High-intensity proton cyclotron accelerators utilize target materials and shells for production. 68 Ge- 88 Zr- 93 mMo isotope method

Abstract

The application designs a method for producing Mo isotopes by using a target and a shell in a strong current proton cyclotron 68 Ge- 88 Zr- 93m The method comprises the following steps: selecting multiple target nuclides capable of fully utilizing the energy interval of the accelerator; producing two target nuclides corresponding to the energy interval of each nuclide, wherein the reaction cross-section peak region of one target nuclide corresponds to the reaction cross-section valley region of the other target nuclide; selecting the target and the shell for producing different target nuclides in different nuclide production energy intervals, and in the same nuclide production energy region, the reaction cross-section peak region of the target for producing the target nuclide corresponds to the reaction cross-section valley region of the shell for producing the target nuclide; or in the same nuclide production energy region, the reaction cross-section peak region of the shell for producing the target nuclide corresponds to the reaction cross-section valley region of the target for producing the target nuclide. The capsule cascade target maximizes the production of radioactive isotopes, reduces the irradiation cost of the accelerator operation, and improves the production efficiency of isotopes.

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. 68 Ge- 88 Zr- 93 Methods using mMo isotopes. 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. 68 Ge- 88 Zr- 93m The method using M 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. 68 Ge- 88 Zr- 93m A method for producing Mo isotopes, based on a high-current proton cyclotron accelerator using a target and a shell. 68 Ge- 88 Zr- 93mThe system of Mo 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, there are sequentially arranged 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). The proton beam generated by the accelerator passes through the incident window of the aluminum support (1) and, after passing through a portion of the cooling water, is sequentially incident 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. The method is characterized by the following steps: Step 1: Select multiple target nuclides that can fully utilize the accelerator's energy range: 68 Ge- 88 Zr- 93m Mo, the multiple target nuclides are provided with multiple nuclide production energy ranges within the accelerator energy range: 66MeV-70MeV, 43MeV-66MeV, 39.65MeV-43MeV, 34MeV-36.5MeV, 12.5MeV-34MeV, and 0-12.5MeV. 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. Furthermore, the beam is injected onto the capsule shell to produce... 88 Zr、 93m The energy ranges of Mo are 66 MeV-70 MeV, 39.65 MeV-43 MeV, 34 MeV-36.5 MeV, and 0-12.5 MeV, respectively; the beam is irradiated onto the target to produce... 68 The energy range of Ge is, in order, the first target material (5) production 68 The energy range of Ge is 43MeV-66MeV, and the energy range of the second target (6) for producing Ge-68 is 12.5MeV-34MeV. Within the same nuclide production energy range, the peak region of the reaction section of the target nuclide produced by the target material corresponds to the valley region of the reaction section of the target nuclide produced by the shell. Or, within the same nuclide production energy range, the peak region of the reaction section of the target nuclide produced by the shell corresponds to the valley region of the reaction section of the target nuclide produced by the target material.

[0005] 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 66 MeV-70 MeV. 88Zr and 68 Ge, of which the target nuclide 88 The reaction cross section of Zr is the peak region, and the target nuclide... 68 The reaction cross section of Ge is a valley region; The target nuclide corresponds to the energy range of 43 MeV-66 MeV. 88 Zr and 68 Ge, of which the target nuclide 68 The reaction cross section of Ge is the peak region, and the target nuclide is... 88 The reaction cross section of Zr is a valley region; The target nuclide corresponds to the energy range of 39.65 MeV-43 MeV. 88 Zr and 68 Ge, of which the target nuclide 88 The reaction cross section of Zr is the peak region, and the target nuclide... 68 The reaction cross section of Ge is a valley region; The target nuclide corresponds to the energy range of 34 MeV-36.5 MeV. 88 Zr and 68 Ge, of which the target nuclide 88 The reaction cross section of Zr is the peak region, and the target nuclide... 68 The reaction cross section of Ge is a valley region; Target nuclides in the energy range of 12.5 MeV-34 MeV 88 Zr and 68 Ge, of which the target nuclide 68 The reaction cross section of Ge is the peak region, and the target nuclide is... 88 The reaction cross section of Zr is a valley region; The target nuclide corresponds to the energy range of 0-12.5 MeV. 93m Mohe 68 Ge, of which the target nuclide 93m The reaction cross section of Mo is the peak region, and the target nuclide is... 68 The reaction cross section of Ge is a valley region.

