Corrosion of high burn-up structured UO2 fuel in presence of dissolved H-2
Journal article, 2009
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.
release
spent fuel
condition
radionuclide
High burn-up
rim
acidity
simfuel
solubility
near-field hydrogen
Hydrogen
Groundwater
product deposits
HBS
Spent nuclear fuel
microstructure changes
Corrosion
Reducing
Irradiated
irradiation
Author
Patrik Fors
Chalmers, Chemical and Biological Engineering, Nuclear Chemistry
P. Carbol
European Commission (EC)
S. Van Winckel
European Commission (EC)
Kastriot Spahiu
Chalmers, Chemical and Biological Engineering, Nuclear Chemistry
Journal of Nuclear Materials
0022-3115 (ISSN)
Vol. 394 1 1-8DOI
10.1016/j.jnucmat.2009.07.004