CN219227907U - Tantalum and beryllium neutron target system suitable for BNCT - Google Patents

Abstract

The utility model relates to the technical field of neutron targets, and discloses a tantalum and beryllium neutron target system suitable for BNCT, which comprises a target plate structure and a target frame for mounting the target plate structure, wherein the target plate structure comprises a tantalum target and a beryllium target, and the tantalum target and the beryllium target are bonded into an integrated target plate structure through a high-temperature-resistant metal adhesive; the tantalum and beryllium neutron target system suitable for BNCT solves the problem that the energy utilization rate is low and the maximization of neutron yield cannot be realized in the existing design.

Description

Tantalum and beryllium neutron target system suitable for BNCT

Technical Field

The utility model relates to the technical field of neutron targets, in particular to a tantalum and beryllium neutron target system suitable for BNCT.

Background

Boron neutron capture therapy (Boron Neutron Capture Therapy, BNCT for short) is a therapeutic method in which thermal neutron beams react with boron-containing drugs accumulated in tumor tissues to release rays with extremely strong killing power, thereby killing cancer cells. It is a new binary technology for accurately treating cancers. Firstly, after the targeted medicine of boron neutrons is injected into a human body, the targeted medicine is gathered on the destroyed tumor, and meanwhile, the medicine is carried with the isotope of boron-10, and the isotope has no radioactivity and no toxicity. However, it has a good characteristic that when a neutron is incident, the reaction section with the neutron is very large, and after the neutron and boron-10 undergo nuclear reaction, alpha particles and 7Li particles are generated. The two particles are very different from X-rays or gamma rays used in traditional radiotherapy, the flight distance is short, the length of one cell is about, and which cell adsorbs the targeting medicine containing boron can be accurately killed by neutrons without damaging surrounding normal cells. Meanwhile, neutrons mainly act with boron-10 of the targeted drug, so that the target is aimed at in a correct direction. This also allows a great reduction in the cost of the boron neutron capture therapy device, a great reduction in volume, and a very simple process.

In addition to the proton energy and beam current generated by the accelerator, it is extremely critical that a neutron conversion target system capable of converting protons into neutrons is needed, while the existing neutron conversion target system mainly adopts a single target to realize the conversion of protons, but because the proton energy generated by the accelerator is continuously released from a low energy end to a high energy end, the single target only has relatively high neutron yield under a certain energy range condition, and cannot fully convert protons in other energy segments, so the energy conversion rate of the existing neutron conversion target system needs to be improved.

And the accelerator continuously operates, and the produced high-energy protons strike on the neutron conversion target to generate huge heat, if the generated heat is not taken away in time, the temperature of the neutron conversion target is continuously increased, the normal operation of the system and the service life of the neutron conversion target are affected, so that cooling measures are required to be taken for the neutron conversion target.

In addition, as the neutron conversion efficiency gradually decreases along with the time change of the high-energy protons striking the neutron conversion target, the neutron conversion target needs to be replaced periodically, and the replacement of the existing neutron conversion target is not easy to operate, so that the service efficiency of the equipment system can be directly affected.

Disclosure of Invention

The object of the present utility model is to provide a tantalum, beryllium neutron target system suitable for BNCT, which solves at least one of the above problems in the prior art.

In order to achieve the above purpose, the present utility model adopts the following technical scheme:

the utility model provides a tantalum, beryllium neutron target system suitable for BNCT, includes target plate structure and is used for installing the target frame of target plate structure, the target plate structure includes tantalum target and beryllium target, tantalum target and beryllium target pass through high temperature resistant metal adhesive bonding and become integrated target plate structure.

In the technical scheme, the target plate structure comprises a tantalum target and a beryllium target, so that the neutron yield generated by the tantalum target at the high energy end (more than 20 Mev) of proton energy is high; the neutron yield generated by the beryllium targets at the middle and low energy ends (below 20 Mev) of the proton energy is high, and the technical scheme adopts the structural design mode of the tantalum-beryllium composite target, so that protons at each energy section can be fully converted into neutrons, and compared with a neutron conversion target of a single target type, the neutron yield can be improved under the condition that proton sources are the same, thereby improving the energy utilization rate, effectively shortening the treatment duration in the BNCT treatment process, and further reducing the negative effects on patients caused by the treatment process. The tantalum target and the beryllium target are adhered to form an integrated target plate structure through the high-temperature-resistant metal adhesive, and the high-temperature-resistant metal adhesive can tightly adhere the tantalum target and the beryllium target together to form a seamless integral, so that the neutron yield generated by protons at high and medium energy ends is maximized, and the adhesion composite mode has the advantages of simple process and low production cost.

