CN115884488A - Tantalum and beryllium neutron target system suitable for BNCT - Google Patents

Abstract

The invention relates to the technical field of neutron targets, and discloses a tantalum and beryllium neutron target system suitable for BNCT (bayonet nut connector), 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 by a high-temperature-resistant metal adhesive to form an integrated target plate structure; the tantalum and beryllium neutron target system suitable for BNCT provided by the invention solves the problem that the energy utilization rate is low and the neutron yield cannot be maximized in the existing design.

Description

Tantalum and beryllium neutron target system suitable for BNCT

Technical Field

The invention 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 (BNCT for short) is a therapeutic method in which a thermal Neutron beam and a Boron-containing drug accumulated in tumor tissue undergo a nuclear reaction to release a ray with extremely strong killing power, thereby killing cancer cells. It is a new binary technology for precisely treating cancer. Firstly, it uses the targeted medicine of boron neutron to inject into human body, then it is gathered on the eliminated tumor, at the same time, the medicine is carried with the isotope of boron-10, said isotope has no radioactivity and has no toxicity. However, it has a good characteristic that when neutrons are incident, the reaction cross section with the neutrons is very large, and alpha particles and 7Li particles are generated after the neutrons and boron-10 have nuclear reaction. The two kinds of particles are greatly different from X-ray or gamma ray used in traditional radiotherapy, the flight distance is short and is about the length of one cell, and whichever cell adsorbs the targeted medicament containing boron can be accurately killed by neutrons without damaging surrounding normal cells. Meanwhile, as neutrons mainly act with boron-10 of the targeted drug, only approximate aiming is needed and the direction is correct. Therefore, the manufacturing cost of the boron neutron capture treatment equipment can be greatly reduced, the volume is greatly reduced, and the boron neutron capture treatment equipment is very simple.

The boron neutron capture treatment system of the existing accelerator is characterized in that a neutron conversion target system capable of converting protons into neutrons is required besides proton energy and beam current generated by the accelerator, the existing neutron conversion target system mainly adopts a single target to realize conversion of protons, but the proton energy generated by the accelerator is continuously released from a low energy end to a high energy end, so that the single target has relatively high neutron yield only under the condition of a certain energy range, and cannot sufficiently convert protons in other energy sections, and the energy conversion rate of the existing neutron conversion target system still needs to be improved.

Moreover, the accelerator is operated continuously, and the high-energy protons generated by the accelerator hit the neutron conversion target, so that huge heat is generated, and if the generated heat is not taken away in time, the temperature of the neutron conversion target is continuously increased, so that the normal operation of the system and the service life of the neutron conversion target are influenced, and therefore, cooling measures must be taken for the neutron conversion target.

In addition, the neutron conversion efficiency is gradually reduced along with the time change of the high-energy protons hitting the neutron conversion target, so that the neutron conversion target needs to be replaced periodically, and the replacement of the conventional neutron conversion target is not easy to operate, and further the service efficiency of the equipment system can be directly influenced.

Disclosure of Invention

It is an object of the present invention to provide a tantalum, beryllium neutron target system suitable for BNCT that solves at least one of the above-mentioned problems of the prior art.

In order to achieve the purpose, the invention adopts the following technical scheme:

the tantalum and beryllium neutron target system suitable for BNCT 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 integral target plate structure through a high-temperature-resistant metal adhesive.

In the technical scheme, because the target plate structure comprises the tantalum target and the beryllium target, the neutron yield generated by the tantalum target at the high-energy end (more than 20 Mev) of proton energy is high; the technical scheme adopts a structural design mode of a tantalum-beryllium composite target, protons in all energy sections can be fully converted into neutrons, and compared with a neutron conversion target with a single target material type, the neutron yield can be increased under the condition that proton sources are the same, so that the energy utilization rate is increased, and when the neutron conversion target is used in a BNCT treatment process, the treatment time can be effectively shortened, and the negative effects of the treatment process on patients are reduced. Because the tantalum target and the beryllium target are bonded into an integral target plate structure through the high-temperature-resistant metal bonding agent, the high-temperature-resistant metal bonding agent can tightly bond the tantalum target and the beryllium target together to form a seamless connection whole, so that the neutron yield generated by protons at high and middle energy ends is maximized, and the bonding composite mode has the advantages of simple process and low production cost.

