A conceptual process study for recovery of uranium alone from spent nuclear fuel by using high-alkaline carbonate media

Nuclear Technology

Volumn 166, Issue 2, 2009, Pages 170-179

  Kim, Kwang Wook ^a   Chung, Dong Yong ^a   Yang, Han Bum ^a   Lim, Jea Kwan ^a   Lee, Eil Hee ^a   Song, Kee Chan ^a   Song, Kyuseok ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

Carbonate; Hydrogen peroxide; Uranium leaching

Indexed keywords

CARBONATES; CARBONATION; FISSION PRODUCTS; FUELS; HYDROGEN PEROXIDE; LEACHING; OXIDATION; PEROXIDES; RECOVERY; SPENT FUELS; TRANSURANIUM ELEMENTS; URANIUM; URANIUM COMPOUNDS; URANIUM DIOXIDE;

ALKALINE CARBONATES; CARBONATE SOLUTIONS; OPERATIONAL SAFETY; PROLIFERATION RESISTANCE; SECONDARY WASTES; SPENT NUCLEAR FUELS; URANIUM LEACHING; URANIUM PEROXIDE;

RADIOACTIVE WASTES;

EID: 67249083470     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT09-A7403     Document Type: Article

References (37)

1. S. PIET, T. BJORNARD, B. DIXON, D. GOMBER, C. LAWS, and G. MATTHERN, "Which Elements Should Be Recycled for a Comprehensive Fuel Cycle?" Proc. Global 2007, Boise, Idaho, September 9-13, 2007, American Nuclear Soci- ety (2007).
2. "Global Nuclear Energy Partnership Technology Devel- opment Plan, " GNEP-TECH-TR-PP-2007-00020, Rev 0, U. S. Department of Energy (2007).
3. "Actinide Separation Chemistry in Nuclear Waste Streams and Materials, " NEA/NSC/DOC (97) 19, Nuclear Energy Agency (1997).
4. Y. SANO, S. MIURA, M. NAKAHARA, M. KAMIYA, K. NOMURA, and J. KOMAKI, "Plutonium and Other Actinides Behavior in NEXT Process, " J. Alloys Compounds, 445-446, 397 (2007).
5. E. D. COLLINS, D. E. BENKER, L. K. FELKER, R. D. TAYLOR, G. D. DEL CUL, B. B. SPENCER, W. D. BOND, and D. O. CAMPBELL, "Development of the UREX+2 Flow Sheet-An Advanced Separations Process for Spent Fuel Pro- cessing, " Trans Am. Nucl. Soc., 93, 739 (2005).
6. A. P. PAIVA and P. MALIK, "Recent Advances on the Chemistry of Solvent Extraction Applied to the Reprocessing of Spent Nuclear Fuels and Radioactive Wastes, " J. Radioanal. Nucl. Chem., 261, 2, 485 (2004).
7. 2 in Aqueous Carbonate Media, " Ind. Eng. Chem. Res., 43, 8188 (2004).
8. N. ASANUNMA, M. HARADA, Y. IKEDA, and H. TOMI- YASU, "New Approach to Nuclear Reprocessing in a Non- Aqueous Solution, " Proc. Global 2001, Paris, France, September 9-13, 2001, French Nuclear Energy Society (2001).
9. K. OHYAMA, K. NOMURA, T. WASHIYA, T. TAYAMA, K. YANO, A. SHIBATA, J. KOMAKI, T. CHIKAZAWA, and T. KIKUCHI, "Development of Uranium Crystallization Sys- tem in NEXT Reprocessing Process, " Proc. Global 2007, Boise, Idaho, September 9-13, 2007, American Nuclear Society (2007).
10. G. S. GOFF, F. L. TAW, S. M. PEPER, L. F. BRODNAX, and W. H. RUNDE, "Uranium, Neptunium, and Plutonium Complexes in Aqueous Hydrogen Peroxide-Carbonate Solu- tion: Stability and Speciation, " presented at American Chem- ical Society Northwest Regional Meeting, Boise, Idaho, June 17-20, 2007.
11. J. A. PORTER, "Precipitation of Neptunium Oxalate and Calcination to Neptunium Oxide, " DP-591, E. I. du Pont de Nemours and Company (1961).
12. 2 Nuclear Fuel at a Burn-Up of Around 100 MWd/kgHM, " J. Nucl. Mater., 345, 192 (2005).
13. W. RUNDE, "The Chemical Interactions of Actinides in the Environment, " Los Alamos Sci., 26, 392 (2000).
14. D. W. SHOESMITH, "Used Fuel and Uranium Dioxide Dissolution Studies-Review, " NWMO TR-2007-03, Nuclear Waste Management Organization (2007).