Further, in order to conveniently realize the installation to the target plate structure, simultaneously, in order to better realization to the heat dissipation of target plate structure, the target frame includes fretwork installation position, the target plate structure is installed in fretwork installation position department.

Further, in order to avoid the high-energy neutrons to leak out through the gap of the target frame and enter the accelerator hall as far as possible, the target frame comprises a lower extending structure and an upper extending structure, the hollowed-out installation position is located on the lower extending structure, the width of the upper extending structure is larger than that of the lower extending structure, a first bending structure 11 is arranged between the lower extending structure and the upper extending structure, that is, the target frame adopts an inverted trapezoid structure design with a large upper part and a small lower part, and the upper part and the lower part are not vertically communicated, but are provided with a bent edge structure design, so that a better leakage preventing effect is achieved.

Further, in order to better realize the effect of moderating and reflecting the high-energy neutrons, a target frame moderating body block and a target frame reflecting body block are arranged in the upper extending structure.

Further, in order to better realize the heat dissipation to the target frame, promote neutron conversion target's life, one side of target frame is equipped with the radiator unit, beryllium target is located the one side that is close to the radiator unit.

Further, in order to avoid the gap leakage of high energy neutron through the heat dissipation frame to go out and then enter into the accelerator hall as far as possible, the heat dissipation subassembly includes the heat dissipation frame and installs the cooling tube on the heat dissipation frame, the heat dissipation frame includes lower part support body structure and upper portion support body structure, the width of upper portion support body structure is greater than the width of lower part support body structure, have second kink structure 31 between lower part support body structure and the upper portion support body structure, that is, the heat dissipation frame adopts big-end-up's reverse trapezoidal structural design, upper and lower not vertical intercommunication, but have the structural design of bent edge, reach better leak protection effect like this.

Further, in order to promote the radiating effect to neutron target, in order to realize the plug-in installation to the target frame simultaneously, the radiating component includes metal heat dissipation panel, metal heat dissipation panel is located the heat dissipation frame and falls into left side space and right side space with the space in the heat dissipation frame, the target frame is installed in left side space, the cooling tube sets up in right side space.

Further, in order to reach better radiating effect, simultaneously, for better realization is to the moderation and the reflection effect of high-energy neutron, the heat dissipation frame has lower bellying and upper concave part, form the slope transition face between lower bellying and the upper concave part, be right side lower part space between metal heat dissipation panel's lower extreme and the lower bellying, be right side upper portion space between metal heat dissipation panel's upper end and the upper concave part, the coil pipe portion of cooling tube is located right side lower part space, be equipped with heat dissipation frame reflector piece and heat dissipation frame moderation body piece in the right side upper portion space.

Further, in order to be convenient for install neutron conversion target detachable on the heat dissipation frame, the heat dissipation frame includes base, supporter, left side board and right side board, lower bellying and upper concave part form on the supporter, the lower extreme fixed connection of base and supporter, left side board and right side board respectively with the left side and the right side fixed connection of supporter, the inboard of left side board and right side board is equipped with vertical spacing arch respectively, metal heat dissipation panel is located vertical spacing bellied left side.

Further, in order to facilitate the installation of the radiating pipe, the compactness of the structure is improved, two limiting grooves are respectively formed in the upper concave portion, the extending section of the radiating pipe is located in the corresponding limiting groove and extends upwards to the outside of the limiting groove, and the extending section of the radiating pipe is limited in the limiting groove by the vertical limiting protrusions.

