Determination of 93Zr in radioactive waste using ion exchange techniques
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Abstract
This paper describes a simple and rapid method of 93Zr pre-concentration, separation and purification by using cation and anion exchange resins which are commercially available from Eichrom Technologies, Inc.,. The method is suitable for analyzing high contaminated radioactive waste samples in a relatively short time and high decontamination factors. The use and effectiveness of this method was successfully tested by analysis of heterogeneous waste from nuclear power plant and samples from nuclear reactor and fuel parts such as control rod drive shaft and neutron absorbers, shielding cassettes and neutron in-core measurement channels (KNI) samples.
Keywords
Zirconium-93 separation Anion exchangerNotes
Acknowledgments
This work was supported by the Slovak Research and Development Agency under the contract no. APVV-20-007105.
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