Furthermore, for the installation of convenient realization to the target plate structure, simultaneously, for the better heat dissipation of realization to the target plate structure, the target frame includes fretwork installation position, the target plate structure is installed in fretwork installation position department.

Further, leak out and then enter into the accelerator hall in order to avoid high energy neutron to pass through the gap of target frame as far as, the target frame includes extension structure down and last extension structure, fretwork installation position is located extension structure down, it is greater than extension structure's width down to go up extension structure's width, it buckles structure 11 to have first between extension structure down and the last extension structure, also is, the target frame adopts big-end-up's trapezoidal structural design, and not vertical intercommunication from top to bottom has the structural design on the limit of buckling, reaches better effect of preventing leaking like this.

Furthermore, in order to better realize the moderation and reflection effect on the high-energy neutrons, a target frame moderating body block and a target frame reflector body block are arranged in the upper extension structure.

Furthermore, in order to better realize the heat dissipation of the target frame and prolong the service life of the neutron conversion target, a heat dissipation assembly is arranged on one side of the target frame, and the beryllium target is located on one side close to the heat dissipation assembly.

Further, leak away and then enter into the accelerator hall in order to avoid high-energy neutron to leak through the gap of heat dissipation frame as far as, radiator unit includes heat dissipation frame and the cooling tube of installing on heat dissipation frame, 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, it buckles structure 31 to have the second between lower part support body structure and the upper portion support body structure, also promptly, heat dissipation frame adopts big-end-up's trapezoidal structural design, is not vertical intercommunication from top to bottom, but has the structural design on the limit of buckling, reaches better effect of preventing leaking like this.

Further, in order to promote the radiating effect to the neutron target, in order to realize the plug-in installation to the target frame simultaneously, radiator unit 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 the left side space, the cooling tube sets up in the right side space.

Further, in order to reach better radiating effect, simultaneously, for the moderation and the reflex action of better realization to high energy neutron, heat dissipation frame has bellying and last depressed part down, form the excessive face of slope down between bellying and the last depressed part, be right side lower part space between lower extreme and the lower bellying of metal cooling panel, be right side upper portion space between metal cooling panel's the upper end and the last depressed part, the coil pipe position of cooling tube is in right side lower part space, be equipped with heat dissipation frame reflector block and heat dissipation frame moderation body block in the right side upper portion space.

Further, for the convenience of being detachable with neutron conversion target and installing on heat dissipation frame, heat dissipation frame includes base, supporter, left side board and right side board, bellying and last depressed part form on the supporter down, 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, for the convenient installation that realizes the cooling tube, promote the compactness of structure, be equipped with two spacing grooves on the last depressed part respectively, the extending section of cooling tube is located the spacing inslot that corresponds and upwards extends to the spacing inslot outside, vertical spacing arch is injectd the extending section of cooling tube in the spacing inslot.

The beneficial effects of the invention are as follows: in the technical scheme, because the target plate structure comprises the tantalum target and the beryllium target, the neutron yield generated by the tantalum target at the high-energy end (more than 20 Mev) of proton energy is high; the technical scheme adopts a structural design mode of a tantalum-beryllium composite target, protons in all energy sections can be fully converted into neutrons, and compared with a neutron conversion target with a single target material type, the neutron yield can be increased under the condition that proton sources are the same, so that the energy utilization rate is increased, and when the neutron conversion target is used in a BNCT treatment process, the treatment time can be effectively shortened, and the negative effects of the treatment process on patients are reduced. Because the tantalum target and the beryllium target are bonded into an integral target plate structure through the 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 connection whole, thereby maximizing the neutron yield generated by protons at high and middle energy ends, and the bonding composite mode has simple process and low production cost.

