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

Published online by Cambridge University Press:  25 January 2013

Hundal Jung
Affiliation:
Center for Nuclear Waste Regulatory Analyses (CNWRA), 6220 Culebra Rd, San Antonio, TX 78238, U.S.A.
Tae Ahn
Affiliation:
U.S. Nuclear Regulatory Commission (NRC), MS E2–B2, Washington, DC 20555-0001, U.S.A.
Roberto Pabalan
Affiliation:
Center for Nuclear Waste Regulatory Analyses (CNWRA), 6220 Culebra Rd, San Antonio, TX 78238, U.S.A.
David Pickett
Affiliation:
Center for Nuclear Waste Regulatory Analyses (CNWRA), 6220 Culebra Rd, San Antonio, TX 78238, U.S.A.
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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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Articles
Copyright
Copyright © Materials Research Society 2013 

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References

REFERENCES

Ahn, T. and Mohanty, S., NUREG–1914, Washington, DC: U.S. Nuclear Regulatory Commission (NRC) (2008).Google Scholar
Lucuta, P.G., Verrall, R.A., Matzke, H.J., and Palmer, B.J., J. Nucl. Mater. 178, 48 (1991).CrossRefGoogle Scholar
Jung, H., Ahn, T., Axler, K., Pabalan, R., and Pickett, D., NRC ADAMS Accession Number ML112520488. Washington, DC: NRC (2011).Google Scholar
Rondinella, V. and Matzke, Hj., J. Nucl. Mater. 238, 44 (1996).CrossRefGoogle Scholar
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).Google Scholar
Forsyth, R., SKB TR 97– 25. Stockholm, Sweden: Swedish Nuclear Fuel and Waste Management Company (1997).Google Scholar
Shoesmith, D.W., J. Nucl. Mater. 282, 1, (2000).CrossRefGoogle Scholar
Röllin, S., Spahiu, K., and Eklund, U.-B., J. Nucl. Mater. 297, 231 (2001).CrossRefGoogle Scholar
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).CrossRefGoogle Scholar