[0006] Furthermore, the beam is directed onto the target to produce... 68 The energy range of Ge is, in order, the first target material (5) production 68 Ge has an energy range of 43MeV-66MeV, and the second target material (6) is produced. 68 Ge has an energy range of 12.5 MeV-34 MeV, specifically: When the target nuclide is produced 68When Ge is selected, a first target (5) and a second target (6) are chosen. The energy range of the first target (5) is 43MeV-66MeV, and this range is the range in which the first target (5) produces nuclides. 68 The peak region of Ge, and also the first target material for capsule shell (3-1) production. 88 Zr valley area; production of the second target material (6) 68 Ge has an energy range of 12.5 MeV to 34 MeV, and this range is the area where the second target (6) produces nuclides. 68 The peak region of Ga, and also the production of the second target material, the capsule shell (4-1). 88 The valley region of Zr. The thicknesses of the first target material (5) and the second target material (6) are calculated to be 5.24 mm and 2.56 mm, respectively.

[0007] Furthermore, the beam is injected onto the capsule shell to produce... 88 The energy ranges of Zr are 66 MeV-70 MeV, 39.65 MeV-43 MeV, and 34 MeV-36.5 MeV, respectively. 1) When producing the target nuclide 88 When using Zr, select the shell. 93 Nb, the shell consists of a first target material front capsule shell (3-1), a first target material rear capsule shell (3-2), and a second target material front capsule shell (4-1). 2) Selecting the shell 93 Nb production 88 The energy ranges with relatively high Zr reaction cross-sections are: 66 MeV-70 MeV, 39.65 MeV-43 MeV, and 34 MeV-36.5 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 the production of target nuclei in the first target pre-capsule shell (3-1). 88 The peak region of Zr is also the production area of ​​the first target material (5). 68 The valley region of Ge; the energy range of 39.65 MeV-43 MeV is the first target material after the capsule shell (3-2) to produce the target nuclide. 88 The peak region of Zr is also the production area of ​​the first target material (5). 68 The valley region of Ge; the energy range of 34MeV-36.5MeV is the first post-target capsule shell (3-2) for the production of target nuclides. 88 The peak region of Zr is also the production area of ​​the first target material (5). 68 Ge'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 0.78mm, 0.45mm, 2mm, and 0.3mm respectively.

[0008] Furthermore, the beam is injected onto the capsule shell to produce... 93m The energy of Mo is 0-12.5 MeV, specifically: 1) When producing the target nuclide 93m When selecting a housing (Mo), choose the appropriate housing. 93 Nb production target nuclide, shell 93 Nb is the second target material behind the capsule shell (4-2). 2) Select shell production 93m The Mo reaction cross-section has a relatively high energy range of 0-12.5 MeV, which corresponds to the energy range for nuclide production by the capsule shell (4-2) after the second target material; the energy range of 0-12.5 MeV is the energy range for the production of target nuclei by the capsule shell (4-2) after the second target material. 93m The peak region of Mo is also the production area of ​​the second target material (6). 68 Ge's valley area; 3) Determine the thickness of the shell: The thickness of the capsule shell (4-2) after the second target material is 0.42 mm.

[0009] 3) Determine the thickness of the shell: The thickness of the capsule shell (4-2) after the second target material is 0.42 mm. Advantages and effects of the present invention

[0010] 1. This invention addresses the needs of radioisotope production in cyclotron accelerators by redesigning the traditional single irradiation target into a capsule cascade target with different target materials. This design maximizes the yield of radioisotopes by minimizing proton beam loss in the energy region of the first target material, while also ensuring suitable energy loss in the second target material and appropriate energy ranges for isotope production within the capsule shell. This improves proton beam utilization, rationally utilizes the excitation curves of different target materials, increases the variety and yield of nuclides produced, and avoids cross-contamination of target components. Consequently, it reduces accelerator operation irradiation costs and enhances isotope production efficiency.