Drawings

FIG. 1 is a schematic front view of the present invention;

FIG. 2 isbase:Sub>A schematic cross-sectional view of A-A of FIG. 1;

FIG. 3 is an exploded view of the present invention;

FIG. 4 is a schematic view of a first perspective view of the present invention in use;

FIG. 5 is a side view of the present invention in use;

FIG. 6 is an exploded view of a neutron conversion target of the present invention;

FIG. 7 is a schematic diagram of a side view of a neutron conversion target according to the present invention;

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

FIG. 9 is a schematic view of a first perspective view of a neutron conversion target according to the present invention;

FIG. 10 is a schematic diagram of a second view of a neutron conversion target according to the present invention;

FIG. 11 is an exploded view of the heat sink assembly of the present invention;

FIG. 12 is a first perspective view of a heat dissipation assembly of the present invention;

FIG. 13 is a second perspective view of the heat dissipation assembly of the present invention;

FIG. 14 is a third perspective view of a heat sink assembly according to the present invention;

in the figure: a target stand 1; a target frame 1.1; target frame 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; a hollow mounting position 5; the target frame moderating block 6; a first moderator block bend structure 6.1; a target reflector block 7; a handle part 8; a lower frame structure 9; an upper frame structure 10; a first bending structure 11; a metal heat radiation panel 12; the left space 13; the right side space 14; a lower boss portion 15; an upper recess 16; an inclined transition surface 17; a mounting groove 18; a heat sink reflector block 20; a heat sink moderator 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 limiting groove 28; a flow 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 invention or the technical solutions in the prior art, the present invention will be briefly described below with reference to the accompanying drawings and the embodiments or the description in the prior art, it is obvious that the following description of the structure of the drawings is only some embodiments of the present invention, and other drawings can be obtained by those skilled in the art without creative efforts. It should be noted that the description of the embodiments is provided to help understanding of the present invention, and the present invention is not limited thereto.

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, comprising a target plate structure 32 and a target holder 1 for mounting the target plate structure 32, wherein the target plate structure 32 comprises 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 percent. Specifically, the cutting tool can be formed by cutting a tantalum plate with the same thickness as that of the tantalum target 2; or a tantalum rod with the same diameter as the tantalum target 2 can be selected and cut by a wire cutting machine. The beryllium target 3 is a high-purity beryllium target material. Beryllium content: 99.99 percent. Specifically, a beryllium rod 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 bonded by the high-temperature-resistant metal bonding agent 4 to form an integrated target plate structure 32, the high-temperature-resistant metal bonding agent 4 capable of selectively resisting the temperature of about 300 ℃ is more in variety, and the tantalum target 2 and the beryllium target 3 can be bonded in a seamless mode by adopting a mechanical coating and pressure-bearing mode as long as the metal bonding agent is capable of resisting the temperature of about 300 ℃, is environment-friendly, oil-resistant, waterproof, corrosion-resistant, impact-resistant and aging-resistant.

In the technical scheme, because 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 technical scheme adopts a structural design mode of a tantalum-beryllium composite target, protons in all energy sections can be fully converted into neutrons, and compared with a neutron conversion target with a single target material type, the neutron yield can be increased under the condition that proton sources are the same, so that the energy utilization rate is increased, the treatment time can be effectively shortened when the neutron conversion target is used in a BNCT treatment process, and negative effects on a patient caused by the treatment process are reduced. Because the tantalum target 2 and the beryllium target 3 are bonded into an integral target plate structure 32 through the high-temperature-resistant metal bonding agent 4, the high-temperature-resistant metal bonding agent can tightly bond 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 middle energy ends is maximized, and the bonding composite mode has the advantages of simple process and low production cost.

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 leading-out end of the accelerator beam line system, 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 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 embodiment is optimized based on embodiment 1 described above.