The beneficial effects of the utility model are as follows: in the technical scheme, the target plate structure comprises a tantalum target and a beryllium target, so that the neutron yield generated by the tantalum target at the high energy end (more than 20 Mev) of proton energy is high; the neutron yield generated by the beryllium targets at the middle and low energy ends (below 20 Mev) of the proton energy is high, and the technical scheme adopts the structural design mode of the tantalum-beryllium composite target, so that protons at each energy section can be fully converted into neutrons, and compared with a neutron conversion target of a single target type, the neutron yield can be improved under the condition that proton sources are the same, thereby improving the energy utilization rate, effectively shortening the treatment duration in the BNCT treatment process, and further reducing the negative effects on patients caused by the treatment process. The tantalum target and the beryllium target are adhered to form an integrated target plate structure through the high-temperature-resistant metal adhesive, and the high-temperature-resistant metal adhesive can tightly adhere the tantalum target and the beryllium target together to form a seamless integral, so that the neutron yield generated by protons at high and medium energy ends is maximized, and the adhesion composite mode has the advantages of simple process and low production cost.

Drawings

FIG. 1 is a schematic diagram of a front view of the present utility model;

FIG. 2 is a schematic cross-sectional view of A-A of FIG. 1;

FIG. 3 is an exploded view of the present utility model;

FIG. 4 is a schematic view of the structure of the present utility model at a first viewing angle in a use state;

FIG. 5 is a schematic side view of the present utility model in use;

FIG. 6 is an exploded view of a neutron conversion target in the present utility model;

FIG. 7 is a schematic side view of a neutron conversion target of the utility model;

FIG. 8 is a schematic diagram of the front view of a neutron conversion target according to the present utility model;

FIG. 9 is a schematic diagram of a neutron conversion target of the present utility model at a first view angle;

FIG. 10 is a schematic diagram of a neutron conversion target according to the present utility model at a second view angle;

FIG. 11 is an exploded view of a heat dissipating assembly according to the present utility model;

FIG. 12 is a schematic view of a heat dissipating assembly according to a first view of the present utility model;

FIG. 13 is a schematic diagram of a heat dissipating assembly according to a second view of the present utility model;

FIG. 14 is a schematic view of a third view of a heat dissipating assembly according to the present utility model;

in the figure: a target holder 1; a target frame 1.1; a target plate 1.2; an upper frame box 1.3; an upper extension structure 1.4; a lower extension structure 1.5; a tantalum target 2; a beryllium target 3; a high temperature resistant metal adhesive 4; the hollow installation position 5; a target holder slowing body block 6; a first moderated bulk bending structure 6.1; a target holder reflector block 7; a handle 8; a lower frame structure 9; an upper frame structure 10; a first bending structure 11; a metal heat-dissipating panel 12; a left space 13; a right space 14; a lower boss 15; an upper concave portion 16; an inclined transition surface 17; a mounting groove 18; a heat sink reflector block 20; a heat dissipation frame slowing body block 21; a base 22; a support 23; a left side plate 24; a right side plate 25; a vertical limit projection 26; a middle limit projection 27; a limit groove 28; a beam tube 29; a radiating pipe 30; a second bending structure 31; a target plate structure 32.

Detailed Description

In order to more clearly illustrate the embodiments of the present utility model or the technical solutions in the prior art, the present utility model will be briefly described below with reference to the accompanying drawings and the description of the embodiments or the prior art, and it is obvious that the following description of the structure of the drawings is only some embodiments of the present utility model, and other drawings can be obtained according to these drawings without inventive effort to a person skilled in the art. It should be noted that the description of these examples is for aiding in understanding the present utility model, but is not intended to limit the present utility model.

Example 1:

