Commenced in January 2007
Paper Count: 30999
Electrolytic Dissolutions of UO2 and SIMFUEL in Carbonate Solutions at Several pHs
Abstract:Electrolytic dissolution characteristics of UO2 and SIMFUEL electrodes were studied at several potentials in carbonate solutions of a high concentration at several pHs. The electrolytic uranium dissolution was much affected by a corrosion product of UO2CO3 generated at the electrode during the dissolution in carbonate solution. The corrosion product distorted the voltammogram at UO2 and SIMFUEL electrodes in the potential region of oxygen evolution and increased the overpotential of oxygen evolution at the electrode. The effective dissolution in a carbonate solution could be obtained at an applied potential such as +4 V (vs SSE) or more which had an overpotential of oxygen evolution high enough to rupture the corrosion product on the electrode surface.
Digital Object Identifier (DOI): doi.org/10.5281/zenodo.1077327Procedia APA BibTeX Chicago EndNote Harvard JSON MLA RIS XML ISO 690 PDF Downloads 1210
 K.-W. Kim, D.-Y. Chung, H.-B. Yang, J.-K. Lim, E.-H. Lee, K.-C. Song, and K. Song, "A Conceptual Process Study for Recovery of Uranium Alone from Spent Nuclear Fuel by Using High-Alkaline Carbonate Media," Nuclear Technology, vol. 166, pp. 170-179, May 2009.
 S. M. Pepper, L. F. Brodnax, S. E. Field, R .A. Zehnder, S. N. Valdez, and W. H. Runde, "Kinetic Study of the Oxidative Dissolution of UO2 in Aqueous Carbonate Media," Ind. Eng. Chem. Res., vol. 43, pp. 8188-8193, 2004.
 S. Goff, F. L. Taw, S. M. Pepper, L. F. Brodnax, S. E. Field, and W. H. Runde, "Separation of uranium from fission product in spent nuclear fuel using aqueous H2O2-carbonate solutions," AIChE 2006 Annual Meeting, November 12-17, 2006, San Francisco.
 N. Asanuma, M. Harada, Y. Ikeda, and H. Tomiyasu, "New approach to nuclear reprocessing in a non-aqueous solution," Global 2001, September 9-13, 2001, American Nuclear Society, Paris, France.
 C. Soderquist, and B. Hanson, "Dissolution of spent nuclear fuel in carbonate-peroxide solution," J. Nucl. Mat., vol. 396, pp. 159-162,, 2010.
 S. M. Peper, B. K. McNamara, M. J. O-Hara, and M. Douglas, "Aqueous dissolution of uranium oxides in oxidizing alkaline media," NRC7-7th international Conference on Nuclear and Radiochemistry, August 24-29, 2008, Budapest, Hungary.
 W. Runde, "The Chemical Interactions of Actinides in the Environmen," Los Alamos Sci., vol. 26, pp. 392-411, 2000.
 D. W. Shoesmith, "Used Fuel and Uranium Dioxide Dissolution StudiesÔÇöReview," NWMO TR-2007-03, Nuclear Waste Management Organization, July 2007, pp. 1-60.
 D. L. Clark, D. E. Hobart, and M. P. Neu, "Actinide Carbonte Complexes and Their Importance in Actinide Environmental Chemis," Chem. Rev., vol. 95, pp. 25-48, 1995.
 S. Rollin, K. Spahiu, and U. B. Eklund, "Determination of dissolution rates of spent fuel in carbonate solutions under different redox conditions with a flow-through experiment," J. Nucl. Mater., vol. 297, pp. 231-243, 2001.
 S, Sunder, N. H. Miller, and D.W. Shoesmith, "Corrosion of uranium dioxide in hydrogen peroxide solutions," Corrosion Science, vol. 46, pp. 1095-1111, 2004.
 D. W. Shoesmith, "Fuel corrosion processes under waste disposal conditions," J. Nucl. Mat., vol. 282, pp. 1-31, 2000.
 B. G. Santos, J. J. Nöel, and D.W. Shoesmith, "The effect of pH on the anodic dissolution of SIMFUEL (UO2)," J. Electroanal. Chem., vol. 586, pp. 1-11, 2006.
 D. W. Shoesmith, S. Sunder, M. G. Bailey, and G. J. Wallace, "The corrosion of nuclear fuel (UO2) in oxygenated solutions," Corrosion Sci., vol. 29, No.9, pp. 1115-1128, 1989.
 J. S. Goldik, J. J. Noel, and D. W. Shoesmith, "Surface electrochemistry of UO2 in dilute alkaline hydrogen peroxide solutions: Part II. Effects of carbonate ions," Electrochimica Acta, vol. 51, pp. 3278-3286, 2006.
 B. G. Santos, J. J. Noel, and D. W. Shoesmith, "The influence of calcium ions on the development of acidity in corrosion product deposits on SIMFUEL, UO2," J. Nucl. Mat., vol. 350, pp. 320-331, 2006.
 P. G. Lucuta, R. A. Verrall, Hj Matzke, and B. J. Palmer, "Microstructural features of SIMFUEL- Simulated high-burnup UO2-based nuclear fuel," J. Nucl. Mat., vol. 178, pp. 48-60, January 1991.