Durability testing of an iodate-substituted hydroxyapatite designed for the conditioning of 129I

The safe management of iodine coming from spent nuclear fuels by storage in deep geological repositories requires durable materials. For this purpose, we have recently developed an iodate-substituted hydroxyapatite (HA-CaI). In the present article, the chemical durability of this material is assessed as a function of leaching media and apatite stoichiometry. First, the maximum rate for iodine release was determined in unsaturated conditions leading to a congruent dissolution of HA-CaI. In these conditions, the forward rate was equal to 2 x 10(-2) g m(-2) d(-1) at 50 degrees C independently of apatite stoichiometry. During this regime, dissolution was controlled by surface reaction and diffusion phenomena. When concentrations of calcium and phosphate ions in solution increased, the system became saturated towards non substituted hydroxyapatite Ca-10(PO4)(6)(OH)(2) and the rate of iodine release consecutively decreased. Consequently, tests were carried out to determine the behaviour of HA-CaI in such experimental conditions (saturated conditions), which were thought to be time-prevalent given the half-life of I-129 (15.7 million years). During this regime, also called residual regime, iodine was released in the solution at a constant rate without being trapped in a secondary phase. The residual rate at 50 degrees C on the basis of iodine release was of 10(-4) g m(-2) d(-1) in an initially deionized water, and it fell by one order of magnitude (r = 10(-5) g m(2) d(-1)) in a clay-equilibrated groundwater (hereafter called Callovo-oxfordian (COx) groundwater). This singular behaviour was ascribed to the presence of calcium in COx water. These preliminary results on the chemical durability of HA-CaI suggest that this material is a viable candidate as repository iodine waste form. (C) 2016 Elsevier B.V. All rights reserved.