as shown in fig. 1-14, the present embodiment provides a tantalum and beryllium neutron target system suitable for BNCT, as shown in fig. 6-10, including a target plate structure 32 and a target holder 1 for mounting the target plate structure 32, where the target plate structure 32 includes a tantalum target 2 and a beryllium target 3, and preferably, the tantalum target 2 is made of a high-purity tantalum target material. Tantalum content: 99.99%. Specifically, the tantalum target is formed by cutting a tantalum plate with the same thickness as the tantalum target 2; alternatively, a tantalum rod having the same diameter as the tantalum target 2 may be used and cut by a wire cutting machine. The beryllium target 3 is made of high-purity beryllium target material. Beryllium content: 99.99%. Specifically, beryllium rods with the same diameter as the beryllium target 3 can be selected and cut by a wire cutting machine. The tantalum target 2 and the beryllium target 3 are adhered to form an integrated target plate structure 32 through the high-temperature-resistant metal adhesive 4, the variety of the selectable high-temperature-resistant metal adhesive 4 with the temperature resistance of about 300 ℃ is more, and the tantalum target 2 and the beryllium target 3 can be adhered in a seamless manner by adopting a mechanical coating and pressure-bearing mode as long as the metal adhesive is environment-friendly, oil-resistant, waterproof, corrosion-resistant, impact-resistant and ageing-resistant.

In the technical scheme, as the target plate structure 32 comprises the tantalum target 2 and the beryllium target 3, the neutron yield generated by the tantalum target 2 at the high energy end (more than 20 Mev) of proton energy is high; the neutron yield generated by the beryllium target 3 at the middle and low energy ends (below 20 Mev) of the proton energy is high, and the technical scheme adopts the structural design mode of the tantalum-beryllium composite target, so that protons at each energy section can be fully converted into neutrons, and compared with a neutron conversion target of a single target type, the neutron yield can be improved under the condition that proton sources are the same, thereby improving the energy utilization rate, effectively shortening the treatment duration in the BNCT treatment process, and further reducing the negative effects on patients caused by the treatment process. The tantalum target 2 and the beryllium target 3 are adhered to form an integrated target plate structure 32 through the high-temperature-resistant metal adhesive 4, and the high-temperature-resistant metal adhesive can tightly adhere the tantalum target 2 and the beryllium target 3 together to form a seamless connection whole, so that the neutron yield generated by protons at high and medium energy ends is maximized, and the adhesion composite mode has the advantages of simple process and low production cost.

It should be noted that, the sizes of the tantalum target 2 and the beryllium target 3 are consistent with the inner diameter of the proton extraction end of the beam line system of the accelerator, that is, the inner diameter of the port of the beam tube 29 of the accelerator is generally 10-12mm, specifically, the thicknesses 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 3.0-4.0mm, and the thickness of the beryllium target 3 is generally 9.0-11mm.

Example 2:

this example was optimized based on example 1 above.

As shown in fig. 6, in order to facilitate the installation of the target plate structure 32, and simultaneously, in order to better achieve the heat dissipation of the target plate structure 32, the target frame 1 includes a hollow installation position 5, and the target plate structure 32 is installed at the hollow installation position 5.

Specifically, the tantalum target 2 and the beryllium target 3 which are tightly adhered together are inlaid at the hollowed-out installation position on the target frame 1, and the tantalum target 2 is opposite to the proton extraction port of the beam line system of the accelerator, namely, the port of the beam tube 29 of the accelerator, so that the beryllium target 3 can be tightly adhered to the heat dissipation assembly, and a better heat dissipation effect is achieved.

It should be noted that, the target plate structure 32 may be designed to be easily detachable from the target frame 1, and after the radioactivity on the used target frame 1 naturally decays for a period of time to reduce the dosage to an allowable level, so that the target plate structure 32 may be detached and the target frame 1 may be reused.

Example 3:

this example was optimized based on example 2 above.

In order to avoid the high-energy neutrons leaking out through the gaps of the target frame 1 and entering the accelerator hall as far as possible, as shown in fig. 1 and 8, the target frame 1 comprises a lower extending structure 1.5 and an upper extending structure 1.4, the hollowed-out installation position 5 is positioned on the lower extending structure 1.5, the width of the upper extending structure 1.4 is larger than that of the lower extending structure 1.5, a first bending structure 11 is arranged between the lower extending structure 1.5 and the upper extending structure 1.4, that is, the target frame 1 adopts an inverted trapezoid structure design with a large upper part and a small lower part, and is not vertically communicated up and down, but has a bent edge structure design, so that straight beams can be effectively avoided, and a better leakage preventing effect is achieved.

Example 4:

this example was optimized based on example 3 above.

