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Aqueous leaching of ADOPT and standard UO2 spent nuclear fuel under H2 atmosphere

Published online by Cambridge University Press:  28 January 2020

Alexandre Barreiro Fidalgo*
Affiliation:
Studsvik Nuclear AB, Nyköping, Sweden
Olivia Roth
Affiliation:
Studsvik Nuclear AB, Nyköping, Sweden
Anders Puranen
Affiliation:
Studsvik Nuclear AB, Nyköping, Sweden
Lena Z. Evins
Affiliation:
The Swedish Nuclear Fuel Waste Management Company (SKB), Stockholm, Sweden
Kastriot Spahiu
Affiliation:
The Swedish Nuclear Fuel Waste Management Company (SKB), Stockholm, Sweden
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Abstract

Leaching results to compare the dissolution behavior of a new type of fuel with additives (Advanced Doped Pellet Technology, ADOPT) with standard UO2 fuel are presented. Both fuels were irradiated in the same assembly of a commercial boiling water reactor to a local burnup of ∼58 MWd/kgU. Fuel fragments are leached in simplified groundwater in two autoclaves under hydrogen atmosphere, representing conditions in a canister failure scenario resulting in water intrusion for a spent nuclear fuel repository. Preliminary results indicate the uranium concentration decreased to 3-4x10-8 M after 421 days, slightly above the solubility of amorphous UO2. Xe has been detected in the gas phase of both autoclaves. The concentration of Cs and I seems to gradually approach constant values, yet the redox sensitive elements continue to slowly increase with time. The preliminary data obtained supports the hypothesis that there is no major difference in leaching behavior between the two fuels.

Type
Articles
Copyright
Copyright © Materials Research Society 2020

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References

REFERENCES:

Arborelius, J. et al. J. Nucl. Sci. Technol. , 43, 967-976 (2006).CrossRefGoogle Scholar
Roth, O. et al. Leaching of high burn up spent fuel with and without matrix dopants, In Kienzler, B., Metz, V., Duro, L., Valls, A. Final (3rd) Annual Workshop Proceedings of the 7th EC FP CP FIRST-Nuclides project 2014.Google Scholar
Nilsson, K. et al. J. Nucl. Mater., 488, 123-128 (2017).CrossRefGoogle Scholar
Guillamont, R. et al. Update on the chemical thermodynamics of U, Np, Pu, Am and Tc, OECD NEA, Elsevier (2003)Google Scholar
Puranen, A., Roth, O., Evins, L.Z., Spahiu, K., MRS Advances 3(19), 1013-1018 (2018)CrossRefGoogle Scholar
Roudil, et al. J. Nucl. Mater, 362, 411-415 (2007)CrossRefGoogle Scholar
Fors, P., Carbol, P., Van Winkel, S., Spahiu, K., J. Nucl. Mater. 394, 1-8 (2009).CrossRefGoogle Scholar
Loida, A., Metz, V., Kienzler, B., Geckeis, H., J. Nucl. Mater. 346, 24-31 (2005)CrossRefGoogle Scholar
Spahiu, K., Cui, D., Lundström, M., Radiochimica Acta, 92(9-11), 625-629 (2004)Google Scholar
Gray, W.J. and Wilson, C.N. (1995) Spent Fuel Dissolution Studies FY 1991 to 1994, PNL-10540, Pacific Northwest National LaboratoryCrossRefGoogle Scholar
Puranen, A. et al., MRS Advances, Vol. 1(52), 4169-4175 (2016)CrossRefGoogle Scholar