A tantalum and beryllium neutron target system suitable for BNCT

Abstract

The present invention relates to the technical field of neutron targets and discloses a tantalum and beryllium neutron target system suitable for BNCT. The tantalum and beryllium neutron target system comprises a target plate structure and a target stand for mounting the target plate structure. The target plate structure comprises a tantalum target and a beryllium target, which are bonded into an integrated target plate structure by a high-temperature resistant metal adhesive. The tantalum and beryllium neutron target system suitable for BNCT provided by the present invention solves the problem of low energy utilization and inability to maximize neutron yield in existing designs.

Description

Technical Field

[0001] The present invention relates to the technical field of neutron targets, and in particular to a tantalum and beryllium neutron target system suitable for BNCT. Background Art

[0002] Boron Neutron Capture Therapy (BNCT) is a treatment method that uses a thermal neutron beam to react with a boron-containing drug accumulated in tumor tissue, releasing a highly lethal radiation that kills cancer cells. It is a novel dual-pronged approach for precision cancer treatment. First, a boron-neutron-targeted drug is injected into the body, where it accumulates and destroys the tumor. Simultaneously, the drug is loaded with the boron-10 isotope, which is non-radioactive and non-toxic. However, BNCT has a significant advantage: when neutrons are injected, the reaction cross-section with the neutrons is very large. The nuclear reaction between the neutrons and the boron-10 produces alpha particles and 7Li particles. These particles differ significantly from the X-rays or gamma rays used in traditional radiotherapy in that they travel a short distance, approximately the length of a cell. Any cell that has absorbed the boron-containing targeted drug will be precisely killed by the neutrons, sparing surrounding healthy cells. Furthermore, since the neutrons primarily interact with the boron-10 in the targeted drug, only rough aiming and accurate direction are required. This means that the cost of boron neutron capture therapy equipment can be greatly reduced, the size can be greatly reduced, and it is also very simple.

[0003] In addition to the proton energy and beam generated by the accelerator, the existing accelerator boron neutron capture therapy system must have a neutron conversion target system that can convert protons into neutrons. The existing neutron conversion target system mainly uses a single target to achieve proton conversion. However, since the proton energy generated by the accelerator is continuously released from the low energy end to the high energy end, a single target can only have a relatively high neutron yield within a certain energy range and cannot fully convert protons in other energy ranges. Therefore, the energy conversion rate of the existing neutron conversion target system needs to be improved.

[0004] Furthermore, the accelerator operates continuously, and the high-energy protons it produces will generate huge amounts of heat when they hit the neutron conversion target. If the heat is not removed in time, the temperature of the neutron conversion target will continue to rise, affecting the normal operation of the system and the service life of the neutron conversion target. Therefore, cooling measures must be taken for the neutron conversion target.

[0005] In addition, as the time that high-energy protons hit the neutron conversion target changes, the neutron conversion efficiency will gradually decrease. Therefore, the neutron conversion target needs to be replaced regularly. However, the replacement of existing neutron conversion targets is not easy to operate, which will directly affect the utilization efficiency of the equipment system. Summary of the Invention

[0006] The object of the present invention is to provide a tantalum and beryllium neutron target system suitable for BNCT, so as to solve at least one of the above problems existing in the prior art.

[0007] In order to achieve the above object, the present invention adopts the following technical solutions:

[0008] A tantalum and beryllium neutron target system suitable for BNCT includes a target plate structure and a target stand for mounting the target plate structure. The target plate structure includes a tantalum target and a beryllium target, which are bonded into an integrated target plate structure by a high-temperature resistant metal adhesive.

[0009] In this technical solution, since the target plate structure includes a tantalum target and a beryllium target, the tantalum target produces a high neutron yield at the high energy end of proton energy (above 20 MeV); the beryllium target produces a high neutron yield at the medium and low energy ends of proton energy (below 20 MeV). This technical solution adopts a tantalum-beryllium composite target structural design method, which can fully convert protons in various energy ranges into neutrons. Compared with neutron conversion targets of a single target material type, it can achieve an increase in neutron yield under the same proton source, thereby improving energy utilization. When used in BNCT treatment, it can effectively shorten the treatment time and thus reduce the negative effects of the treatment process on the patient. Since the tantalum target and the beryllium target are bonded into an integrated target plate structure by a high-temperature resistant metal adhesive, the high-temperature resistant metal adhesive can tightly bond the tantalum target and the beryllium target together to form a seamless whole, thereby maximizing the neutron yield generated by protons at the high and medium energy ends. In addition, this bonding composite method has a simple process and low production cost.

