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Preliminary study of spent UO2 fuel corrosion in the presence of bentonite |
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| Authors: | Roy S. Forsyth Lars O. Werme Jordi Bruno |
| Affiliation: | a Studsvik Energiteknik AB, S-611 82, Nyköping, Sweden b Swedish Nuclear Fuel and Waste Management Co., Box 5864, S-102 48, Stockholm, Sweden c Department of Inorganic Chemistry, Royal Institute of Technology, S-100 44, Stockholm, Sweden |
| Abstract: | The corrosion of spent UO2 fuel in the presence of a dilute suspension (1.5%) of bentonite in synthetic groundwater has been studied. No significant changes in the uranium concentrations no indications of increased corrosion due to changes in solution chemistry, or due to sorption was found when bentonite was introduced to the system. The measured uranium concentrations were (3 ± 2) × 10−6M in the presence as well as in the absence of bentonite. The concentrations of plutonium and cationic fission products in the aqueous phase were lowered considerably, by up to two orders of magnitude in the case of plutonium due to sorption onto the bentonite. |
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