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Corrosion of high burn-up structured UO2 fuel in presence of dissolved H-2

Patrik Fors (Institutionen för kemi- och bioteknik, Kärnkemi) ; P. Carbol ; S. Van Winckel ; Kastriot Spahiu (Institutionen för kemi- och bioteknik, Kärnkemi)
Journal of Nuclear Materials (0022-3115). Vol. 394 (2009), 1, p. 1-8.
[Artikel, refereegranskad vetenskaplig]

The influence of high burn-up structured material on UO2 corrosion has been studied in an autoclave experiment. The experiment was conducted on spent fuel fragments with an average burn-up of 67 GWd/tHM. They were corroded in a simplified groundwater containing 33 mM dissolved H-2 for 502 days. All redox sensitive elements were reduced. The reduction continued until a steady-state concentration was reached in the leachate for U at 1.5 x 10(-10) M and for Pu at 7 x 10(-11) M. The instant release of Cs during the first 7 days was determined to 3.4% of the total inventory. However, the Cs release stopped after release of 3.5%. It was shown that the high burn-up structure did not enhance fuel corrosion. (C) 2009 Elsevier B.V. All rights reserved.

Nyckelord: HBS, High burn-up, Spent nuclear fuel, Corrosion, Irradiated, Reducing, condition, Hydrogen, Groundwater, near-field hydrogen, spent fuel, microstructure changes, radionuclide, release, product deposits, solubility, irradiation, simfuel, acidity, rim

Denna post skapades 2010-02-24.
CPL Pubid: 114527


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Institutioner (Chalmers)

Institutionen för kemi- och bioteknik, Kärnkemi (2005-2014)



Chalmers infrastruktur