow cake during a total submersion time of 240 days in the ocean.
Uotani, Masaki*; Shimizu, Takao*; Tamada, Masao
Proceedings of 2003 International Congress on Advances in Nuclear Power Plants (ICAPP '03) (DVD-ROM), 8 Pages, 2003/00
The present paper describes the current technology of uranium recovery from seawater by using radiation-induced graft-adsorbent and the utilization scenario of collected uranium from the viewpoint of long-term perspective of nuclear energy demand in Japan. The several thousand tons of uranium will be required in the latter half of 21st century in Japan, even if the plutonium is practically used in fast breeder reactors (FBRs). This demand of uranium can be supplied by the uranium recovered from seawater if the recovery cost is reasonable. In conclusion, the utilization of uranium from seawater will be able to play an essential role of providing enough time to develop safe and economical FBRs.
Sawa, Kazuhiro; Yoshimuta, Shigeharu*; Shiozawa, Shusaku; Fujikawa, Seigo; Tanaka, Toshiyuki; *; *; *
IAEA-TECDOC-1043, p.177 - 189, 1998/09
no abstracts in English
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.