[0011] 2. 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 serves merely 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.

[0012] 3. 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.

[0013] 4. 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

[0014] Figure 1 This invention relates to a high-current proton cyclotron accelerator manufactured using a target and a shell. 68 Ge- 88 Zr- 93 A schematic diagram of the mMo isotope system.

[0015] Figure 2 This invention relates to a high-current proton cyclotron accelerator manufactured using a target material and a shell. 68 Ge- 88 Zr- 93 A schematic diagram of the mMo isotope method.

[0016] 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

[0017] 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.

[0018] 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.

[0019] 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.

[0020] 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. Design principle of the invention

[0021] I. Design Principle of Multi-Target Cascade and Coordinated Energy Utilization. This is the basic architecture of the entire invention. In the traditional single-target production mode, after the high-energy proton beam deposits energy in the target material, the remaining energy is wasted, resulting in low beam utilization. This invention transforms a single target material into a "cascaded reactor," allowing the proton beam to pass through multiple target material units sequentially, like passing through a series of carefully designed "energy filters." The proton beam travels along a preset path (front capsule shell → internal target material → rear capsule shell → cooling water → next target unit…), with energy attenuating at each stage. The wide-energy range of 0-75 MeV proton beam is "segmented" according to energy ranges, with each segment of energy used to produce a specific isotope best suited for that energy range (e.g., high energy for 68Ge, medium energy for 88Zr, and low energy for 93mMo), thus achieving "multi-purpose use of one beam," greatly improving beam utilization efficiency and the overall output of a single irradiation.

[0022] II. Design Principles of Waste Resource Utilization. This represents a breakthrough in materials science and environmental protection concepts based on macroscopic structure. Traditional encapsulation capsule shells become radioactive waste after irradiation due to activation, increasing treatment costs and environmental burden. This invention overturns the traditional concept that "encapsulation materials are inert," upgrading them from "structural components" to "functional components." By actively selecting specific capsule shell materials (such as...) 93 Radioactive waste (Nb) can undergo nuclear reactions when bombarded by a proton beam, generating economically valuable target isotopes (such as 93mMo). What was originally intended as a discarded "packaging box" is transformed into a high-value product. This approach minimizes the generation of radioactive waste at its source, achieves resource recycling, significantly reduces the overall production cost of isotopes, and embodies advanced green and environmentally friendly concepts.

[0023] III. Design Principles for Synergistic Nuclear Reaction and Purity Optimization. This is the ingenious control strategy that ensures the efficient and high-quality realization of the first two innovations, and it is the essence of the design. When multiple targets are connected in series, improper design can lead to side reactions in non-optimal energy regions, producing impurity nuclides, affecting the radiochemical purity of the final product, and increasing the difficulty and cost of subsequent chemical separation. This is achieved through precise "peak-valley matching" energy region design. This considers not only "what energy to use for production" but also "what energy to avoid using for production." Peak utilization: Ensuring that when the proton beam enters each target, its energy falls precisely in the peak region of the reaction cross-section where the target nuclide is produced ("peak"), to achieve the highest yield. Valley avoidance: Simultaneously, by adjusting the thickness of the preceding target / capsule shell, the energy of the proton beam decays precisely to an energy region ("valley") that will not cause severe impurity nuclides to be produced in the subsequent materials after passing through them. The thickness of the first target (Ga target) and its capsule shell is designed such that the proton beam enters the Ga target at an energy of 66 MeV (the peak region for 68Ge production), while the energy drops to 43 MeV upon exit. This 43 MeV is precisely the valley region for 88Zr production in the first capsule shell (Y target), thus suppressing the formation of 88Zr impurities in the Y target.

[0024] In summary, this invention is not a simple superposition of three isolated ideas, but rather a highly synergistic organic whole: "Multi-target cascade" is the skeleton, creating the possibility of segmented energy utilization; "waste resource utilization" is the flesh and blood, giving each component of the skeleton production value; and "nuclear reaction synergy" is the nerve center, ensuring the efficient and pure operation of the entire system through precise energy control. Ultimately, this methodology enables the simultaneous, efficient, and high-purity production of multiple high-value medical isotopes with a single proton beam irradiation, while significantly reducing radioactive waste, representing an important development direction for radioactive isotope production technology.

