Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1567674 | Journal of Nuclear Materials | 2009 | 8 Pages |
Abstract
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 67Â GWd/tHM. They were corroded in a simplified groundwater containing 33Â mM dissolved H2 for 502Â days. All redox sensitive elements were reduced. The reduction continued until a steady-state concentration was reached in the leachate for U at 1.5Â ÃÂ 10â10Â M and for Pu at 7Â ÃÂ 10â11Â M. The instant release of Cs during the first 7Â 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.
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Authors
P. Fors, P. Carbol, S. Van Winckel, K. Spahiu,