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Separation of Uranium and Thorium for 230Th-U Dating of Submarine Hydrothermal Sulfides
Published on: May 20, 2019
Group hexavalent actinide separation from lanthanides using sodium bismuthate chromatography.
Samantha A Labb1, Kelly N Kmak2, John D Despotopulos2
1Department of Environmental and Radiological Health Sciences, Colorado State University, 1618 Campus Delivery, Fort Collins, CO, 94550 USA; Nuclear and Chemical Sciences Division, Lawrence Livermore National Laboratory, 7000 East Ave., Livermore, CA, 94550, USA.
Sodium bismuthate efficiently separates actinides from lanthanides in nuclear fuel reprocessing. This solid oxidant and ion exchanger offers a rapid, effective method for advanced nuclear waste management.
Area of Science:
- Nuclear Chemistry
- Radiochemistry
- Materials Science
Background:
- Advanced nuclear fuel reprocessing faces challenges in separating actinides (An) from lanthanides (Ln) due to complex radiochemical processes.
- The hexavalent oxidation state of actinides (Uranium to Americium) offers a potential route for selective group separation from trivalent lanthanides and Curium.
- Existing methods require intricate engineering and separations, limiting efficiency in nuclear waste management.
Purpose of the Study:
- To expand the application of sodium bismuthate (NaBiO3) chromatography for actinide/lanthanide separation.
- To characterize the adsorption, kinetic, and elution behavior of Uranium (U), Plutonium (Pu), and Europium (Eu) using NaBiO3.
- To evaluate the potential of NaBiO3-based separations in nuclear reprocessing, particularly after TRUEX processes.
Main Methods:
- Utilized column chromatography with sodium bismuthate (NaBiO3) as a solid oxidant and ion exchanger.
- Investigated the oxidation and separation of actinides (U, Pu) from lanthanides (Eu) in dilute nitric acid solutions.
- Characterized adsorption, kinetic, and elution behaviors of target elements and key fission products.
Main Results:
- Achieved quantitative oxidation and separation of actinides from lanthanides.
- Observed high separation factors (over 200) with rapid kinetics for U, Pu, and Am from Eu and Cm.
- Demonstrated complete actinide/lanthanide separation in under an hour.
- Characterized the behavior of key fission products, indicating compatibility with existing reprocessing streams.
Conclusions:
- Sodium bismuthate chromatography provides an effective and rapid method for separating actinides from lanthanides.
- This technique shows significant potential for improving advanced nuclear fuel reprocessing strategies.
- NaBiO3-based separation is a promising advancement for nuclear waste management and reprocessing applications.
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