As shown in fig. 6, in order to better achieve the effect of moderating and reflecting high-energy neutrons, the upper extension structure 1.4 is internally provided with a target frame moderating body block 6 and a target frame reflecting body block 7, the target frame reflecting body block 7 is positioned above the target frame moderating body block 6, two sides of the target frame moderating body block 6 are provided with first moderating body block bending structures 6.1 matched with the first bending structures 11 of the target frame 1, so that direct beams can be effectively avoided, a better leakage-proof effect is achieved, and the target frame moderating body block 6 matched with the inverted trapezoid structure of the target frame 1 is easy to process, maintain or replace, and is convenient to assemble and disassemble.

Preferably, in order to facilitate the replacement of the target holder 1, the upper end of the target holder 1 is provided with a handle portion 8 for facilitating the removal thereof.

As shown in fig. 3, 6 and 9, the target frame 1 includes a target frame 1.1 and a target frame plate 1.2, and the target frame 1.1 is formed by mechanical pressing an aluminum alloy with a thickness of 2-2.5 mm; the target frame plate 1.2 is formed by mechanically pressing an aluminum alloy with the thickness of 1.5-2 mm. The upper end of the target frame 1.1 is provided with an upper frame box 1.3, the target frame slowing body block 6 and the target frame reflecting body block 7 are both arranged in the upper frame box 1.3, and the target frame plate 1.2 is buckled at the opening of the upper frame box 1.3 of the target frame 1.1 to realize the sealing of the upper frame box 1.3. The target frame moderating body block 6 and the target frame reflecting body block 7 are respectively made of neutron moderating materials and neutron reflecting materials by mechanical processing.

Assembling a neutron conversion target: the target frame slowing body block 6 and the target frame reflecting body block 7 are assembled in an upper frame box 1.3 which is mechanically pressed into a frame of the target frame 1, the target frame plate 1.2 is covered, and the target frame is screwed by a screw. The tantalum target 2 and the beryllium target 3 which are integrally bonded by adopting a mechanical coating and pressure-bearing mode are inlaid at the hollowed-out mounting position 5 of the target frame 1.1 and fixed.

Example 5:

this example was optimized based on example 1 above.

In order to better realize heat dissipation of the target frame 1 and improve the service life of the neutron conversion target, a heat dissipation component is arranged on one side of the target frame 1, the beryllium target 3 is positioned on one side close to the heat dissipation component, and because beryllium has good heat conductivity, the heat conductivity of the beryllium is 5 times that of copper and 6 times that of aluminum, and heat generated by high-energy protons striking the tantalum target 3 and the beryllium target 3 is easier to be conducted to the heat dissipation component.

Example 6:

this example was optimized based on example 5 above.

In order to avoid the high-energy neutrons leaking out through the gaps of the radiating frame and entering the accelerator hall as far as possible, the radiating assembly comprises the radiating frame and radiating pipes 30 arranged on the radiating frame, as shown in fig. 13, the radiating frame comprises a lower frame body structure 9 and an upper frame body structure 10, the width of the upper frame body structure 10 is larger than that of the lower frame body structure 9, a second bending structure 31 is arranged between the lower frame body structure 9 and the upper frame body structure 10, that is, the radiating frame adopts an inverted trapezoid structure design with a large upper part and a small lower part, and is not vertically communicated up and down, but has a bent edge structure design, so that direct beams can be effectively avoided, and a better leakage prevention effect is achieved.

Example 7:

this example was optimized based on example 6 above.

In order to enhance the heat dissipation effect on the neutron target, and simultaneously in order to realize the pluggable installation of the target holder 1, as shown in fig. 1, 3 and 11-14, the heat dissipation assembly comprises a metal heat dissipation panel 12, wherein the metal heat dissipation panel 12 is positioned in the heat dissipation holder and divides the space in the heat dissipation holder 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 tube 30 is arranged in the right space 14. Preferably, the heat dissipation frame is formed by mechanically pressing an aluminum alloy with the thickness of 2.5-3 mm; the metal heat dissipation panel 12 is made of aluminum alloy with the thickness of 1.5-2mm by mechanical pressing. The radiating pipe 30 is made of square copper cooling pipes and copper pipes with diameters of 15-20mm in a mechanical mode.