[0010] Furthermore, in order to facilitate the installation of the target plate structure and to better dissipate the heat of the target plate structure, the target stand includes a hollow installation position, and the target plate structure is installed at the hollow installation position.

[0011] Furthermore, in order to prevent high-energy neutrons from leaking through the gaps in the target holder and entering the accelerator hall as much as possible, the target holder includes a lower extension structure and an upper extension structure. The hollow mounting position is located on the lower extension structure. The width of the upper extension structure is greater than that of the lower extension structure. A first bending structure 11 is provided between the lower extension structure and the upper extension structure. That is, the target holder adopts an inverted trapezoidal structure design with a larger upper portion and a smaller lower portion. The upper and lower portions are not vertically connected, but have a structural design with bent edges, thereby achieving a better anti-leakage effect.

[0012] Furthermore, in order to better achieve the moderation and reflection of high-energy neutrons, a target stand moderator block and a target stand reflector block are provided in the upper extension structure.

[0013] Furthermore, in order to better dissipate heat for the target holder and extend the service life of the neutron conversion target, a heat dissipation component is provided on one side of the target holder, and the beryllium target is located on the side close to the heat dissipation component.

[0014] Furthermore, in order to prevent high-energy neutrons from leaking through the gaps in the heat sink and entering the accelerator hall as much as possible, the heat dissipation assembly includes a heat sink and a heat pipe installed on the heat sink. The heat sink includes a lower frame structure and an upper frame structure. The width of the upper frame structure is greater than the width of the lower frame structure. A second bending structure 31 is provided between the lower frame structure and the upper frame structure. That is, the heat sink adopts an inverted trapezoidal structure design with a larger upper portion and a smaller lower portion. The upper and lower portions are not vertically connected, but have a structural design with bent edges, thereby achieving a better anti-leakage effect.

[0015] Furthermore, in order to improve the heat dissipation effect of the neutron target and to realize the plug-in installation of the target holder, the heat dissipation assembly includes a metal heat dissipation panel, which is located in the heat dissipation frame and divides the space in the heat dissipation frame into a left space and a right space. The target holder is installed in the left space, and the heat dissipation pipe is arranged in the right space.

[0016] Furthermore, in order to achieve a better heat dissipation effect and at the same time, in order to better realize the moderation and reflection of high-energy neutrons, the heat sink has a lower protrusion and an upper recessed portion, and an inclined transition surface is formed between the lower protrusion and the upper recessed portion. The lower space on the right side is between the lower end of the metal heat dissipation panel and the lower protrusion, and the upper space on the right side is between the upper end of the metal heat dissipation panel and the upper recessed portion. The coil portion of the heat pipe is located in the lower space on the right side, and the heat sink reflector block and the heat sink moderator block are provided in the upper space on the right side.

[0017] Furthermore, in order to facilitate the detachable installation of the neutron conversion target on the heat dissipation rack, the heat dissipation rack includes a base, a support body, a left plate and a right plate, the lower protrusion and the upper recess are formed on the support body, the base is fixedly connected to the lower end of the support body, the left plate and the right plate are respectively fixedly connected to the left and right sides of the support body, the inner sides of the left plate and the right plate are respectively provided with vertical limiting protrusions, and the metal heat dissipation panel is located on the left side of the vertical limiting protrusion.

[0018] Furthermore, in order to facilitate the installation of the heat dissipation pipe and improve the compactness of the structure, two limiting grooves are respectively provided on the upper recessed portion. The extension section of the heat dissipation pipe is located in the corresponding limiting groove and extends upward to the outside of the limiting groove. The vertical limiting protrusion limits the extension section of the heat dissipation pipe within the limiting groove.

