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A method for preparation and purification of 234Th
Y Albinsson1, C Ekberg, S Holgersson
1Department of Nuclear Chemistry, Chalmers University of Technology, Gothenburg, Sweden. ya@nc.chalmers.se
Summary
A new method efficiently recovers thorium-234 (234Th) from depleted uranium using solvent extraction and ion-exchange. This process yields high-purity 234Th suitable for sensitive research and offers a reusable uranium source.
Area of Science:
- Nuclear Chemistry
- Radiochemistry
- Separation Science
Background:
- Depleted uranium (DU) contains significant quantities of thorium-234 (234Th), a valuable radioisotope.
- Efficient recovery methods for 234Th from DU are crucial for its application in scientific research.
Purpose of the Study:
- To develop and present an improved method for recovering 234Th from depleted uranium.
- To characterize the purity and specific activity of the recovered 234Th.
- To assess the potential of the remaining uranium fraction as a 234Th generator.
Main Methods:
- Solvent extraction techniques were employed for initial separation.
- Ion-exchange chromatography was utilized for purification of the thorium fraction.
- Specific activity measurements were performed on the final product.
Main Results:
- The developed method successfully recovers 234Th from depleted uranium.
- The final thorium fraction exhibits a high specific activity, ranging from 1-3 PBq/mol Th.
- The overall processing time for the method is approximately 2 days.
- The remaining uranium fraction can serve as a 234Th generator for several years.
Conclusions:
- The improved method provides a fast and effective means to obtain high-purity 234Th.
- The recovered 234Th is suitable for investigations requiring low thorium concentrations.
- The dual utility of the process, providing both purified 234Th and a long-term generator, enhances its value.