Because the accelerator hall dose is very high when the accelerator is operated, a person cannot enter the hall to replace the target plate structure 32 within a period of time after the accelerator is stopped, and the dose of tantalum and beryllium targets used by the accelerator is very high, the person is never allowed to touch, so that the robot or the intelligent picking and placing system must be used for replacing the target plate structure 32. In this technical scheme, design target frame 1 into plug type and fall trapezoidal structure, target frame 1 adopts split type design with the heat dissipation frame, and target frame 1 can be followed the heat dissipation frame and is torn down the change, is favorable to adopting robot or intelligence to get and puts the system and change target frame 1 and target plate structure 32 whole, and is swift again safe.

Example 8:

this example was optimized based on example 5 above.

In order to achieve better heat dissipation effect, and achieve better effect of moderating and reflecting high-energy neutrons, as shown in fig. 3, the heat dissipation frame is provided with a lower protruding portion 15 and an upper recessed portion 16, an inclined transition surface 17 is formed between the lower protruding portion 15 and the upper recessed portion 16, a right lower space is formed between the lower end of the metal heat dissipation panel 12 and the lower protruding portion 15, a right upper space is formed between the upper end of the metal heat dissipation panel 12 and the upper recessed portion 16, a coil pipe portion of the heat dissipation tube 30 is located in the right lower space, a heat dissipation frame reflector block 20 and a heat dissipation frame moderating body block 21 are arranged in the right upper space, and the heat dissipation frame reflector block 20 is located above the heat dissipation frame moderating body block 21. The radiator support reflector block 20 and the radiator support moderating block 21 are respectively made of neutron reflecting materials and neutron moderating materials by machining.

Assembling a heat radiation assembly: the radiator support reflector block 20 and the radiator support moderator block 21 are assembled in the right upper space, and the square copper cooling tube fabricated is fixed in the right space 14 and covered with the metal radiator panel 12.

It should be noted that ordinary light water may be used as the coolant. One 1ma,30me proton beam of the accelerator has 30KW, and the generated heat is transferred to the tantalum-beryllium neutron target, such large heat requiring a tantalum-beryllium neutron target heat dissipation system. In the heat radiation system, the heat on the beryllium target 3 is conducted to the heat radiation component, the heat radiation pipe 30 is cooled by light water, and the heat radiation component of the tantalum-beryllium neutron target can be shared with the accelerator water cooling system because the accelerator system is cooled by light water, so that the burden of newly arranging the tantalum-beryllium neutron target cooling system is reduced.

Example 9:

this example was optimized based on example 8 above.

In order to facilitate the detachable installation of the neutron conversion target on the heat dissipation frame, as shown in fig. 11-14, the heat dissipation frame comprises a base 22, a supporting body 23, a left side plate 24 and a right side plate 25, a lower protruding portion 15 and an upper recessed portion 16 are formed on the supporting body 23, the base 22 is fixedly connected with the lower end of the supporting body 23, the left side plate 24 and the right side plate 25 are respectively fixedly connected with the left side and the right side of the supporting body 23, vertical limit protrusions 26 are respectively arranged on the inner sides of the left side plate 24 and the right side plate 25, the metal heat dissipation panel 12 is positioned on the left side of the vertical limit protrusions 26, and the heat dissipation frame reflector block 20, the heat dissipation frame moderating body block 21 and the heat dissipation tube 30 are positioned on the right side of the vertical limit protrusions 26.

Preferably, in order to better realize the butt joint installation between the neutron conversion target and the heat dissipation assembly, the inner sides of the left side plate 24 and the right side plate 25 are respectively provided with a middle limiting protrusion 27 matched with the shape of the bending structure 11 on the target frame 1.

As shown in fig. 11, for convenience of mounting the metal heat-dissipating panel 12, the mount 22 is provided with a mounting groove 18, and the lower end of the metal heat-dissipating panel 12 is located in the mounting groove 18.

Example 10:

this example was optimized based on example 9 above.

