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The objective of this project was the source term quantification for spent fuel performance asessment in granite, clay and salt formations. Four materials were studied under a variety of conditions.

MOX fuel shows significantly higher release rates for Pu and other radionuclides than UOX fuel. The generation reaction mechanism of the spent UOX fuel matrix dissolution was found to be similar in various geological formations. Differences in UOX spent fuel corrosion rates were explained by the effect of groundwater consitutents on solubility, surface complex formation and electrochemical corrosion potentials. Key parameters were radiation field, redox conditions and carbonate concentrations. Salinity and humic acid concentrations were less significant. In the presence of repository rock and iron, spent fuel matrix dissolution rates are as similar as in their absence, but the environmental materials retained upto 99% of the total released radioactivity. Partial pressures of hydrogen of 2.7 bar were observed to reduce spent fuel corrosion rates by a factor of 500. Coprecipitation was found to be an important retention mechanism for actinides. .

Additional information

Bibliographic Reference: EUR 19140 EN (2000), 355pp.
Availability: Available from EUR-OP sales agents
ISBN: ISBN 92-828-9168-2
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