Physico-chemical cement matrix characterization tests for ion exchange resins from a NPP

The characterization of materials used for immobilization of radioactive waste is a fundamental task to demonstrate the suitability, security and viability of the locations used for its interim or final disposal. This report covers the results obtained in the experiments carried out in the L and I Radioactive Waste Unit of CIEMAT aimed to obtain the better mixture to immobilize the operation spent ion exchange resins from a nuclear power plant (NPP) according to particular technical specifications. The assays was planned and carried out in two phases. The first phase to decide the optimal formulation and the second one in order to attest the qualification of the selected formulation according to the technical specifications proposed. It has been performed tests of resin humidity, consistency and aspect of the mixture, cement mechanical properties after different curing periods and storage conditions, cement setting time and leaching behaviour of Cs-137 and Co-60. (authors)