Production of intense proton cyclotron using target and shell 225 Ac- 22 Na- 68 Method for production of germanium isotopes

Abstract

The application discloses a kind of strong current proton cyclotron production 225 Ac- 22 Na- 68 Method for producing Ge isotopes, comprising the following steps: selecting a plurality of target nuclides capable of fully utilizing the accelerator energy interval; each nuclide produces an energy interval corresponding to the production of two target nuclides, and the reaction cross-section peak region of one of the target nuclides corresponds to the reaction cross-section valley region of the other target nuclide; selecting target materials and shells for producing different target nuclides in different nuclide production energy intervals, in the same nuclide production energy region, the reaction cross-section peak region of the target nuclide produced by the target material corresponds to the reaction cross-section valley region of the target nuclide produced by the shell; or in the same nuclide production energy region, the reaction cross-section peak region of the target nuclide produced by the shell corresponds to the reaction cross-section valley region of the target nuclide produced by the target material; The present application converts the original radioactive waste into valuable products, reduces the production and processing cost of radioactive waste, and realizes the recycling of resources.

Description

Technical Field

[0001] This invention belongs to the field of radioactive isotope production technology for cyclotron accelerators, specifically providing a method for producing radioactive isotopes using a target and shell in a high-current proton cyclotron accelerator. 225 Ac- 22 Na- 68 Ge isotope method Background Technology

[0002] Medium- and high-energy accelerators above 30 MeV are used in the preparation of medical isotopes. 68 During Ge generation, capsule-shaped target structures are typically used for irradiation production. The capsule shell material is often made of metals such as aluminum and niobium, which offer advantages in encapsulating the target material, maintaining target structural stability, and thermal conductivity. However, under prolonged bombardment by high-current proton beams, the capsule shell itself inevitably becomes activated, generating various radioactive isotopes, such as aluminum shells². 7 Al may produce 22 Na, etc., niobium shell 93 Nb may generate 88 Zr and other nuclides. These activation products make the irradiated capsule shells highly radioactive, and they are currently generally treated as radioactive solid waste. This not only increases the steps and costs of waste disposal, but also wastes certain material resources, thus significantly increasing the risk of radioactive contamination. 68 The overall production cost of Ge limits its development into large-scale, economical production. Summary of the Invention

[0003] This invention addresses the issue that capsule shells produce a large amount of radioactive isotopes after irradiation with an accelerator beam. It proposes a high-current proton cyclotron accelerator method that utilizes a target material and a shell to produce these radioactive isotopes. 225 Ac- 22 Na- 68 The method of using Ge isotopes turns waste into treasure.