[0025] Based on the above principles, this invention designs a high-current proton cyclotron accelerator that utilizes a target material and a shell for production. 68 Ge-88 Zr- 93m A method for producing Mo isotopes, based on a high-current proton cyclotron accelerator using a target and a shell. 68 Ge- 88 Zr- 93m The system of Mo 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, a second target capsule shell 4, and a second target 6 are sequentially arranged. The proton beam generated by the accelerator passes through the incident window of the aluminum support 1 and, after passing through a portion of the cooling water, is sequentially incident 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. The method is characterized by the following steps: Step 1: Select multiple target nuclides that can fully utilize the accelerator's energy range: 68 Ge- 88 Zr- 93m Mo, the multiple target nuclides are provided with multiple nuclide production energy ranges within the accelerator energy range: 66MeV-70MeV, 43MeV-66MeV, 39.65MeV-43MeV, 34MeV-36.5MeV, 12.5MeV-34MeV, and 0-12.5MeV. 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... 88 Zr、 93m The energy ranges of Mo are 66 MeV-70 MeV, 39.65 MeV-43 MeV, 34 MeV-36.5 MeV, and 0-12.5 MeV, respectively; the beam is irradiated onto the target to produce... 68 The energy range of Ge is, in order, the first target material 5 production 68 The energy range of Ge is 43 MeV-66 MeV, and the energy range of Ge-68 produced by the second target 6 is 12.5 MeV-34 MeV. 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.

[0026] 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 66 MeV-70 MeV. 88 Zr and 68 Ge, of which the target nuclide 88 The reaction cross section of Zr is the peak region, and the target nuclide... 68 The reaction cross section of Ge is a valley region; The target nuclide corresponds to the energy range of 43 MeV-66 MeV. 88 Zr and 68 Ge, of which the target nuclide 68 The reaction cross section of Ge is the peak region, and the target nuclide is... 88 The reaction cross section of Zr is a valley region; The target nuclide corresponds to the energy range of 39.65 MeV-43 MeV. 88 Zr and 68 Ge, of which the target nuclide 88 The reaction cross section of Zr is the peak region, and the target nuclide... 68 The reaction cross section of Ge is a valley region; The target nuclide corresponds to the energy range of 34 MeV-36.5 MeV. 88 Zr and 68 Ge, of which the target nuclide 88 The reaction cross section of Zr is the peak region, and the target nuclide... 68 The reaction cross section of Ge is a valley region; Target nuclides in the energy range of 12.5 MeV-34 MeV 88 Zr and 68 Ge, of which the target nuclide 68 The reaction cross section of Ge is the peak region, and the target nuclide is... 88 The reaction cross section of Zr is a valley region; The target nuclide corresponds to the energy range of 0-12.5 MeV. 93m Mohe 68 Ge, of which the target nuclide 93m The reaction cross section of Mo is the peak region, and the target nuclide is... 68 The reaction cross section of Ge is a valley region.

[0027] Furthermore, the beam is directed onto the target to produce... 68 The energy range of Ge is, in order, the first target material 5 production 68Ge has an energy range of 43 MeV-66 MeV, and the second target material 6 is produced. 68 Ge has an energy range of 12.5 MeV-34 MeV, specifically: When the target nuclide is produced 68 When Ge is selected, the first target 5 and the second target 6 are chosen. The energy range of the first target 5 is 43MeV-66MeV, and this range is the range in which the first target 5 produces nuclides. 68 The peak region of Ge, and also the first target material precapsule shell 3-1 production 88 Zr valley area; production of the second target material 6 68 Ge has an energy range of 12.5 MeV-34 MeV, and this range is the area from which the second target material 6 produces nuclides. 68 The peak region of Ga, and also the production of the second target material, pre-capsule shell 4-1. 88 The valley region of Zr. The thicknesses of the first target material 5 and the second target material 6 are calculated to be 5.24 mm and 2.56 mm, respectively.

