Stacked Irradiation Target for Mo-99 Production
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Solution Overview
Problem
The existing methods for producing titanium-molybdate-99 materials for technetium-99m generators are inefficient due to the short half-life of molybdenum-99, requiring timely reduction to a usable form, which is hindered by limited production sites and long transportation times.
Innovation Solution
An irradiation target system comprising plates and an elongated central member, both formed from materials capable of producing molybdenum-99 through neutron capture, designed to minimize processing time by facilitating efficient neutron capture and subsequent dissolution of molybdenum-99 into a usable form.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Productivity
If traditional irradiation targets are used for Mo-99 production, then Mo-99 can be produced, but the production time is too long and processing is inefficient due to the short half-life of Mo-99
Solution Approach 1:
The irradiation target is divided into multiple plates arranged in a stack, with each plate separated by spacers. This segmentation increases the total surface area for neutron capture while maintaining a compact structure, thereby improving production efficiency and reducing processing time for Mo-99 generation
Solution Approach 2:
The invention transitions from a single-plane target design to a three-dimensional stacked configuration of multiple plates. By utilizing the vertical dimension and arranging plates in layers with spacers, the target achieves increased neutron capture capacity within a compact volume, addressing the time efficiency challenge
2Quantity of substance
If highly-enriched uranium targets are used, then Mo-99 can be produced, but the number of production sites is limited and transportation time is long
Solution Approach 1:
The invention modifies the target material composition by using titanium-molybdate compounds instead of traditional highly-enriched uranium. This parameter change enables Mo-99 production at more locations, reducing transportation time while maintaining production quantity through optimized neutron capture cross-sections
3Reliability
If Mo-99 is produced and shipped to generator manufacturing sites, then Tc-99m generators can be produced, but the short half-life of Mo-99 requires minimization of time in processing
Solution Approach 1:
The irradiation target is pre-designed with integrated spacers and plate configurations that facilitate rapid disassembly and processing after irradiation. This preliminary structural preparation enables quick reduction of Mo-99 to usable form, ensuring timely delivery to generator manufacturing sites and maintaining generator reliability
Data Source
AI summary
An irradiation target for the production of radioisotopes, comprising at least one plate defining a central opening and an elongated central member passing through the central opening of the at least one plate so that the at least one plate is retained thereon, wherein the at least one plate and the elongated central member are both formed of materials that produce molybdenum-99 (Mo-99) by way of neutron capture.