In order to facilitate the installation of the radiating pipe 30 and improve the compactness of the structure, two limiting grooves 28 are respectively arranged on the upper concave portion 16, the extending section of the radiating pipe 30 is positioned in the corresponding limiting groove 28 and extends upwards to the outside of the limiting groove 28, and the extending section of the radiating pipe 30 is limited in the limiting groove 28 by the vertical limiting bulge 26. Meanwhile, because the replacement period of the radiating tube 30 is relatively long (the radiating tube 30 is generally replaced only by using a plurality of years), the radiating tube 30 and the radiating frame are designed into a buckle type structural design, so that the radiating tube 30 can be replaced after a plurality of years.

The utility model is mainly suitable for a conversion target system for converting protons into neutrons of a high-energy accelerator boron neutron capture treatment system with energy of about 30 Mev.

Finally, it should be noted that: the above is only a preferred embodiment of the present utility model and is not intended to limit the scope of the present utility model. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present utility model should be included in the protection scope of the present utility model.

Claims (10)

1. A tantalum, beryllium neutron target system suitable for BNCT, characterized in that: the high-temperature-resistant metal adhesive integrated target plate structure comprises a target plate structure and a target frame for installing the target plate structure, wherein the target plate structure comprises a tantalum target and a beryllium target, and the tantalum target and the beryllium target are adhered through the high-temperature-resistant metal adhesive to form the integrated target plate structure.

2. A tantalum, beryllium neutron target system for BNCT as defined in claim 1, wherein: the target frame comprises a hollowed-out installation position, and the target plate structure is installed at the hollowed-out installation position.

3. A tantalum, beryllium neutron target system for BNCT as defined in claim 2, wherein: the target frame comprises a lower extending structure and an upper extending structure, the hollowed-out installation position is located on the lower extending structure, the width of the upper extending structure is larger than that of the lower extending structure, and a first bending structure is arranged between the lower extending structure and the upper extending structure.

4. A tantalum, beryllium neutron target system for BNCT as claimed in claim 3, wherein: and a target frame slowing body block and a target frame reflecting body block are arranged in the upper extension structure.

5. A tantalum, beryllium neutron target system for BNCT as defined in claim 1, wherein: and a heat dissipation assembly is arranged on one side of the target frame, and the beryllium target is positioned on one side close to the heat dissipation assembly.

6. A tantalum, beryllium neutron target system for BNCT as recited in claim 5, wherein: the heat dissipation assembly comprises a heat dissipation frame and a heat dissipation pipe arranged on the heat dissipation frame, the heat dissipation frame comprises a lower frame body structure and an upper frame body structure, the width of the upper frame body structure is larger than that of the lower frame body structure, and a second bending structure is arranged between the lower frame body structure and the upper frame body structure.

7. A tantalum, beryllium neutron target system for BNCT as recited in claim 6, wherein: the heat dissipation assembly comprises a metal heat dissipation panel, wherein the metal heat dissipation panel is positioned in a 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.

8. A tantalum, beryllium neutron target system for BNCT as recited in claim 7, wherein: the heat dissipation frame has lower bellying and upper concave part, form the excessive face of slope down between bellying and the upper concave part, be right side lower part space between the lower extreme of metal heat dissipation panel and the bellying down, be right side upper portion space between the upper end of metal heat dissipation panel and the upper concave part, the coil pipe portion of cooling tube is located right side lower part space, be equipped with heat dissipation frame reflector piece and heat dissipation frame moderating body piece in the right side upper portion space.

9. A tantalum, beryllium neutron target system for BNCT as recited in claim 8, wherein: the heat dissipation frame comprises a base, a support body, a left side plate and a right side plate, wherein the lower protruding portion and the upper concave portion are formed on the support body, the base is fixedly connected with the lower end of the support body, the left side plate and the right side plate are respectively fixedly connected with the left side and the right side of the support body, vertical limiting protrusions are respectively arranged on the inner sides of the left side plate and the right side plate, and the metal heat dissipation panel is located on the left side of the vertical limiting protrusions.

10. A tantalum, beryllium neutron target system for BNCT as recited in claim 9, wherein: the upper concave part is respectively provided with two limiting grooves, the extension section of the radiating pipe is positioned in the corresponding limiting groove and extends upwards to the outside of the limiting groove, and the vertical limiting protrusion limits the extension section of the radiating pipe in the limiting groove.

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