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

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

It should be noted that the target plate structure 32 may be designed with a connection structure that is easily detachable from the target stand 1, and the radioactivity on the target stand 1 to be used may naturally decay over time to reduce the dose to an allowable level, so that the target plate structure 32 may be removed and the target stand 1 may be reused.

Example 3:

this example was optimized based on example 2 described above.

In order to avoid high-energy neutrons to leak out through the gap of target stand 1 and then enter into the accelerator hall as far as possible, as shown in fig. 1 and fig. 8, the target stand 1 comprises a lower extension structure 1.5 and an upper extension structure 1.4, the hollowed-out installation 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, a first bending structure 11 is arranged between the lower extension structure 1.5 and the upper extension structure 1.4, namely, the target stand 1 adopts an inverted trapezoid structure design with a large upper part and a small lower part, the upper part and the lower part are not vertically communicated, but the structural design with a bending edge is adopted, direct beam passing can be effectively avoided, and a better anti-leakage effect is achieved.

Example 4:

this embodiment is optimized based on embodiment 3 described above.

As shown in fig. 6, in order to better realize the moderation and reflection effect on the high-energy neutrons, a target holder moderating body block 6 and a target holder reflecting body block 7 are arranged in the upper extension structure 1.4, the target holder reflecting body block 7 is positioned above the target holder moderating body block 6, first moderating body block bending structures 6.1 matched with the first bending structures 11 of the target holder 1 are arranged on two sides of the target holder moderating body block 6, direct beam penetration can be effectively avoided, so that a better leakage-preventing effect is achieved, the target holder moderating body block 6 matched with the inverted trapezoid structures of the target holder 1 is easy to process, maintain or replace, and assembly and disassembly are also convenient.

Preferably, in order to conveniently replace the target holder 1, the upper end of the target holder 1 is provided with a handle part 8 which is convenient to take out.

It should be noted that, as shown in fig. 3, 6 and 9, the target holder 1 includes a target holder frame 1.1 and a target holder plate 1.2, and the target holder frame 1.1 is formed by mechanical pressing with an aluminum alloy having a thickness of 2-2.5 mm; the target frame plate 1.2 is made of aluminum alloy with the thickness of 1.5-2mm by mechanical pressing. The upper end of the target frame 1.1 is provided with an upper frame box 1.3, the target frame slowing-down 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 block 6 and the target frame reflector block 7 are respectively made of neutron moderating materials and neutron reflecting materials through mechanical processing.

Assembling the neutron conversion target: the target moderator block 6 and the target reflector block 7 are assembled in the upper casing 1.3 of the target 1, which is mechanically pressed, and the target plate 1.2 is covered and screwed on. And (3) embedding the tantalum target 2 and the beryllium target 3 which are seamlessly adhered into a whole by adopting a mechanical coating and pressure-bearing mode at the hollow installation position 5 of the target frame 1.1 and fixing.

Example 5:

this embodiment is optimized based on embodiment 1 described above.

In order to better realize the heat dissipation of the target holder 1 and prolong the service life of the neutron conversion target, one side of the target holder 1 is provided with a heat dissipation assembly, the beryllium target 3 is positioned at one side close to the heat dissipation assembly, because beryllium has good heat conductivity, the heat conductivity of beryllium is 5 times that of copper and 6 times that of aluminum, and the heat generated when high-energy protons impact on the tantalum and beryllium targets 3 is easier to be conducted to the heat dissipation assembly.

Example 6:

this embodiment is optimized based on embodiment 5 described above.

In order to avoid high-energy neutrons to leak out through the gap of heat dissipation frame and then enter into the accelerator hall as far as possible, the heat dissipation assembly comprises a heat dissipation frame and a heat dissipation pipe 30 installed on the heat dissipation frame, as shown in fig. 13, the heat dissipation 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 greater 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, namely, the heat dissipation frame adopts an inverted trapezoidal structure design with a large upper part and a small lower part, the upper part and the lower part are not vertically communicated, but have a structural design with a bending edge, direct bundling can be effectively avoided, and a better leakage-proof effect is achieved.

