Separation and recovery of iodide in radioactive waste for 129I

For the disposal of low-level radwaste from nuclear power plant need the determination of levels of radio nuclides in radwaste. These nuclides include the difficult-to-measure nuclides, so indirect methodology for the determination of the difficult-to-measure nuclides have to be developed. In this work, for the determination of 129I(t1/2=1.57X107 years) in low-level radwaste from nuclear power plant is investigated. Recovery of iodide in simulated waste(UO2 pellet) as a soluble and radwaste(resin, woolen fabric)as a insoluble samples are measured. After pretreatment of sample, I2 are extracted from aqueous solution with CCL4. Then I- are extracted from CCl4 with 0.1M NaHSO3 aqueous solution. Iodide in aqueous solution are determined by ion chromatography. The overall recovery yield is 76.7 (RSD 1.7%) for mixed-acid digestion method. In case of woolen fabrics, overall recovery yield is 74.3 (RSD 2.2%) and recovery of iodide in resin 56.5 (RSD 5.6%) for alkaline fusion method