[0019] The beneficial effects of the present invention are as follows: in this technical solution, since the target plate structure includes a tantalum target and a beryllium target, the tantalum target produces a high neutron yield at the high energy end of proton energy (above 20 MeV); the beryllium target produces a high neutron yield at the medium and low energy ends of proton energy (below 20 MeV). This technical solution adopts a tantalum-beryllium composite target structural design method, which can fully convert protons in each energy range into neutrons. Compared with a neutron conversion target of a single target material type, it can achieve an increase in neutron yield under the same proton source, thereby improving energy utilization. When used in BNCT treatment, it can effectively shorten the treatment time and reduce the negative effects of the treatment process on the patient. Since the tantalum target and the beryllium target are bonded into an integrated target plate structure by a high-temperature resistant metal adhesive, the high-temperature resistant metal adhesive can tightly bond the tantalum target and the beryllium target together to form a seamless whole, thereby maximizing the neutron yield generated by protons at the high and medium energy ends, and this bonding composite method has a simple process and low production cost. BRIEF DESCRIPTION OF THE DRAWINGS

[0020] Figure 1 This is a schematic diagram of the main structure of the present invention;

[0021] Figure 2 for Figure 1 Schematic cross-sectional view of AA in the figure;

[0022] Figure 3 An exploded view of the present invention;

[0023] Figure 4 This is a schematic structural diagram of the present invention in use from a first perspective;

[0024] Figure 5 This is a side structural schematic diagram of the present invention in use;

[0025] Figure 6 An exploded view of the neutron conversion target of the present invention;

[0026] Figure 7 Schematic diagram of the side structure of the neutron conversion target of the present invention;

[0027] Figure 8 This is a schematic diagram of the main structure of the neutron conversion target of the present invention;

[0028] Figure 9 This is a schematic structural diagram of the neutron conversion target of the present invention from a first perspective;

[0029] Figure 10 This is a schematic structural diagram of the neutron conversion target of the present invention from a second perspective;

[0030] Figure 11 An exploded view of the heat dissipation component of the present invention;

[0031] Figure 12 This is a schematic structural diagram of the heat dissipation assembly of the present invention from a first perspective;

[0032] Figure 13 This is a schematic structural diagram of the heat dissipation assembly of the present invention from a second viewing angle;

[0033] Figure 14 This is a schematic structural diagram of the heat dissipation assembly of the present invention from a third perspective;

[0034] In the figure: target mount 1; target mount frame 1.1; target mount plate 1.2; upper frame box 1.3; upper extension structure 1.4; lower extension structure 1.5; tantalum target 2; beryllium target 3; high temperature resistant metal adhesive 4; hollow mounting position 5; target mount moderator block 6; first moderator block bending structure 6.1; target mount reflector block 7; handle 8; lower frame structure 9; upper frame structure 10; first bending structure 11; metal heat dissipation panel 12; left space 13; right space 14; lower protrusion 15; upper recessed portion 16; inclined transition surface 17; mounting groove 18; heat dissipation frame reflector block 20; heat dissipation frame moderator block 21; base 22; support body 23; left side plate 24; right side plate 25; vertical limiting protrusion 26; middle limiting protrusion 27; limiting groove 28; beam tube 29; heat dissipation pipe 30; second bending structure 31; target plate structure 32. DETAILED DESCRIPTION

[0035] In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the present invention will be briefly introduced below in conjunction with the drawings and the description of the embodiments or the prior art. Obviously, the following description of the structure of the drawings is only some embodiments of the present invention. For those skilled in the art, other drawings can be obtained based on these drawings without creative work. It should be noted that the description of these embodiments is used to help understand the present invention, but does not constitute a limitation of the present invention.

[0036] Example 1:

[0037] like Figures 1-14 As shown, this embodiment provides a tantalum and beryllium neutron target system suitable for BNCT, such as Figures 6-10As shown, the target plate structure 32 includes a target holder 1 for mounting the target plate structure 32. The target plate structure 32 includes a tantalum target 2 and a beryllium target 3. Preferably, the tantalum target 2 is made of high-purity tantalum target material with a tantalum content of 99.99%. Specifically, it can be cut from a tantalum plate of the same thickness as the tantalum target 2; alternatively, it can be cut from a tantalum rod of the same diameter as the tantalum target 2 using a wire cutter. The beryllium target 3 is made of high-purity beryllium target material with a beryllium content of 99.99%. Specifically, it can be cut from a beryllium rod of the same diameter as the beryllium target 3 using a wire cutter. The tantalum target 2 and the beryllium target 3 are bonded into an integrated target plate structure 32 by a high-temperature resistant metal adhesive 4. There are many types of high-temperature resistant metal adhesives 4 that can withstand temperatures of about 300°C. As long as the metal adhesive is resistant to temperatures of about 300°C, is environmentally friendly, oil-resistant, waterproof, corrosion-resistant, impact-resistant and aging-resistant, the tantalum target 2 and the beryllium target 3 are seamlessly bonded by mechanical coating and pressure-bearing.

