Corrosion of high burn-up structured UO2 fuel in presence of dissolved H-2
Artikel i vetenskaplig tidskrift, 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
Författare
Patrik Fors
Chalmers, Kemi- och bioteknik, Kärnkemi
P. Carbol
Europeiska kommissionen (EU)
S. Van Winckel
Europeiska kommissionen (EU)
Kastriot Spahiu
Chalmers, Kemi- och bioteknik, Kärnkemi
Journal of Nuclear Materials
0022-3115 (ISSN)
Vol. 394 1 1-8DOI
10.1016/j.jnucmat.2009.07.004