[0004] To solve its technical problems, the present invention proposes the following technical solutions: A high-current proton cyclotron accelerator is produced using a target and a shell. 225 Ac- 22 Na- 68 A method for producing Ge isotopes, based on a high-current proton cyclotron accelerator using a target and a shell. 225 Ac- 22 Na- 68The system of Ge isotopes has an outermost aluminum support (1) and a second outermost cooling water (2). Within the second outermost cooling water (2), along the proton beam incident direction, a first target capsule shell (3) and a first target material (5) contained within the first target capsule shell (3), a second target capsule shell (4), and a second target material (6) contained within the second target capsule shell (4) are sequentially arranged. The proton beam generated by the accelerator passes through the incident window of the aluminum support (1), and then passes through a portion of the cooling water sequentially onto the first target front capsule shell (3-1), the first target material (5), the first target rear capsule shell (3-2), 2mm of cooling water, the second target front capsule shell (4-1), the second target material (6), and the second target rear capsule shell (4-2). The accelerator energy range is 0 to 75 MeV. The method is characterized by the following steps: Step 1: Select multiple target nuclides that can fully utilize the accelerator's energy range: 225 Ac- 22 Na - 68 Ge, the multiple target nuclides are provided with multiple nuclide production energy ranges within the accelerator energy range: 68MeV-70MeV, 50MeV-68MeV, 47MeV-50MeV, 40MeV-44.5MeV, 11MeV-40MeV; each nuclide production energy range corresponds to the production of two target nuclides, and the reaction cross-section peak region of one target nuclide corresponds to the reaction cross-section valley region of the other target nuclide; Step 2: Select targets and shells for producing different target nuclides within different energy ranges for nuclide production. Specifically, the beam is directed onto the capsule shell to produce... 22 The energy ranges of Na are 68 MeV-70 MeV, 47 MeV-50 MeV, and 40 MeV-44.5 MeV, respectively; the beam is incident on the target to produce... 225 Ac and 68 The energy range of Ge: in sequence, the first target material (5) production 225 The energy range of Ac is 50MeV-68MeV, and the production of the second target (6) 68 The energy range of Ge is 11MeV-40MeV; within the same nuclide production energy range, the peak region of the reaction cross section of the target nuclide produced by the target material corresponds to the valley region of the reaction cross section of the target nuclide produced by the shell; or within the same nuclide production energy range, the peak region of the reaction cross section of the target nuclide produced by the shell corresponds to the valley region of the reaction cross section of the target nuclide produced by the target material. Furthermore, each nuclide production energy range in step one corresponds to the production of two target nuclides, with the peak region of the reaction cross section of one target nuclide corresponding to the valley region of the reaction cross section of the other target nuclide, specifically: The target nuclide corresponds to the energy range of 68 MeV-70 MeV.22 Na and 225 Ac, where the target nuclide 22 The reaction cross section of Na is the peak region, and the target nuclide is... 225 The reaction cross section of Ac is the valley region; Target nuclides in the 50MeV-68MeV energy range 225 Ac and 227 Ac, where the target nuclide 225 The reaction cross section of Ac is the peak region, and the target nuclide 227 The reaction cross section of Ac is the valley region; The target nuclide corresponds to the energy range of 47 MeV-50 MeV. 22 Na and 225 Ac, where the target nuclide 22 The reaction cross section of Na is the peak region, and the target nuclide is... 225 The reaction cross section of Ac is the valley region; The target nuclide corresponds to the energy range of 40 MeV-44.5 MeV. 22 Na and 225 Ac, where the target nuclide 22 The reaction cross section of Na is the peak region, and the target nuclide is... 225 The reaction cross section of Ac is the valley region; Target nuclides in the 11MeV-40MeV energy range 22 Na and 68 Ge, of which the target nuclide 68 The reaction cross section of Ge is the peak region, and the target nuclide is... 22 The reaction cross section of Na is a valley region; Furthermore, in step two, the beam is incident on the target to produce... 225 Ac and 68 The energy range of Ge is, in order, the first target material (5) production 225 The energy range of Ac is 50MeV-68MeV, and the second target material 6 is produced. 68 Ge has an energy range of 11 MeV-40 MeV, specifically: 1) When producing the target nuclide 225 When using Ac, select the first target material (5). 232 Th(p,x) 225 Ac, and determine the first target (5). 232 The thickness of Th(p,x) is 3.01 mm; the first target material (5) 232 The energy range of Th(p,x) is 50MeV-68MeV, and this range is the first target material (5). 232 Th(p,x) 225The peak region of Ac is also the first target material, the capsule shell (3-1). 27 Al(p,x) 22 Na's valley region; 2) When producing the target nuclide 68 When Ga is used, the second target material is selected (5). net Ga(p,x) 68 Ga; and determine the second target (6) net The thickness of Ga(p,x) is 3.68 mm; the second target (6) net Ga(p,x) 68 Ge has an energy range of 11 MeV-40 MeV, and this range is the second target material (6). net Ga(p,x) 68 The peak region of Ga is also the precapsule shell of the second target material (4-1). net Ga(p,x) 22 Na's valley region; Furthermore, in step two, the beam is injected onto the capsule shell to produce... 22 The energy ranges of Na are 68 MeV-70 MeV, 47 MeV-50 MeV, and 40 MeV-44.5 MeV, respectively. 1) When producing the target nuclide 22 When Na, select the shell. 27 Al(p,x) 22 Na, shell 27 A1 consists of the first target material front capsule shell (3-1), the first target material rear capsule shell (3-2), and the second target material front capsule shell (4-1). 2) Selecting the shell 27 Al(p,x) 22 The energy ranges with relatively high Na reaction cross-sections are 68 MeV-70 MeV, 47 MeV-50 MeV, and 40 MeV-44.5 MeV, corresponding to the energy ranges for nuclide production in the first target pre-capsule shell (3-1), the first target post-capsule shell (3-2), and the second target pre-capsule shell (4-1), respectively; the energy range of 66 MeV-70 MeV is the energy range for target nuclide production in the first target pre-capsule shell (3-1). 22 The peak region of Na is also the first target material (5). 232 Th(p,x) 225 The valley region of Ac; the energy range of 47MeV-50MeV is the first target material after the capsule shell (3-2) to produce the target nuclide. 22 The peak region of Na is also the first target material (5). 232 Th(p,x) 225 Ac valley region; energy range 40MeV-44.5MeV. MeV is the first post-target capsule shell (3-2) for producing target nuclides.22 The peak region of Na is also the first target material (5). 232 Th(p,x) 225 The valley area of ​​Ac; 3) Determine the thickness of the shell: The thicknesses of the first target front capsule shell (3-1), the first target rear capsule shell (3-2), the cooling water, and the second target front capsule shell (4-1) are calculated to be 1mm, 1.12mm, 2mm, and 1.51mm respectively. Advantages and effects of the present invention

