Multi-Layer Zinc Target for 67Cu Production
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Solution Overview
Problem
Current methods for producing 67Cu in nuclear medicine face limitations due to high co-production of contaminating 64Cu, resulting in low final activity and inefficient production processes, particularly when using high-energy proton beams with zinc targets.
Innovation Solution
A method utilizing a multi-layer target composed of different zinc isotopes (70Zn and 68Zn) to optimize the production of 67Cu up to 70 MeV, maximizing its production while minimizing 64Cu co-production, by varying the energy range and using a proton beam with specific energy and thickness configurations.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Quantity of substance
If a thick 68Zn target is used to increase 67Cu production, then the final activity of 67Cu is improved, but the co-production of contaminating 64Cu increases significantly
Solution Approach 1:
The target is divided into multiple layers with different zinc isotopes (68Zn and 70Zn) arranged in specific sequences. This segmentation allows different regions of the target to produce different radionuclides, enabling 67Cu production while minimizing 64Cu contamination by controlling which isotopes are exposed to specific proton beam energy ranges.
Solution Approach 2:
Different layers of the target have different isotopic compositions (enriched in either 68Zn or 70Zn) tailored to specific energy ranges. The 68Zn-enriched layers are positioned to capture protons at energies optimal for 67Cu production, while 70Zn-enriched layers are positioned to avoid producing 64Cu, creating local quality variations that optimize the overall production ratio.
2Productivity
If the proton beam energy range is extended to maximize 67Cu production, then the productivity is improved, but the co-production of 64Cu increases
Solution Approach 1:
The energy range of the proton beam is segmented across different target layers. Lower energy protons (optimal for 67Cu) are directed at 68Zn-enriched layers, while higher energy protons (which would produce 64Cu) are directed at 70Zn-enriched layers or stopped before reaching sensitive regions, thus maintaining high productivity without increasing contamination.
Solution Approach 2:
The invention changes the isotopic composition parameter of the target material at different depths and positions. By varying the zinc isotope enrichment (68Zn vs 70Zn) and the physical parameters (thickness, density) of different layers, the nuclear reaction outcomes are optimized to favor 67Cu production while suppressing 64Cu formation across the full energy range.
3Loss of time
If waiting time for 64Cu decay is reduced to improve workflow efficiency, then the loss of time is reduced, but the purity of 67Cu decreases
Solution Approach 1:
The target is designed with 70Zn-enriched layers that prevent 64Cu formation during irradiation in the first place. By preliminarily configuring the isotopic composition to avoid harmful byproduct generation, the need for extended decay waiting periods is eliminated, allowing immediate processing while maintaining high purity.
Data Source
Figure 1
Figure 2~3
Figure 4A
AI summary
The present invention relates to a method for the production of 67Cu which provides for disposing a target (1) comprising a first layer (2) of zinc-enriched in 70Zn and a second layer (4) of zinc-enriched in 68Zn placed adjacent to the first layer (2), providing a proton beam (3), exposing the target (1) to the proton beam (3) from the side of the first layer (2) so that the proton beam (3) passes through, in the order, first the first layer (2) and then the second layer (4), and subjecting the target (1) to radiochemical treatment in a radiochemical unit (5). The invention also refers to a target (1) for the production of 67Cu through exposure to a proton beam (3). Advantageously, the present invention finds application in the industrial field for the realization of high-power targets for the production of high quantities of 67Cu, specifically for medical applications, and for the development of automatic modules for the extraction and purification of 67Cu from the irradiated material.