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Complex for Super-DIREX ProcessKamiya, Masayoshi; Miura, Sachiko; Nomura, Kazunori; Koyama, Tomozo; Ogumo, Shinya*; Mori, Yukihide*; Enokida, Yoichi*
CD-ROM, P1-35, 4P., 4 Pages, 2004/00
Super-DIREX is a new reprocessing method which has high economical efficiency. Experimental study of this process was started on the direct extraction of U and Pu from irradiated MOX fuel by the supercritical carbon dioxide (SFCO
) containing TBP-HNO complex. This report describes direct extraction of U and Pu with TBP-HNO3 complex at atmospheric pressure, as the first test for irradiated fuel, in order to investigate the applicability of SFCO containing TBP-HNO complex. In this test, dependency on dissolution temperature, Pu content, fuel/ TBP-HNO complex ratio and effect of voloxidation were investigated. From these results, TBP-HNO complex was found to be effective in the respect of the recovery of U and Pu. The number of the process step in dissolution and co-extraction is small, and amount of waste can be reduced. It is applicable to the direct extraction in Super-DIREX.
Miura, Sachiko; Kamiya, Masayoshi; Nomura, Kazunori; Miyachi, Shigehiko; Koyama, Tomozo; Ogumo, Shinya*; Shimada, Takashi*
Abstracts P.30, 30 Pages, 2003/00
None
Miura, Sachiko; Nakahara, Masaumi; Sano, Yuichi; Kamiya, Masayoshi; Nomura, Kazunori; Komaki, Jun
no journal, ,
The behaviour of Pu and other actinides in the crystallization process and U-Pu-Np co-recovery process was discussed. Pu showed the different behaviour in the crystallization process according to its valence in the dissolver solution. Low DF of Cs in some crystallization conditions might be related with the formation of some kinds of Cs compounds with Pu in the dissolver solution. In the U-Pu-Np co-recovery process, Although there are some considerable points, e.g. temperature control in the stripping section, suitable condition for Np extraction, etc., we confirmed that it was possible to co-recover U-Pu-Np under the appropriate condition.
Kamiya, Masayoshi; Koyama, Tomozo; Miura, Sachiko; Aoki, Kazuo*; Sawada, Kayo*
no journal, ,
Distribution coefficient of Am and relation between distribution coefficient of Am and concentration of nitric ion in high salt concentration and high acid concentration region, were given by the experiment using U, Pu, and Am nitric acid solution. The Extractant of this experiment is TBP.
Kamiya, Masayoshi; Sano, Yuichi; Miura, Sachiko; Koyama, Tomozo; Aoki, Kazuo*; Sawada, Kayo*
no journal, ,
Processing in high concentration condition is the feature of actinides co-extraction system with direct extraction process using supercritical fluid. Distribution coefficient of U and Pu obtained by experiment indicates that conventional empirical formula is applicable in this condition.
Kamiya, Masayoshi; Miura, Sachiko; Sano, Yuichi; Koyama, Tomozo; Aoki, Kazuo*; Sawada, Kayo*
no journal, ,
The direct extraction test of the unirradiation MOX fuel was executed under ordinary pressure. If the composition of the solvent used was appropriate, it was able to be confirmed that not only U and Pu but also Am was extractive at the same time by TBP. It was suggested to have approved the extraction simultaneously on slight balances of the concentration of TBP, acid, and water in the solvent.
-ray durability of adsorbents for MA recovery processWatanabe, So; Miura, Sachiko; Sano, Yuichi; Nomura, Kazunori; Koma, Yoshikazu; Nakajima, Yasuo
no journal, ,
no abstracts in English
Kaji, Naoya; Kamiya, Masayoshi; Takahatake, Yoko; Oyama, Koichi; Miura, Sachiko; Koyama, Tomozo; Aoki, Kazuo*; Yamada, Seiya*
no journal, ,
A battery of tests using MOX fuel were performed for development of actinides co-extraction system with direct extraction process using supercritical fluid. The condition that was set up based on consideration of the results of the tests under ordinary pressure, and then was made fine adjusted based on the tests with supercritical fruid. As a result, U, Pu and Am were extracted simultaneously. Comparative test confirmed that U, Pu and Am could be also extracted simultaneously with dodecane as a diluent. While the extraction test of unirradiated MOX fuel with simulated FP, U, Pu was extracted with U and Am, and the Pu residue, that was found at the extraction test of irradiated fuel, was not found. As the result of scrubbing and stripping test, it was showed that traditional extraction process design method could be applied to design scrubbing and stripping process with supercritical fluid.
Watanabe, So; Miura, Sachiko; Sano, Yuichi; Nomura, Kazunori; Koma, Yoshikazu; Nakajima, Yasuo
no journal, ,
no abstracts in English