[0005] 1. This invention employs a cascaded composite structure of "capsule shell + internal target material". The proton beam first passes through the capsule shell, exciting a nuclear reaction within its optimal energy range to produce the first target nuclide. The remaining energy of the beam continues into the internal target material, producing the second target nuclide within another optimal energy range. Unlike existing technologies where the capsule shell is merely used as an inert encapsulation material, this invention transforms the capsule shell into a functional activation component, enabling the simultaneous production of multiple isotopes in a single proton irradiation, thus improving beam utilization efficiency and total yield per irradiation cycle.

[0006] 2. This invention utilizes functionalized encapsulation materials to "turn waste into treasure." The originally inert capsule shell material (such as aluminum) is replaced or designed into a functional material capable of producing high-value isotopes (such as Na²⁺). During irradiation, the capsule shell itself participates in the production reaction of the target nuclide. This completely changes the existing model of treating irradiated capsule shells as radioactive waste, transforming them into valuable products. This not only significantly reduces the amount and cost of radioactive waste, but also effectively lowers the overall production cost of isotopes through resource recycling, resulting in significant economic and environmental benefits.

[0007] 3. Co-design of nuclear reactions to achieve "purity optimization". This invention employs meticulous co-design of energy ranges at the nuclear reaction level. By selecting materials and energy parameters, the optimal production energy range (reaction cross-section peak region) of one target nuclide is matched with the low-yield or impurity-generating range (reaction cross-section valley region) of another target nuclide. Through energy spectrum "peak shaving and valley filling," this invention cleverly suppresses the occurrence of non-target nuclear reactions, thereby effectively improving the radiochemical purity of the target product, simplifying subsequent chemical separation and purification processes, and further enhancing production efficiency and economy. Attached Figure Description

[0008] Figure 1 This invention relates to the production of a high-current proton cyclotron accelerator using a target and a shell. 225 Ac- 22 Na- 68 A schematic diagram of the Ge isotopes system; Figure 2This invention relates to the production of a high-current proton cyclotron accelerator using a target and a shell. 225 Ac- 22 Na- 68 A schematic diagram of the method for using Ge isotopes.

[0009] In the diagram: 1: Aluminum support; 2: Cooling water; 3: First target capsule shell; 3-1: Front capsule shell of the first target; 3-2: Rear capsule shell of the first target; 4-1: Front capsule shell of the second target; 4-2: Rear capsule shell of the second target; 4: Second target capsule shell; 4-1: Front capsule shell of the second target; 4-2: Rear capsule shell of the second target; 5: First target; 6: Second target. Detailed Implementation Innovation of this invention

[0010] 1. An innovative cascaded structure of "capsule shell + internal target material" is adopted to form a composite target. When the proton beam passes through the shell, it first produces one isotope within the capsule shell at its optimal energy range; the remaining energy of the beam then enters the internal target material to produce a second isotope at a different energy range. This fully utilizes the energy deposition of the proton beam in different energy ranges, enabling the production of multiple isotopes with a single irradiation, greatly improving the utilization efficiency of the proton beam and the overall isotope yield.

