Rates and mechanisms of radioactive release and retention inside a waste disposal canister (IN CAN PROCESSES)


Project leader


Funding source

EU Fifth Framework Programme


Project Details

Start date: 01/09/2000
End date: 31/08/2003
Funding: 750000 EUR


Description

This project will use an innovative method based on isotope dilution measurements to determine the actual dissolution rate of uranium dioxide and spent nuclear fuel as a function of radiation dose and redox conditions. The results will remove the present uncertainties in source term estimates due to precipitation of secondary phases during experiments. Other studies will measure the rate of reduction of oxidized forms of U and Np when they encounter solutions that contain actively corroding iron, which represents the interior of a waste disposal canister. Theoretical calculations concerning expected solution concentrations and rates of reduction reactions will support and elucidate the experimental results. These calculations will also be used to evaluate the data base information used in repository performance assessments.


External Partners


Last updated on 2017-24-03 at 12:54