Polymer Cement Stabilized Radioactive Waste Ion Exchange Resin Formulations

Spent ion-exchange resin is the main low and intermediate level wet solid waste in the operation of nuclear power stations,reprocessing plants and decontamination of nuclear facilities. With the development of nuclear power stations and the increasing the capacity of reprocessing plants, the amount of spent ion exchange resin will increase year by year. Spent resin need to be immobilized, in order to avoid radioactivity dispersing into environment. Applying normal design and correlative computer software, a new solidified material and an excellent waste formulation were developed. Based on the theory calculations and normal design in this test, the formulation tests were carried out withpolymer complex cement as solidified matrix mixed with simulated spent resin. Then thecharacterization of solidified waste after curing has been done. The results satisfied the treatment of the waste about the requirements of GB14569.1-93. Leaching index of the solidified waste was excellent. An optimized formulation was recommended. The leach curve of Sr appeared a maximum point at the third day, which was explained by a mathematical model. The diffusion theory and chemical kinetics first-order formed this model. Apparent diffusion coefficient value was calculated.