[0011] 2. Turning waste into treasure and achieving comprehensive utilization of materials: This invention designs the capsule shell itself as a material capable of producing target isotopes. By carefully selecting the materials for the shell and the internal target, different useful nuclides are produced in different energy ranges. This transforms what was originally radioactive waste into valuable products, significantly reducing the amount and cost of radioactive waste disposal, and achieving resource recycling.

[0012] 3. Collaborative Design for Optimized Product Purity and Production Efficiency. This invention employs a meticulous collaborative design of energy ranges. The optimal production energy range (reaction cross-section peak region) for one target nuclide is matched with the low-yield range (reaction cross-section valley region) for another target nuclide. This design cleverly avoids triggering unnecessary nuclear reactions within non-target energy ranges, thereby effectively reducing the formation of impurity nuclides, improving the radiochemical purity of the target product, and simplifying subsequent separation and purification processes.

[0013] In summary, this invention organically combines three innovative strategies—shell functionalization, target cascading, and energy range synergy—to form a new, efficient, economical, and environmentally friendly method for producing radioactive isotopes. Key design points of this invention

[0014] 1. Synergistic design at the nuclear reaction level: "peak-valley matching" of energy window and reaction cross-section: simultaneously and efficiently producing multiple nuclides (such as²² 5Ac, ²²Na, 68 (Ge), ensuring product purity. The optimal production "window" is found for different nuclides across the entire energy range of the proton beam. The key innovation lies in carefully selecting energy ranges so that the optimal production energy (reaction cross-section peak) for one nuclide corresponds to the low-yield or impurity-generating energy (reaction cross-section valley) for another nuclide. This fundamentally reduces interference between different nuclide production pathways, significantly improves the radiochemical purity of the target product, and simplifies subsequent complex chemical separation processes.

[0015] 2. Innovative Design at the Target Structure Level: Capsule-Cascaded Targets and Multifunctional Materials: Maximizing the energy of the proton beam to achieve tandem irradiation of multiple targets. A tandem design of "shell + internal target" is adopted. The proton beam first penetrates the outer shell, producing the first nuclide in a specific high-energy range; the beam, after energy decay, then enters the internal target, producing the second nuclide in an optimized low-energy range. Material Selection and Thickness Optimization: Precise calculation and selection of target materials (such as...) ²³² Th, ⁿᵃᵗ Ga) and shell material (such as ²7 The type and thickness of Al (Al) were carefully controlled to manage proton beam energy loss, ensuring optimal reaction energy at each stage while also considering thermal management and material irradiation stability. This enabled multi-target cascading, significantly improving proton beam utilization. Multiple isotopes can be produced in a single irradiation, with the total nuclide yield per unit beam far exceeding that of traditional fractional irradiation.

[0016] 3. Value-added design at the resource and efficiency level: turning waste into treasure and comprehensive material utilization. The capsule shells, traditionally considered structural components or waste, are designed as targets for producing useful isotopes (e.g., using aluminum shells to produce Na²²). This achieves comprehensive material utilization. What was originally radioactive "waste" is transformed into high-value byproducts, significantly reducing the amount and burden of radioactive waste disposal, and improving the economic efficiency and environmental friendliness of the entire production process.