Example 7:

this embodiment is optimized based on embodiment 6 described above.

In order to improve the heat dissipation effect on the neutron target and simultaneously achieve the plug-in installation of the target holder 1, as shown in fig. 1, fig. 3, and fig. 11 to fig. 14, the heat dissipation assembly includes a metal heat dissipation panel 12, the metal heat dissipation panel 12 is located 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 disposed 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 heat dissipation pipe 30 is a square copper cooling pipe, and is made of a copper pipe with the diameter of 15-20mm by a mechanical method.

Because the dosage of the hall of the accelerator is very high when the accelerator is running, personnel cannot enter the hall to replace the target plate structure 32 within a period of time after the accelerator is stopped, and the dosage of the tantalum and beryllium target used by the accelerator is very high and is not allowed to be contacted by the personnel, therefore, the target plate structure 32 must be replaced by adopting a robot or an intelligent picking and placing system. Among this technical scheme, become the trapezoidal structure of plug-in formula of target frame 1 design, target frame 1 adopts split type design with the heat dissipation frame, and target frame 1 can be followed the heat dissipation and put and pull down the change, is favorable to adopting robot or intelligence to get the system and change target frame 1 and target plate structure 32 wholly, not only swift but also safety.

Example 8:

this embodiment is optimized based on embodiment 5 described above.

In order to achieve better heat dissipation effect and better realize moderation and reflection action on high-energy neutrons, as shown in fig. 3, the heat dissipation frame has a lower convex portion 15 and an upper concave portion 16, an inclined transition surface 17 is formed between the lower convex portion 15 and the upper concave portion 16, a right lower space is formed between the lower end of the metal heat dissipation panel 12 and the lower convex portion 15, a right upper space is formed between the upper end of the metal heat dissipation panel 12 and the upper concave portion 16, the coil portion of the heat dissipation pipe 30 is located in the right lower space, a heat dissipation frame reflector block 20 and a heat dissipation frame moderation block 21 are arranged in the right upper space, and the heat dissipation frame reflector block 20 is located above the heat dissipation frame moderation block 21. The heat dissipation frame reflector block 20 and the heat dissipation frame moderating block 21 are respectively made of neutron reflection materials and neutron moderating materials through machining.

Assembling the heat dissipation assembly: the heat sink reflector block 20 and the heat sink moderator block 21 are fitted in the right upper space, and the square copper cooling tube thus produced is fixed in the right space 14 and covered with the metal heat sink panel 12.

It should be noted that ordinary light water can 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, so that the large heat needs a heat dissipation system of the tantalum-beryllium neutron target. In the heat dissipation system, heat on the beryllium target 3 is conducted to the heat dissipation assembly, the heat dissipation pipe 30 is cooled by light water, and the heat dissipation assembly of the tantalum-beryllium neutron target can be shared with the accelerator water cooling system because the accelerator system is also cooled by the light water, so that the burden of newly adding the tantalum-beryllium neutron target cooling system is reduced.

Example 9:

this embodiment is optimized based on embodiment 8 described above.

In order to facilitate the neutron conversion target to be detachably mounted on the heat dissipation frame, as shown in fig. 11-14, the heat dissipation frame includes a base 22, a support 23, a left side plate 24 and a right side plate 25, a lower protrusion 15 and an upper recess 16 are formed on the support 23, the base 22 is fixedly connected with the lower end of the support 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 support 23, vertical limiting 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 located on the left side of the vertical limiting protrusions 26, and the heat dissipation frame reflector block 20, the heat dissipation frame moderator block 21 and the heat dissipation pipe 30 are located on the right side of the vertical limiting 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 bending structure 11 on the target holder 1 in shape.