[0038] In this technical solution, since the target plate structure 32 includes a tantalum target 2 and a beryllium target 3, the tantalum target 2 produces a high neutron yield at the high energy end of proton energy (above 20 MeV), while the beryllium target 3 produces a high neutron yield at the medium and low energy ends of proton energy (below 20 MeV). This technical solution adopts a tantalum-beryllium composite target structural design method, which can fully convert protons in various energy ranges into neutrons. Compared with neutron conversion targets of a single target material type, it can achieve an increase in neutron yield while maintaining the same proton source, thereby improving energy utilization. In the process of BNCT treatment, it can effectively shorten the treatment time and thus reduce the negative effects of the treatment process on the patient. Since the tantalum target 2 and the beryllium target 3 are bonded together into an integrated target plate structure 32 by a high-temperature resistant metal adhesive 4, the high-temperature resistant metal adhesive can tightly bond the tantalum target 2 and the beryllium target 3 together to form a seamless whole, thereby maximizing the neutron yield generated by protons at the high and medium energy ends. This bonding composite method is simple in process and low in production cost.

[0039] It should be noted that the size of the composite tantalum target 2 and beryllium target 3 is consistent with the inner diameter of the proton output end of the accelerator beam line system, that is, the inner diameter of the port of the accelerator beam tube 29 is generally 10-12 mm. Specifically, the thickness of the tantalum target 2 and the beryllium target 3 can be determined by theoretical calculation. Preferably, the thickness of the tantalum target 2 is generally 3.0-4.0 mm, and the thickness of the beryllium target 3 is generally 9.0-11 mm.

[0040] Example 2:

[0041] This embodiment is optimized based on the above embodiment 1.

[0042] like Figure 6As shown, in order to facilitate the installation of the target plate structure 32 and to better dissipate heat from the target plate structure 32 , the target holder 1 includes a hollow installation position 5 , and the target plate structure 32 is installed at the hollow installation position 5 .

[0043] Specifically, the tantalum target 2 and the beryllium target 3, which are tightly bonded together, are embedded in the hollow mounting area on the target holder 1. The tantalum target 2 faces the proton extraction port of the accelerator beam line system, that is, the port of the accelerator's beam tube 29, so that the beryllium target 3 can be close to the heat dissipation component, thereby achieving a better heat dissipation effect.

[0044] It should be noted that the target plate structure 32 can be designed with a connection structure that is easily detachable from the target stand 1. After the radioactivity on the used target stand 1 has naturally decayed for a period of time and the dose has been reduced to an allowable level, the target plate structure 32 can be removed and the target stand 1 can be reused.

[0045] Example 3:

[0046] This embodiment is optimized based on the above embodiment 2.

[0047] In order to avoid high energy neutrons from leaking out through the gaps in the target holder 1 and then entering the accelerator hall, Figure 1 、 Figure 8 As shown, the target stand 1 includes a lower extension structure 1.5 and an upper extension structure 1.4. The hollow mounting position 5 is located on the lower extension structure 1.5. The width of the upper extension structure 1.4 is greater than that of the lower extension structure 1.5. There is a first bending structure 11 between the lower extension structure 1.5 and the upper extension structure 1.4. That is, the target stand 1 adopts an inverted trapezoidal structure design with a larger upper part and a smaller lower part. The upper and lower parts are not vertically connected, but have a structural design with bent edges, which can effectively avoid straight-through beams, thereby achieving a better anti-leakage effect.

[0048] Example 4:

[0049] This embodiment is optimized based on the above embodiment 3.