[0017] Based on the above principles, this invention designs a high-current proton cyclotron accelerator that utilizes a target material and a shell for production. 225 Ac- 22 Na- 68 A method for producing Ge isotopes, based on a high-current proton cyclotron accelerator using a target and a shell. 225 Ac- 22 Na- 68The system uses Ge isotopes, with an outermost aluminum support 1 and a second outermost cooling water layer 2. Within the second outermost cooling water layer 2, along the proton beam incident direction, a first target capsule shell 3, a first target 5 inside the first target capsule shell 3, a second target capsule shell 4, and a second target 6 inside the second target capsule shell 4 are sequentially arranged. The proton beam generated by the accelerator, after passing through the incident window of the aluminum support 1, first passes through a portion of the cooling water and sequentially enters the first target front capsule shell 3-1, the first target 5, the first target rear capsule shell 3-2, 2mm of cooling water, the second target front capsule shell 4-1, the second target 6, and the second target rear capsule shell 4-2. The accelerator energy range is 0 to 75 MeV. The method is characterized by the following steps: Step 1: Select multiple target nuclides that can fully utilize the accelerator's energy range: 225 Ac- 22 Na - 68 Ge, the multiple target nuclides are provided with multiple nuclide production energy ranges within the accelerator energy range: 68MeV-70MeV, 50MeV-68MeV, 47MeV-50MeV, 40MeV-44.5MeV, 11MeV-40MeV; each nuclide production energy range corresponds to the production of two target nuclides, and the reaction cross-section peak region of one target nuclide corresponds to the reaction cross-section valley region of the other target nuclide; Step 2: Select targets and shells for producing different target nuclides within different energy ranges for nuclide production. Specifically, the beam is directed onto the capsule shell to produce... 22 The energy ranges of Na are 68 MeV-70 MeV, 47 MeV-50 MeV, and 40 MeV-44.5 MeV, respectively; the beam is incident on the target to produce... 225 Ac and 68 The energy range of Ge: sequentially, is the production of the first target material 5. 225 The energy range of Ac is 50MeV-68MeV, and the second target material 6 is produced. 68 The energy range of Ge is 11MeV-40MeV; within the same nuclide production energy range, the peak region of the reaction cross section of the target nuclide produced by the target material corresponds to the valley region of the reaction cross section of the target nuclide produced by the shell; or within the same nuclide production energy range, the peak region of the reaction cross section of the target nuclide produced by the shell corresponds to the valley region of the reaction cross section of the target nuclide produced by the target material. Furthermore, each nuclide production energy range in step one corresponds to the production of two target nuclides, with the peak region of the reaction cross section of one target nuclide corresponding to the valley region of the reaction cross section of the other target nuclide, specifically: The target nuclide corresponds to the energy range of 68 MeV-70 MeV. 22 Na and 225 Ac, where the target nuclide22 The reaction cross section of Na is the peak region, and the target nuclide is... 225 The reaction cross section of Ac is the valley region; Target nuclides in the 50MeV-68MeV energy range 225 Ac and 227 Ac, where the target nuclide 225 The reaction cross section of Ac is the peak region, and the target nuclide 227 The reaction cross section of Ac is the valley region; The target nuclide corresponds to the energy range of 47 MeV-50 MeV. 22 Na and 225 Ac, where the target nuclide 22 The reaction cross section of Na is the peak region, and the target nuclide is... 225 The reaction cross section of Ac is the valley region; The target nuclide corresponds to the energy range of 40 MeV-44.5 MeV. 22 Na and 225 Ac, where the target nuclide 22 The reaction cross section of Na is the peak region, and the target nuclide is... 225 The reaction cross section of Ac is the valley region; Target nuclides in the 11MeV-40MeV energy range 22 Na and 68 Ge, of which the target nuclide 68 The reaction cross section of Ge is the peak region, and the target nuclide is... 22 The reaction cross section of Na is a valley region; Furthermore, in step two, the beam is incident on the target to produce... 225 Ac and 68 The energy range of Ge is, in order, the first target material 5 production 225 The energy range of Ac is 50MeV-68MeV, and the second target material 6 is produced. 68 Ge has an energy range of 11 MeV-40 MeV, specifically: 1) When producing the target nuclide 225 When Ac is selected, the first target material 5 is chosen. 232 Th(p,x) 225 Ac, and determine the first target 5 232 The thickness of Th(p,x) is 3.01 mm; the first target material 5 232 The energy range of Th(p,x) is 50MeV-68MeV, and this range is the first target material 5. 232 Th(p,x) 225 The peak region of Ac is also the first target material precapsule shell 3-1 27 Al(p,x) 22 Na's valley region; 2) When producing the target nuclide 68 When Ga is selected, the second target material 5 is chosen. net Ga(p,x) 68 Ga; and determine the second target material 6 net The thickness of Ga(p,x) is 3.68 mm; the second target material is 6. net Ga(p,x) 68 Ge has an energy range of 11 MeV-40 MeV, and this range is the second target material 6. net Ga(p,x) 68 The peak region of Ga is also the precapsule shell of the second target material 4-1 net Ga(p,x) 22 Na's valley region; Furthermore, in step two, the beam is injected onto the capsule shell to produce... 22 The energy ranges of Na are 68 MeV-70 MeV, 47 MeV-50 MeV, and 40 MeV-44.5 MeV, respectively. 1) When producing the target nuclide 22 When Na, select the shell. 27 Al(p,x) 22 Na, shell 27 A1 consists of the first target material front capsule shell 3-1, the first target material rear capsule shell 3-2, and the second target material front capsule shell 4-1; 2) Selecting the shell 27 Al(p,x) 22 The energy ranges with relatively high Na reaction cross-sections are: 68 MeV-70 MeV, 47 MeV-50 MeV, and 40 MeV-44.5 MeV, corresponding to the energy ranges for nuclide production in the first target front capsule shell 3-1, the first target rear capsule shell 3-2, and the second target front capsule shell 4-1, respectively; the energy range of 66 MeV-70 MeV is the energy range for target nuclide production in the first target front capsule shell 3-1. 22 The peak region of Na, which is also the first target material 5 232 Th(p,x) 225 The valley region of Ac; the energy range of 47MeV-50MeV is the target nuclide produced by the first target material after capsule shell 3-2. 22 The peak region of Na, which is also the first target material 5 232 Th(p,x) 225 Ac valley region; energy range 40MeV-44.5MeV. MeV is the target nuclide for the first post-target capsule shell 3-2 production. 22 The peak region of Na, which is also the first target material 5 232 Th(p,x) 225 The valley area of ​​Ac; 3) Determine the thickness of the shell: The thicknesses of the first target material front capsule shell (3-1), the first target material rear capsule shell 3-2, the cooling water, and the second target material front capsule shell 4-1 are calculated to be 1mm, 1.12mm, 2mm, and 1.51mm respectively. Example 1

