Influence of Plutonium on the Dissolution Behavior of the Spent-Fuel Matrix

摘要

The aim of this wok is to characterize the oxidation state and the dissolution behaviour of Pu and U from the matrix of simulated spent nuclear fuel during storage in a geologic repository. The quantification of the effects of Pu on the dissolution of the fuel matrix in contact with groundwater will provide necessary information to establish a comprehensive prediction of the long-term corrosion behaviour of the fuel.