[0050] like Figure 6 As shown, in order to better achieve the moderation and reflection of high-energy neutrons, a target stand moderator block 6 and a target stand reflector block 7 are provided in the upper extension structure 1.4. The target stand reflector block 7 is located above the target stand moderator block 6. Both sides of the target stand moderator block 6 have first moderator block bending structures 6.1 that match the first bending structure 11 of the target stand 1, which can effectively prevent a straight-through beam, thereby achieving a better leakage prevention effect. In addition, the target stand moderator block 6 that matches the inverted trapezoidal structure of the target stand 1 is also easy to process, maintain or replace, and is convenient to assemble and disassemble.

[0051] Preferably, in order to facilitate the replacement of the target stand 1 , a handle 8 is provided at the upper end of the target stand 1 for easy removal.

[0052] It should be noted that if Figure 3 、 Figure 6 、 Figure 9 As shown, the target mount 1 comprises a target mount frame 1.1 and a target mount plate 1.2. The target mount frame 1.1 is mechanically pressed from an aluminum alloy with a thickness of 2-2.5 mm; the target mount plate 1.2 is mechanically pressed from an aluminum alloy with a thickness of 1.5-2 mm. An upper frame box 1.3 is located at the upper end of the target mount frame 1.1. The target mount moderator block 6 and the target mount reflector block 7 are both mounted within the upper frame box 1.3. The target mount plate 1.2 snaps into the opening of the upper frame box 1.3 of the target mount frame 1.1 to seal the upper frame box 1.3. The target mount moderator block 6 and the target mount reflector block 7 are mechanically processed from neutron moderating and neutron reflecting materials, respectively.

[0053] Neutron conversion target assembly: Assemble the target frame moderator block 6 and reflector block 7 within the upper frame box 1.3 of the mechanically pressed target frame 1. Cover with the target frame plate 1.2 and screw it in place. The tantalum target 2 and beryllium target 3, seamlessly bonded together by mechanical coating and pressure, are mounted in the hollow mounting position 5 of the target frame 1.1 and secured.

[0054] Example 5:

[0055] This embodiment is optimized based on the above embodiment 1.

[0056] In order to better dissipate heat from the target holder 1 and extend the service life of the neutron conversion target, a heat dissipation component is provided on one side of the target holder 1, and the beryllium target 3 is located on the side close to the heat dissipation component. Since beryllium has good thermal conductivity, its thermal conductivity is 5 times that of copper and 6 times that of aluminum. The heat generated by high-energy protons hitting the tantalum and beryllium targets 3 is more easily transferred to the heat dissipation component.

[0057] Example 6:

[0058] This embodiment is optimized based on the above embodiment 5.

[0059] In order to prevent high-energy neutrons from leaking out through the gaps in the heat sink and then entering the accelerator hall, the heat dissipation assembly includes a heat sink and a heat pipe 30 mounted on the heat sink. Figure 13As shown, the heat dissipation rack includes a lower frame structure 9 and an upper frame structure 10. The width of the upper frame structure 10 is greater than the width of the lower frame structure 9. There is a second bending structure 31 between the lower frame structure 9 and the upper frame structure 10. That is, the heat dissipation rack adopts an inverted trapezoidal structure design with a larger upper part and a smaller lower part. The upper and lower parts are not vertically connected, but have a structural design with bent edges, which can effectively avoid straight-through bundles, thereby achieving a better anti-leakage effect.

[0060] Example 7:

[0061] This embodiment is optimized based on the above embodiment 6.

[0062] In order to improve the heat dissipation effect of the neutron target and realize the plug-in installation of the target holder 1, Figure 1 、 Figure 3 、 Figure 11-14 As shown, the heat dissipation assembly includes a metal heat dissipation panel 12, which is located within the heat dissipation frame and divides the space within the heat dissipation frame into a left space 13 and a right space 14. The target holder 1 is installed in the left space 13, and the heat dissipation pipe 30 is arranged in the right space 14. Preferably, the heat dissipation frame is mechanically pressed from an aluminum alloy with a thickness of 2.5-3 mm; the metal heat dissipation panel 12 is mechanically pressed from an aluminum alloy with a thickness of 1.5-2 mm. The heat dissipation pipe 30 is a square copper cooling pipe, mechanically manufactured from a copper tube with a diameter of 15-20 mm.

