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Morita, Yasuji; Yamagishi, Isao; Tsubata, Yasuhiro; Matsumura, Kazumi; Sakurai, Koji*; Iijima, Takahiko
JAEA-Research 2012-031, 39 Pages, 2012/11
JAEA-Research-2012-031.pdf:4.87MBJAEA-Research-2012-031(errata).pdf:0.14MB
Solvent extraction process with di-2-ethylhexylphosphoric acid has been developed for the purpose of Mo separation from high-level radioactive liquid wastes (HLLW). Mo has very low solubility in borosilicate glasses and makes so-called yellow phase when it contained beyond the solubility. After extraction and back-extraction data of Mo and other fission products were obtained by batch extraction tests, continuous extraction tests with simulated HLLW were performed using mixer-settler twice. At the second test, reduction of Y extraction yield and increase of Mo and Zr back-extraction yield were obtained compared with the results of the first tests, but those values should be still improved. Process simulation technique was developed using simulation code named PARC-MA, and the optimized process condition was obtained by the simulation.
Matsumura, Tatsuro; Morita, Yasuji; Matsumura, Kazumi; Sano, Yuichi; Koma, Yoshikazu; Nomura, Kazunori
Proceedings of 11th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (Internet), 8 Pages, 2012/00
no abstracts in English
Matsumura, Tatsuro; Morita, Yasuji; Matsumura, Kazumi; Sano, Yuichi; Koma, Yoshikazu; Nomura, Kazunori
Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 5 Pages, 2011/12
As a part of the FaCT project, R&D of a reprocessing system for fast reactor spent fuel has been conducted. In the system, trivalent minor actinides (An(III) = Am(III) + Cm(III)) are recovered by the method of extraction chromatography from a raffinate from the reprocessing process. The chemical flowsheet is composed of the two cycles system; An(III) + lanthanides (Ln)(III) recovery and An(III)/Ln(III) separation. A best combination of extractants should be considered on the latest extractant development for application. In the course of our development, CMPO and TODGA for An(III) + Ln(III) recovery, and HDEHP, TOPEN and isoHEX-BTP for An(III)/Ln(III) separation were investigated. The adsorbent for the extraction chromatography is based on the composite material of porous silica support and polystyrenedivinylbenzene (SiO
-P) impregnated with the extractants. The flowsheet tests using simulated acidic raffinate from reprocessing process containing TRU tracers were carried out. In this study, it was demonstrated that Am and Cm can be separated from the simulated raffinate with combinations TODGA adsorbent column and isoHEX-BTP adsorbent column or TOPEN adsorbent column. The flow sheets will separate An(III) effectively by improving condition of flow velocity, column length and ionic strength of the feed solution.
Matsumura, Tatsuro; Matsumura, Kazumi; Morita, Yasuji; Koma, Yoshikazu; Sano, Yuichi; Nomura, Kazunori
Journal of Nuclear Science and Technology, 48(6), p.855 - 858, 2011/06
Times Cited Count：13 Percentile：69.55(Nuclear Science & Technology)As a part of the Fast Reactor Cycle Technology Development (FaCT) Project, research and development of a reprocessing system has been conducted. In the system, MA(III) (= Am(III) + Cm(III)) are recovered by the method of extraction chromatography from acidic raffinate of the reprocessing process. In general, an extractant for solvent extraction can be used as an impregnated adsorbent for extraction chromatograph system. Because of the similarity of in chemical properties between MA(III) and Lanthanides(III), the MA(III) recovery processes using solvent extraction are composed of two steps; MA(III) - Ln(III) recovery and MA(III)/Ln(III) separation. In many partitioning methods using extraction chromatography, MA(III) separation from the raffinate is achieved by two column units system corresponding to the two steps. In this study, we demonstrated that the direct separation of MA(III) from the simulated raffinate with single column unit system using 
HEX-BTP adsorbent. The adsorbent has high separation performance of MA(III). DTPA in the feed solution as masking reagent to Pd was effective to prevent to remain of Pd in the column.
radiation durability of TRPEN adsorbent with porous silica supportKoma, Yoshikazu; Watanabe, So; Matsumura, Kazumi; Sano, Yuichi
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The extraction chromatography technology has been developed for recovery of Am and Cm from a high level liquid waste of fast reactor fuel reprocessing. The adsorbent that retains TRPEN (tetrakis(alkylpyridylmethyl)ethylenediamine) extractant on the porous silica support coated with styrene-divinyl benzene polymer was investigated on its durability to radiation. Dependency of adsorption capacity on dose was different from those of other extractants.
-PMatsumura, Tatsuro; Morita, Yasuji; Matsumura, Kazumi; Sano, Yuichi; Koma, Yoshikazu
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no abstracts in English
Matsumura, Tatsuro; Morita, Yasuji; Matsumura, Kazumi; Nomura, Kazunori; Sano, Yuichi; Koma, Yoshikazu
no journal, ,
no abstracts in English
-irradiation test of adsorbents in solution on generation of radiolysis gasNomura, Kazunori; Matsumura, Kazumi; Watanabe, So; Sano, Yuichi; Koma, Yoshikazu
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no abstracts in English
Morita, Yasuji; Yamagishi, Isao; Matsumura, Kazumi; Iijima, Takahiko; Matsumura, Tatsuro
no journal, ,
As a part of the development of high-level liquid waste (HLLW) conditioning technology for advanced nuclear fuel cycle, separation process for Mo by extraction with HDEHP (di-2-ethylhexylphosphoric acid) is being developed as the first separation step for HLW. Separation behavior of various elements in continuous counter-current extraction was examined by an experiment with simulated HLLW using mixer-settler units. The results showed possibility to establish the separation process for Mo by extraction with HDEHP.
Matsumura, Tatsuro; Morita, Yasuji; Matsumura, Kazumi; Nomura, Kazunori; Sano, Yuichi; Koma, Yoshikazu
no journal, ,
no abstracts in English
