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Journal Articles

Simultaneous recovery of all actinides from spent nuclear fuel by carbamoylmethylphosphine oxide in fluorinated diluents

Ozawa, Masaki; Iwai, Takehiko*; Babain, V.*; Shadrin, A.*

Proceedings of International Solvent Extraction Conference "Solvent Extraction-Fundamentals to Industrial Applications" (ISEC 2008), p.623 - 628, 2008/09

Bifunctional organophosphorus extractants dissolved in polar fluorinated diluents were studied aiming at directly recovering all f-elements from the dissolver solution of spent nuclear fuel. Distribution ratios of U, Np and Pu were sufficiently high for 0.4$$sim$$0.8MCMPO in this solvent system, and combination of salt-free, methylamine carbonate (MAC), etc, were evaluated to obtain fractional stripping of f-elements. Static multi-stage extraction using artificial FBR dissolver solution supported the process feasibility.

Journal Articles

A New back-end cycle strategy for enhancing separation, transmutation and utilization of materials (Adv.-ORIENT cycle)

Ozawa, Masaki; Suzuki, Tatsuya*; Koyama, Shinichi; Akatsuka, Hiroshi*; Mimura, Hitoshi*; Fujii, Yasuhiko*

Progress in Nuclear Energy, 50(2-6), p.476 - 482, 2008/03

 Times Cited Count:36 Percentile:91.64(Nuclear Science & Technology)

For the minimization of the ecological burden originated in nuclear fuel recycling, a new R&D strategy was filed as "Adv.-ORIENT cycle". In the context, mutual precise separation of $$f$$-elements, such as minor actinide (MA)/lanthanides (Lns) and Am/Cm, are highly essential for enhancing the MA ($$^{241}$$Am) burning. The separation and utilization of rare metal fission products (RMFPs; Ru, Tc, etc) are a new direction in the partitioning and transmutation field. Separation of exothermic nuclides, $$^{90}$$Sr, $$^{137}$$Cs as well as MA, will significantly help to improve the repository tasks. A key separation media are ion exchange chromatography (IXC) by tertiary pyridine resin and a catalytic electrolytic extraction (CEE) by Pd$$_{adatom}$$. On challenging the isotope separation of LLFP, theoretical and laboratory studies were begun for $$^{135}$$Cs, $$^{126}$$Sn in the first priority.

Oral presentation

Supercritical fluid extraction from simulated MOX containing fission products

Shadrin, A. Y.*; Murzin, A. A.*; Koma, Yoshikazu; Koyama, Tomozo

no journal, , 

Befavior of fission products (FP) in supercritical fluid extraction from mixed oxide was investigated. U, Pu and Np are preferentially extracted and shows no selectivity among them. Extraction of FP increases with flowing of the supercritical CO$$_{2}$$ and TBP-nitiric acid mixture.

Oral presentation

Fundamental aspects on extraction of $$f$$ elements by carbamoylmethylphosphine oxide in fluorinated diluents

Ozawa, Masaki

no journal, , 

Partitioning and transmutation of long-lived radioactive nuclides in high active liquid wastes are required to lessen the environmental burden originated from the operation of nuclear fuel cycle. Against the present scenario by which probably requiring additional initial and running costs with adding new separation processes to the PUREX, a novel extraction system capable of recoverying all of actinide directly from dissolver solution is under developing. The presentation will report the fundamental extraction behaviors on fission products as well as actinides, and on the 3rd phase formation region for proposed extractant media. As a result, the specified ORGA (Organophosporic-fluoropole extractant for Recovery of Group of Actinides) process can extract $$f$$-elements at highly U saturated organic media without splitting the unfavorable 3rd phase. Based on the experimental results, the validity of ORGA process will be referred.

Oral presentation

Development of ORGA process for simultaneous recovery of all actinides from spent fuel, 1; Extraction of $$f$$-elements by CMPO in fluorinated diluents

Ozawa, Masaki; Shadrin, A. Y.*; Babain, V.*; Zilberman, B.*; Strelkov, S.*

no journal, , 

Partitioning and transmutation of long-lived actinides in spent fuel is required for decreasing the radioactive toxicity in nuclear fuel cycle. In collaboration with the Khlopin Radium Institute in St.Petersburg, fundamental extraction and stripping behaviors of f-elements and FPs were studied. New solvent composed of CMPO dissolved in TBP with fluorinated diluents such as metanitrobenzo-trifluoride showed high solubility for extracted metal complexes, and therby expanding the boundary of non-third phase formation. Obtained extraction data suggested the compatibility of ORGA process (Organophosporyl-fluoropole extractant for Recovery of Group of Actinides) as for recovering all actinides in a single extraction cycle.

Oral presentation

Development of ORGA process for simultaneous recovery of all actinides from spent fuel, 2; Static counter-current extraction of actinides and fission products

Ozawa, Masaki; Shadrin, A.*; Babain, V.*; Zilberman, B.*; Strelkov, S.*

no journal, , 

Solvent extraction behaviors of actinides and fission products in simulated dissolver solution of fast reactor spent fuel were investigated by static counter-current, multi-stage extraction using novel 0.4 MOctyl(phenyl)D[iB]CMPO/30%TBP/70%fluoropole-732 solvent.

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