As shown in fig. 11, in order to facilitate the installation of the metal heat dissipation panel 12, the base 22 is provided with an installation groove 18, and the lower end of the metal heat dissipation panel 12 is located in the installation groove 18.

Example 10:

this embodiment is optimized based on embodiment 9 described above.

In order to facilitate the installation of the heat dissipation pipe 30 and improve the compactness of the structure, two retaining grooves 28 are respectively formed on the upper concave portion 16, the extension sections of the heat dissipation pipe 30 are located in the corresponding retaining grooves 28 and extend upwards to the outside of the retaining grooves 28, and the vertical retaining protrusions 26 define the extension sections of the heat dissipation pipe 30 in the retaining grooves 28. Meanwhile, since the heat dissipation tube 30 has a long replacement period (generally, it is replaced after several years of use), the heat dissipation tube 30 and the heat dissipation frame are designed to be of a snap-in structure, which is convenient for replacing the heat dissipation tube 30 after several years.

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

Finally, it should be noted that: the above are merely preferred embodiments of the present invention, and are not intended to limit the scope of the present invention. Any modification, equivalent replacement, or improvement made within the spirit and principle of the present invention should be included in the protection scope of the present invention.

Claims (10)

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

2. The tantalum, beryllium neutron target system suitable for BNCT according to claim 1, wherein: the target frame comprises a hollow installation position, and the target plate structure is installed at the hollow installation position.

3. The tantalum, beryllium neutron target system suitable for BNCT according to claim 2, wherein: the target frame includes extension structure and last extension structure down, fretwork installation position is located extension structure down, the width of going up extension structure is greater than extension structure's width down, the extension structure down with last extension structure between have a structure of buckling.

4. The tantalum and beryllium neutron target system suitable for BNCT according to claim 3, wherein: the upper extension structure is internally provided with a target frame slowing-down block and a target frame reflector block.

5. The tantalum and beryllium neutron target system suitable for BNCT according to 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. The tantalum, beryllium neutron target system suitable for BNCT according to claim 5, wherein: the radiating assembly comprises a radiating frame and a radiating pipe arranged on the radiating frame, the radiating frame comprises a lower frame body structure and an upper frame body structure, the width of the upper frame body structure is greater 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. The tantalum and beryllium neutron target system suitable for BNCT according to claim 6, wherein: the heat dissipation assembly comprises a metal heat dissipation panel, the metal heat dissipation panel 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 tube is arranged in the right space.

8. The tantalum, beryllium neutron target system suitable for BNCT according to claim 5, wherein: the heat dissipation frame is provided with a lower protruding portion and an upper recessed portion, an inclined transition surface is formed between the lower protruding portion and the upper recessed portion, a right lower portion space is formed between the lower end of the metal heat dissipation panel and the lower protruding portion, a right upper portion space is formed between the upper end of the metal heat dissipation panel and the upper recessed portion, the coil pipe portion of the heat dissipation tube is located in the right lower portion space, and a heat dissipation frame reflector block and a heat dissipation frame moderation block are arranged in the right upper portion space.

9. The tantalum, beryllium neutron target system suitable for BNCT according to claim 8, wherein: the heat dissipation frame comprises a base, a supporting body, a left side plate and a right side plate, a lower protruding portion and an upper recessed portion are formed on the supporting body, the base is fixedly connected with the lower end of the supporting body, the left side plate and the right side plate are fixedly connected with the left side and the right side of the supporting body respectively, vertical limiting protrusions are arranged on the inner sides of the left side plate and the right side plate respectively, and the metal heat dissipation panel is located on the left side of the vertical limiting protrusions.

10. The tantalum, beryllium neutron target system suitable for BNCT of claim 9, wherein: go up the depressed part and be equipped with two spacing grooves on the respectively, the extending section of cooling tube is located the spacing inslot that corresponds and upwards extends to the spacing inslot outside, vertical spacing arch is injectd the extending section of cooling tube in the spacing inslot.

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