[0028] Furthermore, the beam is injected onto the capsule shell to produce... 88 The energy ranges of Zr are 66 MeV-70 MeV, 39.65 MeV-43 MeV, and 34 MeV-36.5 MeV, respectively. 1) When producing the target nuclide 88 When using Zr, select the shell. 93 Nb, the shell is a first target material front capsule shell 3-1, a first target material rear capsule shell 3-2 and a second target material front capsule shell 4-1; 2) Selecting the shell 93 Nb production 88 The energy ranges with relatively high Zr reaction cross-sections are: 66 MeV-70 MeV, 39.65 MeV-43 MeV, and 34 MeV-36.5 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 the production of target nuclei in the first target front capsule shell 3-1. 88 The peak region of Zr is also the production area of ​​the first target material 5. 68 The valley region of Ge; the energy range of 39.65 MeV-43 MeV is the target nuclide produced by the first target material and the capsule shell 3-2. 88 The peak region of Zr is also the production area of ​​the first target material 5. 68 The valley region of Ge; the energy range of 34MeV-36.5MeV is the first target material capsule shell 3-2 for the production of target nuclides. 88 The peak region of Zr is also the production area of ​​the first target material 5. 68 Ge's valley area; 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 0.78mm, 0.45mm, 2mm, and 0.3mm respectively.

[0029] Furthermore, the beam is injected onto the capsule shell to produce... 93m The energy of Mo is 0-12.5 MeV, specifically: 1) When producing the target nuclide 93m When selecting a housing (Mo), choose the appropriate housing. 93 Nb production target nuclide, shell 93 Nb is the second target material after capsule shell 4-2; 2) Select shell production 93m The Mo reaction cross-section has a relatively high energy range of 0-12.5 MeV, which corresponds to the energy range for nuclide production in the capsule shell 4-2 after the second target material. The energy range of 0-12.5 MeV is the target nuclide produced by the capsule shell 4-2 after the second target material. 93m The peak region of Mo is also the production area of ​​the second target material 6. 68 Ge's valley area; 3) Determine the thickness of the shell: The thickness of the capsule shell 4-2 after the second target material is 0.42mm. Example 1

[0030] 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, a first target capsule shell 3, a second target capsule shell 4, a first target 5, and a second target 6.

[0031] 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 and cooling water. 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 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 rear capsule shell 4-2.

[0032] The thicknesses of the first target 5 and the second target 6, as well as the thickness of the capsule shell, are precisely calculated using Monte Carlo software. Figure 2 As shown, nat Ga(p,x) 68 The reaction threshold of Ge is at 11 MeV, compared with 93 Nb(p,x) 93 Compared to 12.5 MeV, the reaction cross-section of the mMo reaction is larger if the production of 93 mMo is also considered, while 12.5 MeV-34 MeV is... natGa(p,x) 68 The required thickness for the high Ge reaction cross section is calculated to be 2.56 mm (second target 6), and the thickness of the capsule shell 4-2 behind the second target is 0.42 mm (second target capsule shell 4-2). The deposition energy range is 0-12.5 MeV.

[0033] To suit 68 For Ge production, the energy range of the first target rear capsule shell 3-2, 2mm cooling water, and the second target front capsule shell 4-1 can be 34-43 MeV (exceeding 43 MeV will have a certain impact on the yield of 68Ge). For safety reasons, to prevent target leakage, the capsule shell thickness is at least 0.3mm (for the first target rear capsule shell 3-2 and the second target front capsule shell 4-1). This ensures that within the 34-43 MeV range of the three-layer structure (first target rear capsule shell 3-2, 2mm cooling water, and second target rear capsule shell 4-1),... 88 To maximize Zr production, the thicknesses of the first target material, the capsule shell 3-2, the cooling water, and the second target material, the capsule shell 4-1, are calculated to be 0.45mm (first target material, capsule shell 3-2), 2mm, and 0.3mm (second target material, capsule shell 4-1), respectively, with energy ranges of 39.65MeV-43MeV, 36.5MeV-39.65MeV, and 34MeV-36.5MeV.