[0063] Because the dose in the accelerator hall is very high when the accelerator is running, personnel are unable to enter the hall to replace the target plate structure 32 for a period of time after the accelerator stops operating. In addition, the dose of tantalum and beryllium targets used in the accelerator is very high and human contact is absolutely prohibited. Therefore, a robot or intelligent pick-and-place system must be used to replace the target plate structure 32. In this technical solution, the target holder 1 is designed as a plug-in inverted trapezoidal structure. The target holder 1 and the heat sink are designed to be separated. The target holder 1 can be removed from the heat sink and replaced. This facilitates the use of a robot or intelligent pick-and-place system to quickly and safely replace the target holder 1 and the target plate structure 32 as a whole.

[0064] Example 8:

[0065] This embodiment is optimized based on the above embodiment 5.

[0066] In order to achieve better heat dissipation effect, and at the same time, to better realize the slowing down and reflection of high-energy neutrons, such as Figure 3As shown, the heat sink has a lower raised portion 15 and an upper recessed portion 16, with an inclined transition surface 17 formed between the lower raised portion 15 and the upper recessed portion 16. The lower right space is defined between the lower end of the metal heat sink panel 12 and the lower raised portion 15, while the upper right space is defined between the upper end of the metal heat sink panel 12 and the upper recessed portion 16. The coil portion of the heat pipe 30 is located in the lower right space. The upper right space contains a heat sink reflector block 20 and a heat sink moderator block 21. The heat sink reflector block 20 is located above the heat sink moderator block 21. The heat sink reflector block 20 and the heat sink moderator block 21 are machined from neutron reflecting and neutron moderating materials, respectively.

[0067] Assembly of the heat dissipation assembly: Assemble the heat dissipation frame reflector block 20 and the heat dissipation frame moderator block 21 in the upper right space, fix the manufactured square copper cooling pipe in the right space 14 and cover it with the metal heat dissipation panel 12.

[0068] It should be noted that ordinary light water can be used as a coolant. A 1mA, 30Me proton beam from the accelerator generates 30kW of heat, which is transferred to the tantalum-beryllium neutron target. This large amount of heat requires a tantalum-beryllium neutron target heat dissipation system. In this heat dissipation system, heat from the beryllium target 3 is transferred to a heat sink assembly, and the heat pipe 30 is cooled by light water. Since the accelerator system also uses light water for cooling, the tantalum-beryllium neutron target heat sink assembly can be shared with the accelerator water cooling system, reducing the burden of installing a new tantalum-beryllium neutron target cooling system.

[0069] Example 9:

[0070] This embodiment is optimized based on the above-mentioned embodiment 8.

[0071] In order to facilitate the detachable installation of the neutron conversion target on the heat sink, Figure 11-14 As shown, the heat sink includes a base 22, a support body 23, a left side plate 24 and a right side plate 25. The lower protrusion 15 and the upper recessed portion 16 are formed on the support body 23. The base 22 is fixedly connected to the lower end of the support body 23. The left side plate 24 and the right side plate 25 are fixedly connected to the left and right sides of the support body 23 respectively. The inner sides of the left side plate 24 and the right side plate 25 are respectively provided with vertical limiting protrusions 26. The metal heat dissipation panel 12 is located on the left side of the vertical limiting protrusion 26. The heat sink reflector block 20, the heat sink moderator block 21 and the heat pipe 30 are located on the right side of the vertical limiting protrusion 26.

[0072] Preferably, in order to better achieve docking installation between the neutron conversion target and the heat dissipation assembly, the inner sides of the left plate 24 and the right plate 25 are respectively provided with a middle limiting protrusion 27 that matches the shape of the bending structure 11 on the target holder 1.

[0073] It should be noted that if Figure 11As shown, in order to facilitate the installation of the metal heat dissipation panel 12 , a mounting groove 18 is provided on the base 22 , and the lower end of the metal heat dissipation panel 12 is located in the mounting groove 18 .

[0074] Example 10:

[0075] This embodiment is optimized based on the above-mentioned embodiment 9.

