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Updated: Jul 28, 2026

Speciation and Bioavailability Measurements of Environmental Plutonium Using Diffusion in Thin Films
Published on: November 9, 2015
Determination of 99Tc in TBP phase in spent nuclear fuel reprocessing with plastic scintillation resin
Man Wang1, Tianyi Jia1, Yiman Lu1
1School of Nuclear Science and Technology, Lanzhou University, Lanzhou, 730000, PR China.
Background:
Technetium-99 is a major radionuclide affecting the separation of uranium, plutonium and neptunium in the PUREX process of spent fuel reprocessing due to its strong redox feature. The rapid and reliable determination of 99Tc in TBP is very challenging, mainly due to the complexity of the sample matrix and the severe interference of radionuclides.
Results:
A rapid analytical method for the accurate determination of 99Tc in TBP organic phase was developed in this work. 99Tc was first back-extracted from TBP phase using a mixture of deionized water and carbon tetrachloride with an efficiency of 94.7 %, enabling to directly load to the plastic scintillation resin (TK-TcScint resin). 99Tc adsorbed on the TK-TcScint resin was then directly measured by liquid scintillation counting (LSC). Importantly, the quenching correction for the counting efficiency of 99Tc on the TK-TcScint resin was established for the first time. The excellent decontamination factors for all interferences (>105) in the spent fuel solution (e.g., Sr, Cs, Sm, Fe, Zr, Ru, U) were achieved. The minimum detectable activity for 99Tc in TBP phase was estimated to be 0.09 Bq/L with a counting time of 1 h, and the whole analytical procedure takes only about 2 h per batch of 12 samples.
Significance:
This rapid and reliable analytical method is crucial to monitor 99Tc in the TBP organic phase for the improvement of uranium-plutonium separation in the PUREX process. More importantly, the method with integrative separation and measurement analysis would be conducted for fully automated separation and measurement of 99Tc in spent fuel reprocessing.

