Stacked Irradiation Target Assembly for Faster Mo-99 Processing
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Solution Overview
Problem
There is a need for a timely production process of titanium-molybdate-99 materials suitable for use in technetium-99m generators, as existing methods involve centralized production of molybdenum-99 in high-flux nuclear reactors, which are limited in number and require rapid processing due to Mo-99's short half-life.
Innovation Solution
An irradiation target system comprising plates and an elongated central member formed of materials that produce molybdenum-99 through neutron capture, along with a debundling tool for efficient disassembly, facilitating the production of titanium-molybdate-99 for technetium-99m generators.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Quantity of substance
If centralized production of Mo-99 in high-flux nuclear reactors is used, then Mo-99 can be produced in sufficient quantity, but the production time is extended and the number of production sites is limited
Solution Approach 1:
The irradiation target is segmented into multiple plates stacked together, allowing parallel processing of multiple target units. This segmentation enables simultaneous irradiation of multiple plates in a single reactor load, increasing overall Mo-99 production quantity while maintaining efficient use of reactor time.
Solution Approach 2:
The target plates are nested around a central member that passes through all plates, creating a compact stacked structure. This nested arrangement maximizes the use of reactor irradiation space and allows multiple target plates to be processed simultaneously, thereby increasing production quantity without proportionally increasing production time.
2Adaptability or versatility
If Mo-99 is produced and shipped to manufacturing sites, then Tc-99m generators can be distributed to hospitals, but the short half-life of Mo-99 requires rapid processing
Solution Approach 1:
The irradiation target is designed with pre-assembled stacked plates and a central member that facilitates rapid disassembly after irradiation. This preliminary structural preparation enables quick processing and conversion of Mo-99 to Tc-99m generators, reducing the time loss associated with the short half-life of Mo-99 while maintaining the ability to distribute generators to multiple locations.
3Productivity
If multiple plates are stacked on a central member, then irradiation efficiency is improved, but disassembly and processing complexity increases
Solution Approach 1:
The central member is designed as a separate extractable component that can be easily removed from the stacked plates after irradiation. This extraction design simplifies disassembly by allowing the central member to be taken out first, followed by separation of individual plates, thereby reducing processing complexity while maintaining irradiation efficiency during the stacked configuration.
Solution Approach 2:
The target plates are designed as disposable components that are irradiated and then discarded after a single use. This approach simplifies the overall system by eliminating the need for complex reassembly or refurbishment processes, reducing disassembly complexity while maintaining high irradiation efficiency during the operational phase.
Data Source
AI summary
An irradiation target for the production of radioisotopes comprises a plurality of plates having aligned central openings. First and second elongated central members extend in opposite directions through the aligned central openings of the plates. The first and second elongated central members each have a pair of wings at first and second ends of the plurality of plates, respectively. The first and second elongated central members further have a pair of tabs adjacent to the wings of the other elongated central member. Tabs of the first elongated central member are bent to engage one end face of the plurality of plates. Tabs of the second elongated central member are folded over the wings of the first elongated central member. The plates and the first and second elongated central members are formed of materials that produce molybdenum-99 (Mo-99) by way of neutron capture.