[0034] Production at 66MeV 88 Zr's reaction cross section and production 68 The reaction cross section of Ge is basically the same, therefore 43MeV-66MeV is nat Ga(p,x) 68 The region with a relatively high Ge reaction cross section requires a thickness of 5.24 mm (the thickness of the second target material 6) based on calculations. The proton beam generated by the 75 MeV proton accelerator, after passing through the entrance window on the target holder, first passes through a portion of the cooling water before entering the first target material's front capsule shell 3-1 at an energy of 70 MeV. At this point, the first target material's front capsule shell 3-1 produces... 88 The energy range of Zr can be 66MeV-70MeV. Calculations show that the required thickness for this energy range is 0.78mm (the thickness of the first target material, the capsule shell 3-1).

[0035] The dashed lines represent the energy ranges for the production of Zr-88 and Mo-93m by the beam incident on the capsule shell, which are 66 MeV-70 MeV, 39.65 MeV-43 MeV, 34 MeV-36.5 MeV, and 0-12.5 MeV, respectively. Target 1 produces Ge-68 in the energy range of 43 MeV-66 MeV, while the second target 6 produces Ge-68 in the energy range of 12.5 MeV-34 MeV.

[0036] 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 allowing for suitable energy loss in the second target 6, and simultaneously enabling isotope production within the capsule shell at a suitable energy level. This improves the utilization rate of the proton beam, rationally utilizes the excitation curves of different targets, increases the variety and yield of nuclides produced, and enhances the efficiency of isotope production.

[0037] 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. 68 Ge- 88 Zr- 93m A method for producing Mo isotopes, based on a high-current proton cyclotron accelerator using a target and a shell. 68 Ge- 88 Zr- 93m The system of Mo isotopes has an outermost layer of aluminum support (1) and a second outermost layer of cooling water (2). Within the second outermost layer of cooling water (2), along the proton beam incident direction, are sequentially arranged a first target capsule shell (3), 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). The proton beam generated by the accelerator passes through the incident window of the aluminum support (1) and, after passing through a portion of the cooling water, is sequentially incident 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: 68 Ge- 88 Zr- 93m Mo, the plurality of target nuclides are provided with a plurality of nuclide production energy intervals 66-70 MeV, 43-66 MeV, 39.65-43 MeV, 34-36.5 MeV, 12.5-34 MeV, 0-12.5 MeV in the accelerator energy interval, each nuclide production energy interval 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... 88 Zr、 93m The energy ranges of Mo are 66 MeV-70 MeV, 39.65 MeV-43 MeV, 34 MeV-36.5 MeV, and 0-12.5 MeV, respectively; the beam is irradiated onto the target to produce... 68 The energy range of Ge is, in order, the first target material (5) production 68 The energy range of Ge is 43MeV-66MeV, and the energy range of the second target (6) for producing Ge-68 is 12.5MeV-34MeV. Within the same nuclide production energy range, the peak region of the reaction section of the target nuclide produced by the target material corresponds to the valley region of the reaction section of the target nuclide produced by the shell. Or, within the same nuclide production energy range, the peak region of the reaction section of the target nuclide produced by the shell corresponds to the valley region of the reaction 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 material and a shell. 68 Ge- 88 Zr- 93m The method using Mo 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 66 MeV-70 MeV. 88 Zr and 68 Ge, of which the target nuclide 88 The reaction cross section of Zr is the peak region, and the target nuclide... 68 The reaction cross section of Ge is a valley region; The target nuclide corresponds to the energy range of 43 MeV-66 MeV. 88 Zr and 68 Ge, of which the target nuclide 68 The reaction cross section of Ge is the peak region, and the target nuclide is... 88 The reaction cross section of Zr is a valley region; The target nuclide corresponds to the energy range of 39.65 MeV-43 MeV. 88 Zr and 68 Ge, of which the target nuclide 88 The reaction cross section of Zr is the peak region, and the target nuclide... 68 The reaction cross section of Ge is a valley region; The target nuclide corresponds to the energy range of 34 MeV-36.5 MeV. 88 Zr and 68 Ge, of which the target nuclide 88 The reaction cross section of Zr is the peak region, and the target nuclide... 68 The reaction cross section of Ge is a valley region; Target nuclides in the energy range of 12.5 MeV-34 MeV 88 Zr and 68 Ge, of which the target nuclide 68 The reaction cross section of Ge is the peak region, and the target nuclide is... 88 The reaction cross section of Zr is a valley region; The target nuclide corresponds to the energy range of 0-12.5 MeV. 93m Mohe 68 Ge, of which the target nuclide 93m The reaction cross section of Mo is the peak region, and the target nuclide is... 68 The reaction cross section of Ge is a valley region.

