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Corrosion Study of SIMFUEL in Aerated Carbonate Solution Containing Calcium and Silicate

  • Hundal Jung (a1), Tae Ahn (a2), Roberto Pabalan (a1) and David Pickett (a1)

Abstract

The corrosion behavior of simulated spent nuclear fuel (SIMFUEL) was investigated using electrochemical impedance spectroscopy and solution chemistry analyses. The SIMFUEL was exposed to aerated solutions of NaCl+NaHCO3 with and without calcium (Ca) and silicate. Two SIMFUEL compositions were studied, representing spent nuclear fuel (SNF) corresponding to 3 or 6 at % burnup in terms of fission product equivalents of surrogate elements. For all tested cases, the polarization resistance increased with increased immersion time, indicating possible blocking effects due to accumulation of corrosion products on the SIMFUEL surface. The potential-pH diagram suggests formation of schoepite that may cause the increase in the polarization resistance. The addition of Ca and silicate produced no measureable change in the polarization resistance measured at the corrosion potential. The dissolution rate ranged from 1 to 3 mg/m2-day, which is similar to the range of dissolution rates for SIMFUEL and SNF reported in the literature for comparable conditions. SIMFUEL burnup did not have a major effect on the dissolution rate. Analysis of the solution chemistry shows that uranium is the dominant element dissolved in the posttest solutions, and the dissolution rates calculated from uranium (U) concentrations are consistent with the dissolution rates obtained from impedance measurements. Simulated-fission product elements (i.e., barium, molybdenum, strontium, and zirconium) dissolved from the SIMFUEL electrode at a relatively high rate. Sorption test results indicated significant sorption of U onto the oxide formed on stainless steel. Electrochemical methods were found to be effective for measuring the uranium dissolution rate in real time.

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References

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1. Ahn, T. and Mohanty, S., NUREG–1914, Washington, DC: U.S. Nuclear Regulatory Commission (NRC) (2008).
2. Lucuta, P.G., Verrall, R.A., Matzke, H.J., and Palmer, B.J., J. Nucl. Mater. 178, 48 (1991).
3. Jung, H., Ahn, T., Axler, K., Pabalan, R., and Pickett, D., NRC ADAMS Accession Number ML112520488. Washington, DC: NRC (2011).
4. Rondinella, V. and Matzke, Hj., J. Nucl. Mater. 238, 44 (1996).
5. Grambow, B., Loida, A., Martinez-Esparza, A., Diaz-Arocas, P., De Pablo, J., Paul, J.L., Marx, G., Glatz, J.P., Lemmens, K., Ollila, K., and Christensen, H., European Commission, Nuclear Science and Technology, Report EUR 19140 EN (2000).
6. Forsyth, R., SKB TR 97– 25. Stockholm, Sweden: Swedish Nuclear Fuel and Waste Management Company (1997).
7. Shoesmith, D.W., J. Nucl. Mater. 282, 1, (2000).
8. Röllin, S., Spahiu, K., and Eklund, U.-B., J. Nucl. Mater. 297, 231 (2001).
9. Serrano-Purroy, D., Clarens, F., Glatz, J.-P., Wegen, D., Christiansen, B., de Pablo, J., Gimennez, J., Casa, I., and Martinez-Esparza, A., Radiochim. Acta 97, 491 (2009).

Keywords

Corrosion Study of SIMFUEL in Aerated Carbonate Solution Containing Calcium and Silicate

  • Hundal Jung (a1), Tae Ahn (a2), Roberto Pabalan (a1) and David Pickett (a1)

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