15. D. L. CLARK, D. E. HOBART, and M. P. NEU, "Actinide Carbonate Complexes and Their Importance in Actinide Envi- ronmental Chemistry, " Chem. Rev., 95, 25 (1995).
16. S. ROLLIN, K. SPAHIU, and U.-B. EKLUND, "Determi- nation of Dissolution Rate of Spent Fuel in Carbonate Solu- tions Under Different Redox Conditions with a Flow-Through Experiment, " J. Nucl. Mater., 297, 231 (2001).
17. 2O System, " Radiochim. Acta, 82, 17 (1998).
18. 2O Sys- tem, " Radiochim. Acta, 86, 86 (1999).
19. 2O System, " Radiochim. Acta, 84, 159 (1999).
20. 2) by the Product of Water Radiolysis: Development of a Kinetic Model, " J. Alloys Compounds, 213/214, 93 (1994).
21. 2), " J. Electroanal. Chem., 586, 1 (2006).
22. J. D. PABLO, I. C. CASAS, J. GIMENEZ, M. MOLERA, M. ROVIRA, L. DURO, and J. BRUNO, "The Oxidation Dis- solution Mechanism of Uranium Dioxide. I. The Effect of Tem- perature in Hydrogen Carbonate Medium, " Geochim. Cosmochim. Acta, 63, 3097 (1999).
23. C. F. BAES, Jr. and R. E. MESMER, The Hydrolysis of Cations, Robert E. Krieger Publishing Company, Malabar, Flor- ida (1986).
24. Y. ASANO, N. ASANUMA, T. ITO, M. KATAOKA, S. FUJINO, T. YAMAMURA, W. SUGIYAMA, H. TOMIYASU, K. MIZUMACHI, Y. IKEDA, Y. WADA, and M. ASOU, "Study on a Nuclear Fuel Reprocessing System Based on the Precip- itation Method in Mild Aqueous Solutions, " Nucl. Technol., 120, 198 (1997).
25. J. B. HISKEY, "Hydrogen Peroxide Leaching of Uranium in Carbonate Solutions, " Trans. Inst. Min. Met al.l., 89, C145 (1980).
26. J. M. CLEVELAND, The Chemistry of Plutonium, 2nd ed., American Nuclear Society (1979).
27. M. Y. SUH, C. L. LEE, B. C. SONG, M. H. LEE, S. H. HAN, S. C. SOHN, and K. Y. JEE, "A Valance Control Method Based on a Pt-Aided Hydrogen Peroxide Treatment for Yield- ing Tetravalent Neptunium and Plutonium in Nitric Acid So- lutions, " Bull. Korean Chem. Soc., 29, 2, 475 (2008).
28. Y. MORITA and M. KUBOTA, "Extraction of Neptunium with Di-Isodecyl Phosphoric Acid from Nitric Acid Solution Containing Hydrogen Peroxide, " Solvent Extr. Ion Exch., 6, 2, 233 (1988).
29. J. B. HISKEY, "Kinetics of Uranium Dioxide Dissolution in Ammonium Carbonate, " Miner. Processing Extractive Met- all., 88, C145 (1979).
30. G. D. CUL, L. M. TOTH, W. D. BOND, and D. F. WIL- LIAMS, "Evaluation of Process That Might Lead to Separation of Actinides in Waste Storage Tanks Under Alkaline Condi- tions, " Sep. Sci. Technol., 35, 13, 2127 (2000).
31. 2 in Dilute Alkaline Hydrogen Peroxide Solutions: Part II. Effects of Carbonate Ions, " Elec- trochim. Acta, 51, 3278 (2006).
32. W. RUNDE, L. F. BRODNAX, G. S. GOFF, S. M. PEPER, F. L. TAW, and B. L. SCOTT, "Synthesis and Structural Char- acterization of a Molecular Plutonium (IV) Compound Con- structed from Dimeric Building Block, " Chem. Commun., 17, 1728 (2007).
33. + from Aqueous Solution, " Coord. Chem. Rev., 140, 27 (1995).
34. P. BLAZY, E. A. JDID, A. FLOEANCIG, and B. MOT- TET, "Selective Recovery of Rhenium from Gas-Scrubbing Solution of Molybdenite Roasting Using Direct Precipitation and Separation on Resins, " Sep. Sci. Technol., 28, 2073 (1993).
35. P. C. DEBETS, "X-Ray Diffraction Data on Hydrated Ura- nium Peroxide, " J. Inorg. Nucl. Chem., 35, 727 (1963).
36. K.-A. HUGHES KUBATKO, K. B. HELEAN, A. NAVROTSKY, and P. C. BURNS, "Stability of Peroxide- Containing Uranyl Minerals, " Science, 302, 1191 (2003).
37. "Actinide Separation Chemistry in Nuclear Waste Streams and Materials, " Nuclear Science Committee Report NEA /NSC/DOC (97) 19, Nuclear Energy Agency (Dec. 1997).