[0018] A physical design method for isotope production cascade targets in cyclotron accelerators; the specific implementation of this technical solution can be found by referring to... Figure 1 As shown, the entire system includes an aluminum support 1, cooling water 2, 3 is the first target capsule shell 3, the second target capsule shell 4, the first target 5, and the second target 6.

[0019] Taking the 75MeV high-current proton cyclotron accelerator as an example, such as Figure 1 As shown, the aluminum support 1 encloses the target material 5 and the cooling water 2. After the proton beam generated by the accelerator passes through the entrance window on the outer shell, it first passes through a portion of the cooling water 2 and is sequentially injected onto the first target material front capsule shell 3-1, the first target material 5, the first target material rear capsule shell 3-2, 2mm of cooling water, the second target material front capsule shell 4-1, the second target material 6, and the second target material front capsule shell 4-2.

[0020] Depend on Figure 2 It can be seen that the energy range from 68MeV to 50MeV is achieved through... 232 Th(p,x) 225 Ac reaction produces 225 A peak region of Ac, and at the same time 232 Th(p,x) 227 Ac reaction produces 227 The valley area of ​​Ac is a production area. 225 Ac has a higher irradiation range with a higher reaction cross section.

[0021] Figure 1 The thickness and deposition energy of the structure shown were precisely calculated using Monte Carlo software. The proton beam generated by the 75 MeV proton accelerator, after passing through the incident window on the aluminum support 1, first passes through a portion of the cooling water before entering the first target front capsule shell 3-1, at which point the energy is 70 MeV. At this point, the first target front capsule shell 3-1 produces… 225The energy range of Ac is 68MeV-70MeV, and the required thickness for this energy range is calculated to be 1mm (the thickness of the first target's front capsule shell 3-1). At this point, the beam is incident on the first target 5, with an energy range of 50MeV-68MeV. The required thickness for this energy range is calculated to be 3.01mm (the thickness of the first target 5). Then, the beam is sequentially incident on the first target's rear capsule shell 3-2, 2mm of cooling water, the second target's front capsule shell 4-1, the second target 6, and the second target's rear capsule shell 4-2. The calculated thicknesses are 1.12mm (first target's rear capsule shell 3-2), 2mm, 1.51mm (second target's front capsule shell 4-1), 3.68mm (second target 6), and 0.3mm (second target's rear capsule shell 4-2), respectively.

