Article ID Journal Published Year Pages File Type
1567674 Journal of Nuclear Materials 2009 8 Pages PDF
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 67 GWd/tHM. They were corroded in a simplified groundwater containing 33 mM dissolved H2 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 × 10−10 M and for Pu at 7 × 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.
Related Topics
Physical Sciences and Engineering Energy Nuclear Energy and Engineering
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