[0076] To facilitate installation of the heat pipe 30 and enhance the compactness of the structure, two retaining grooves 28 are provided on the upper recessed portion 16. The extended section of the heat pipe 30 is located within the corresponding retaining groove 28 and extends upwardly beyond the retaining groove 28. The vertical retaining protrusion 26 confines the extended section of the heat pipe 30 within the retaining groove 28. Furthermore, since the replacement cycle of the heat pipe 30 is relatively long (generally, it takes several years of use before replacement), the heat pipe 30 and the heat sink are designed to form a snap-fit structure, which facilitates replacement of the heat pipe 30 after several years.

[0077] The invention is mainly applicable to a conversion target system for converting protons into neutrons in a high-energy accelerator boron neutron capture therapy system with an energy of about 30 MeV.

[0078] Finally, it should be noted that the above are only preferred embodiments of the present invention and are not intended to limit the scope of protection of the present invention. Any modifications, equivalent substitutions, improvements, etc. made within the spirit and principles of the present invention shall be included in the scope of protection of the present invention.

Claims

1. A tantalum or beryllium neutron target system suitable for BNCT, characterized by: It includes a target plate structure and a target stand for mounting the target plate structure, wherein the target plate structure includes a tantalum target and a beryllium target, and the tantalum target and the beryllium target are bonded into an integrated target plate structure by a high-temperature resistant metal adhesive; The target stand includes a hollow installation position, and the target plate structure is installed at the hollow installation position; The target stand comprises a lower extension structure and an upper extension structure, the hollow mounting position is located on the lower extension structure, the width of the upper extension structure is greater than that of the lower extension structure, and a first bending structure is provided between the lower extension structure and the upper extension structure; The upper extension structure is provided with a target stand moderator block and a target stand reflector block; The target stand comprises a target stand frame and a target stand plate. The target stand plate is buckled at the opening of the upper frame box of the target stand frame to seal the upper frame box.

2. The tantalum and beryllium neutron target system suitable for BNCT according to claim 1, characterized in that: A heat dissipation component is provided on one side of the target stand, and the beryllium target is located on the side close to the heat dissipation component.

3. The tantalum and beryllium neutron target system suitable for BNCT according to claim 2, characterized in that: The heat dissipation assembly includes a heat dissipation frame and a heat dissipation pipe installed on the heat dissipation frame. The heat dissipation frame includes a lower frame structure and an upper frame structure. The width of the upper frame structure is greater than the width of the lower frame structure. A second bending structure is provided between the lower frame structure and the upper frame structure.

4. The tantalum and beryllium neutron target system suitable for BNCT according to claim 3, characterized in that: The heat dissipation assembly includes a metal heat dissipation panel, which is located in the heat dissipation frame and divides the space in the heat dissipation frame into a left space and a right space. The target frame is installed in the left space, and the heat dissipation pipe is arranged in the right space.

5. The tantalum and beryllium neutron target system suitable for BNCT according to claim 4, characterized in that: The heat dissipation frame has a lower raised portion and an upper recessed portion, an inclined transition surface is formed between the lower raised portion and the upper recessed portion, the lower right space is between the lower end of the metal heat dissipation panel and the lower raised portion, the upper right space is between the upper end of the metal heat dissipation panel and the upper recessed portion, the coil portion of the heat dissipation pipe is located in the lower right space, and the heat dissipation frame reflector block and the heat dissipation frame moderator block are provided in the upper right space.

6. The tantalum and beryllium neutron target system suitable for BNCT according to claim 5, characterized in that: The heat dissipation rack includes a base, a support body, a left side plate and a right side plate. The lower protrusion and the upper recess are formed on the support body. The base is fixedly connected to the lower end of the support body. The left side plate and the right side plate are respectively fixedly connected to the left and right sides of the support body. Vertical limiting protrusions are respectively provided on the inner sides of the left side plate and the right side plate. The metal heat dissipation panel is located on the left side of the vertical limiting protrusion.

7. The tantalum and beryllium neutron target system suitable for BNCT according to claim 6, characterized in that: Two limiting grooves are respectively provided on the upper recessed portion. The extension section of the heat dissipation pipe is located in the corresponding limiting groove and extends upward to the outside of the limiting groove. The vertical limiting protrusion limits the extension section of the heat dissipation pipe in the limiting groove.

Images