[0022] like Figure 2 As shown, the dashed line encloses the portion where the beam is injected onto the capsule shell during production. 22 The energy ranges for Na are 68 MeV-70 MeV, 47 MeV-50 MeV, and 40 MeV-44.5 MeV, respectively. The area outside the dashed line represents the energy produced when the beam is incident on the first target 5. 225 Ac's energy range, production of the first target material 5 225 The energy range of Ac is 50MeV-70MeV, and the second target material 6 is produced. 68 Ge has an energy range of 11 MeV to 40 MeV.

[0023] This invention, through theory and Monte Carlo calculations, maximizes the production of radioactive isotopes by minimizing proton beam loss in the energy region of the first target 5, while also ensuring that there is a suitable energy region loss in the first target 6. It also enables the production of target isotopes in the capsule shell at a suitable energy range, thereby improving the utilization rate of the proton beam, making reasonable use of the excitation curves of different target materials, increasing the variety and output of nuclides produced, and enhancing the efficiency of isotope production.

[0024] It should be emphasized that the above specific embodiments are merely explanations of the present invention and are not intended to limit the present invention. After reading this specification, those skilled in the art can make modifications to the above embodiments without contributing any inventive step, but as long as they are within the scope of the claims of the present invention, they are protected by patent law.

Claims

1. A high-current proton cyclotron accelerator manufactured using a target and a shell. 225 Ac- 22 Na- 68 A method for producing Ge isotopes, based on a high-current proton cyclotron accelerator using a target and a shell. 225 Ac- 22 Na- 68 The system of Ge isotopes has an outermost aluminum support (1) and a second outermost cooling water (2). Within the second outermost cooling water (2), along the proton beam incident direction, a first target capsule shell (3) and a first target (5) contained within the first target capsule shell (3), a second target capsule shell (4), and a second target (6) contained within the second target capsule shell (4) are sequentially arranged. The proton beam generated by the accelerator passes through the incident window of the aluminum support (1), and then passes through a portion of the cooling water sequentially onto the first target front capsule shell (3-1), the first target (5), the first target rear capsule shell (3-2), 2mm of cooling water, the second target front capsule shell (4-1), the second target (6), and the second target rear capsule shell (4-2). The accelerator energy range is 0 to 75 MeV. Its characteristics are... The method includes the following steps: Step 1: Select multiple target nuclides that can fully utilize the accelerator's energy range: 225 Ac- 22 Na - 68 Ge, the multiple target nuclides are provided with multiple nuclide production energy ranges within the accelerator energy range: 68MeV-70MeV, 50MeV-68MeV, 47MeV-50MeV, 40MeV-44.5MeV, 11MeV-40MeV; each nuclide production energy range corresponds to the production of two target nuclides, and the reaction cross-section peak region of one target nuclide corresponds to the reaction cross-section valley region of the other target nuclide; Step 2: Select targets and shells for producing different target nuclides within different energy ranges for nuclide production. Specifically, the beam is directed onto the capsule shell to produce... 22 The energy ranges of Na are 68 MeV-70 MeV, 47 MeV-50 MeV, and 40 MeV-44.5 MeV, respectively; the beam is incident on the target to produce... 225 Ac and 68 The energy range of Ge: in sequence, the first target material (5) production 225 The energy range of Ac is 50MeV-68MeV, and the production of the second target (6) 68 The energy range of Ge is 11MeV-40MeV; within the same nuclide production energy range, the peak region of the reaction cross section of the target nuclide produced by the target material corresponds to the valley region of the reaction cross section of the target nuclide produced by the shell; or within the same nuclide production energy range, the peak region of the reaction cross section of the target nuclide produced by the shell corresponds to the valley region of the reaction cross section of the target nuclide produced by the target material.

