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Hydrogen Production and Utilization in a Membrane Reactor
Published on: March 10, 2023
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Reactor production of promethium-147
Kathleen Broderick1, Rita Lusk2, James Hinderer2
1Nuclear Security and Isotope Technology Divisions, Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA; Department of Chemistry and Biochemistry, Tennessee Technological University, Cookeville, TN 38505, USA.
Summary
This study details the production of Promethium-147 (Pm-147) using Neodymium-146 (Nd-146) targets, optimizing yields and purity for beta voltaic batteries. It also refines neutron capture cross-section data for Pm isotopes.
Area of Science:
- Nuclear Chemistry and Materials Science
- Radioisotope Production and Applications
Background:
- The production of Promethium-147 (Pm-147) is crucial for applications like beta voltaic batteries.
- Accurate cross-section data for Neodymium-146 (Nd-146) and Promethium isotopes are essential for optimizing production yields.
- Efficient separation techniques are needed to achieve high-purity Pm-147.
Purpose of the Study:
- To determine optimal production yields and impurity levels of Pm-147 from irradiated Nd-146 targets.
- To experimentally evaluate neutron capture cross-sections for Pm-148m and Pm-148g.
- To develop and validate a chemical separation process for high-purity Pm-147.
Main Methods:
- Irradiation of milligram quantities of highly enriched Nd-146 oxide at the High Flux Isotope Reactor (HFIR).
- Comparison of theoretical and experimental production data, including neutron capture cross-section evaluations.
- Development of a chemical separation process using extraction chromatography (LN resin) and ion-exchange chromatography.
Main Results:
- Maximum Pm-147 yield of 101.8 MBq/mg achieved at 60 days post-bombardment for a ~24-day irradiation.
- Experimental neutron capture cross-sections for Pm-147 to Pm-148m and Pm-148g were found to be lower than theoretical calculations.
- A chemical process achieving a mass separation factor >10^4 for Pm from Nd was developed, yielding high-purity Pm-147.
Conclusions:
- Curie quantities of high-purity Pm-147 suitable for beta voltaic batteries can be produced by irradiating gram quantities of Nd-146.
- The study provides refined experimental cross-section data for Pm isotopes, improving production models.
- The developed chemical separation method is effective for producing radiochemically pure Pm-147.
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