3. The high-current proton cyclotron accelerator according to claim 1 is manufactured using a target and a shell. 68 Ge- 88 Zr- 93m The method using Mo isotopes is characterized by: Beam flow into target material for production 68 The energy range of Ge is, in order, the first target material (5) production 68 Ge has an energy range of 43MeV-66MeV, and the second target material (6) is produced. 68 Ge has an energy range of 12.5 MeV-34 MeV, specifically: When the target nuclide is produced 68 When Ge is selected, a first target (5) and a second target (6) are chosen. The energy range of the first target (5) is 43MeV-66MeV, and this range is the range in which the first target (5) produces nuclides. 68 The peak region of Ge, and also the first target material for capsule shell (3-1) production. 88 Zr valley area; production of the second target material (6) 68 Ge has an energy range of 12.5 MeV to 34 MeV, and this range is the area where the second target (6) produces nuclides. 68 The peak region of Ga, and also the production of the second target material, the capsule shell (4-1). 88 The valley region of Zr; the thicknesses of the first target (5) and the second target (6) are calculated to be 5.24 mm and 2.56 mm respectively.

4. The high-current proton cyclotron accelerator according to claim 1, produced using a target and a shell. 68 Ge- 88 Zr- 93m The method using Mo isotopes is characterized by: Beam jet injection onto capsule shell for production 88 The energy ranges of Zr are 66 MeV-70 MeV, 39.65 MeV-43 MeV, and 34 MeV-36.5 MeV, respectively. 1) When producing the target nuclide 88 When using Zr, select the shell. 93 Nb, the shell consists of a first target material front capsule shell (3-1), a first target material rear capsule shell (3-2), and a second target material front capsule shell (4-1). 2) Selecting the shell 93 Nb production 88 The energy ranges with relatively high Zr reaction cross-sections are 66 MeV-70 MeV, 39.65 MeV-43 MeV, and 34 MeV-36.5 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 the production of target nuclei in the first target pre-capsule shell (3-1). 88 The peak region of Zr is also the production area of ​​the first target material (5). 68 The valley region of Ge; the energy range of 39.65 MeV-43 MeV is the first target material after the capsule shell (3-2) to produce the target nuclide. 88 The peak region of Zr is also the production area of ​​the first target material (5). 68 The valley region of Ge; the energy range of 34MeV-36.5MeV is the first post-target capsule shell (3-2) for the production of target nuclides. 88 The peak region of Zr is also the production area of ​​the first target material (5). 68 Ge'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 0.78mm, 0.45mm, 2mm, and 0.3mm respectively.

5. The high-current proton cyclotron accelerator according to claim 1, produced using a target and a shell. 68 Ge- 88 Zr- 93m The method using Mo isotopes is characterized by: Beam jet injection onto capsule shell for production 93m The energy of Mo is 0-12.5 MeV, specifically: 1) When producing the target nuclide 93m When selecting a housing (Mo), choose the appropriate housing. 93 Nb production target nuclide, shell 93 Nb is the second target material behind the capsule shell (4-2). 2) Select shell production 93m The Mo reaction cross-section has a relatively high energy range of 0-12.5 MeV, which corresponds to the energy range for nuclide production by the capsule shell (4-2) after the second target material; the energy range of 0-12.5 MeV is the energy range for the production of target nuclei by the capsule shell (4-2) after the second target material. 93m The peak region of Mo is also the production area of ​​the second target material (6). 68 Ge's valley area; 3) Determine the thickness of the shell: The thickness of the capsule shell (4-2) after the second target material is 0.42 mm.

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