2. The high-current proton cyclotron accelerator according to claim 1 is manufactured using a target and a shell. 225 Ac- 22 Na- 68 The method for using Ge isotopes is characterized by: Each nuclide production energy range in step one corresponds to the production of two target nuclides, with the peak region of the reaction cross section of one target nuclide corresponding to the valley region of the reaction cross section of the other target nuclide. Specifically: The target nuclide corresponds to the energy range of 68 MeV-70 MeV. 22 Na and 225 Ac, where the target nuclide 22 The reaction cross section of Na is the peak region, and the target nuclide is... 225 The reaction cross section of Ac is the valley region; Target nuclides in the 50MeV-68MeV energy range 225 Ac and 227 Ac, where the target nuclide 225 The reaction cross section of Ac is the peak region, and the target nuclide 227 The reaction cross section of Ac is the valley region; The target nuclide corresponds to the energy range of 47 MeV-50 MeV. 22 Na and 225 Ac, where the target nuclide 22 The reaction cross section of Na is the peak region, and the target nuclide is... 225 The reaction cross section of Ac is the valley region; The target nuclide corresponds to the energy range of 40 MeV-44.5 MeV. 22 Na and 225 Ac, where the target nuclide 22 The reaction cross section of Na is the peak region, and the target nuclide is... 225 The reaction cross section of Ac is the valley region; Target nuclides in the 11MeV-40MeV energy range 22 Na and 68 Ge, of which the target nuclide 68 The reaction cross section of Ge is the peak region, and the target nuclide is... 22 The reaction cross section of Na is the valley region.

3. The high-current proton cyclotron accelerator according to claim 1 is manufactured using a target and a shell. 225 Ac- 22 Na- 68 The method for using Ge isotopes is characterized by: In step two, the beam is directed onto the target to produce... 225 Ac and 68 The energy range of Ge is, in order, the first target material (5) production 225 The energy range of Ac is 50MeV-68MeV, and the second target material 6 is produced. 68 Ge has an energy range of 11 MeV-40 MeV, specifically: 1) When producing the target nuclide 225 When using Ac, select the first target material (5). 232 Th(p,x) 225 Ac, and determine the first target (5). 232 The thickness of Th(p,x) is 3.01 mm; the first target material (5) 232 The energy range of Th(p,x) is 50MeV-68MeV, and this range is the first target material (5). 232 Th(p,x) 225 The peak region of Ac is also the first target material for the capsule shell (3-1). 27 Al(p,x) 22 Na's valley region; 2) When producing the target nuclide 68 When Ga is used, the second target material is selected (5). net Ga(p,x) 68 Ga; and determine the second target (6) net The thickness of Ga(p,x) is 3.68 mm; the second target (6) net Ga(p,x) 68 Ge has an energy range of 11 MeV-40 MeV, and this range is the second target material (6). net Ga(p,x) 68 The peak region of Ga is also the front capsule shell of the second target material (4-1). net Ga(p,x) 22 The valley region of Na.

4. The high-current proton cyclotron accelerator according to claim 1, produced using a target and a shell. 225 Ac- 22 Na- 68 The method for using Ge isotopes is characterized by: In step two, the beam is injected onto the capsule shell to produce... 22 The energy ranges of Na are 68 MeV-70 MeV, 47 MeV-50 MeV, and 40 MeV-44.5 MeV, respectively. 1) When producing the target nuclide 22 When Na, select the shell. 27 Al(p,x) 22 Na, shell 27 A1 consists of the first target material front capsule shell (3-1), the first target material rear capsule shell (3-2), and the second target material front capsule shell (4-1). 2) Selecting the shell 27 Al(p,x) 22 The energy ranges with relatively high Na reaction cross-sections are 68 MeV-70 MeV, 47 MeV-50 MeV, and 40 MeV-44.5 MeV, corresponding to the energy ranges for nuclide production in the first target pre-capsule shell (3-1), the first target post-capsule shell (3-2), and the second target pre-capsule shell (4-1), respectively; the energy range of 66 MeV-70 MeV is the energy range for target nuclide production in the first target pre-capsule shell (3-1). 22 The peak region of Na is also the first target material (5). 232 Th(p,x) 225 The valley region of Ac; the energy range of 47MeV-50MeV is the first target material after the capsule shell (3-2) to produce the target nuclide. 22 The peak region of Na is also the first target material (5). 232 Th(p,x) 225 Ac valley region; energy range 40MeV-44.5MeV. MeV is the first post-target capsule shell (3-2) for producing target nuclides. 22 The peak region of Na is also the first target material (5). 232 Th(p,x) 225 Ac's valley area; 3) Determine the thickness of the shell: The thicknesses of the first target front capsule shell (3-1), the first target rear capsule shell (3-2), the cooling water, and the second target front capsule shell (4-1) are calculated to be 1mm, 1.12mm, 2mm, and 1.51mm respectively.

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