A distributed BNCT neutron target system with a long life cycle

Abstract

The present invention provides a distributed BNCT neutron target system with a long life cycle, the BNCT neutron target system comprising: a functional component, the functional component comprising a continuous strip-shaped active layer and a bearing layer for bearing the active layer, the bearing layer having a width and length not less than the active layer; one end of the functional component is mounted on a first reel assembly, the other end is mounted on a second reel assembly, and a working area is formed between the first reel assembly and the second reel assembly, the working area comprising an incident area of ​​an incident particle line; a disc-shaped or annular interception component, the interception component is located at the downstream side of the working area and does not contact the functional component, the interception component comprises a heat dissipation layer and a hydrogen storage layer arranged in contact with each other, the hydrogen storage layer is arranged opposite to one side of the bearing layer of the functional component. The present invention solves the problem of target material scrapping caused by defects such as short service life of the target material and bubbling during use in conventional fixed BNCT neutron targets.

Description

Technical Field

[0001] The present invention relates to the technical field of boron neutron capture therapy (BNCT for short), and in particular to a distributed BNCT neutron target system with a long life cycle. Background Art

[0002] Boron Neutron Capture Therapy (BNCT) is a cutting-edge cancer treatment method that combines the principles of nuclear physics and biomedicine. The principle of this therapy is to accelerate protons to a certain energy through an accelerator and then bombard the target to form a neutron beam, which is then shaped and then used to combine neutrons with boron-10 ( 10 B) The property of producing nuclear reactions, by selectively delivering boron compounds to cancer cells and irradiating these cells with neutron beams, thus initiating nuclear reactions and releasing high-energy particles that are able to damage the DNA of cancer cells, leading to cancer cell death.

[0003] Neutron targets are key components of BNCT equipment, which are used to generate neutron beams for cancer treatment. The selection and design of neutron targets are crucial to the efficacy and safety of BNCT. Neutron targets are generally made of 9 Be(p,n) 9 B reaction, 7 Li(P,n) 7 Be reaction. However, when using this 9 Be(p,n) 9 In order to produce the amount of neutrons required for BNCT during the B reaction, the proton acceleration energy needs to be increased to 30MeV, and the energy of the neutrons produced will also increase accordingly. 7 Li(P,n) 7 In the Be reaction, the acceleration energy of protons is 9 Be(p,n) 9 B reaction, set lower at 2.5 MeV, 9 Be(p,n) 9 The acceleration energy of protons in the B reaction is one order of magnitude lower, the energy of the neutrons produced is significantly lower than that of the Be target, and the energy consumption for decelerating the neutrons is also low. Therefore, in BNCT, 7 Li(P,n) 7 The utilization of Be reaction has received extensive attention.

[0004] In accelerator boron neutron capture therapy, the proton beam is accelerated by an accelerator. The proton beam is accelerated to an energy sufficient to overcome the Coulomb repulsion of the target nucleus and undergoes a nuclear reaction with the target to produce neutrons. Therefore, in the process of producing neutrons, the target will be bombarded by an accelerated proton beam of very high energy level. A small number of protons undergo nuclear reactions with the neutron target to produce neutrons, and a large number of high-speed protons gradually slow down in the neutron target until their speed is zero and then deposit in the neutron target. The energy of the high-speed protons is absorbed by the neutron target, causing the temperature of the target to rise significantly. At the same time, the metal part of the target is prone to blistering, which affects the service life of the target.

[0005] The patent with application number 201911264901.0 discloses a target material for a neutron beam generator. The patent with application number 202210824444.1 discloses a target material for a particle beam generator. The above patents all adopt the conventional fixed target method, and the service life of the target material is extended to a certain extent by arranging different heat dissipation layers and anti-foaming layers. The patent with application number 202210788155.0 discloses a lithium target for BNCT, which attempts to solve the problem of heating and bubbling of neutron targets by setting an anisotropic carbon substrate, but its technical solution has certain problems: when no intermediate metal is set, the protons in the path cannot be captured; when the intermediate metal is set, the protons in the path are captured by the intermediate metal, which is equivalent to the heat of protons bombarding the lithium target and the intermediate metal layer being conducted through the anisotropic carbon substrate for heat dissipation; its heat dissipation has more conduction process of the anisotropic carbon substrate, but it is not as good as the heat conduction distance of the heat dissipation method without anisotropic carbon substrate and directly conducted by the intermediate metal layer after heat conduction, and the path is shorter.

[0006] Although the above technical solutions have solved the problems of heat dissipation and bubbling of neutron targets to a certain extent, the existing solutions all adopt a fixed target method, and the loading of the active layer material used for nuclear reaction with protons is small. When the reaction proceeds to a certain extent, the thickness of the active layer material is significantly reduced, resulting in extremely low neutron production. Therefore, this type of neutron target has a short service life due to the small loading of the active layer material. In addition, the neutron target is radioactive after neutron bombardment due to nuclear reaction or activation, which has certain pollution and is inconvenient to replace.

[0007] Therefore, it is necessary to propose a new technical solution to solve the above problems. Summary of the invention

[0008] The technical problem to be solved by the present invention is to overcome the deficiencies of the prior art and provide a BNCT neutron target system with a long life cycle.

[0009] In order to solve the above technical problems, the basic concept of the technical solution adopted by the present invention is as follows: (1) The service life of the neutron target is greatly improved by changing the active layer material into a continuous strip. (2) The heat dissipation and blistering problems are solved by dividing the process of high-speed proton bombardment of the target material into two parts. One part of the protons bombards the active layer material to produce neutrons. For this part, the present invention designs a functional component including an active layer and a bearing layer; the other part, most of the high-speed protons that do not undergo nuclear reactions penetrate the functional component and are intercepted and absorbed by the hydrogen storage layer set in the interception component. The reaction of the first part of proton bombardment to produce neutrons is an endothermic reaction. The heat of this part is mainly generated by the penetration of high-speed protons. The heat generated by this part can be reduced by reducing the thickness of the active layer and the bearing layer. In addition, the temperature rise can be avoided by cooling the functional component. On the other hand, the heat absorption capacity of the functional component can be improved by pre-cooling the functional component. The second part of the heat generation is generated by the deposition of most of the protons that do not undergo nuclear reactions. This part is also the part of conventional target material blistering. For this part, the present invention designs an interception component composed of a hydrogen storage layer and a heat dissipation layer. The hydrogen storage layer can store a large number of protons that have not undergone nuclear reactions. The heat dissipation layer fits tightly with the hydrogen storage layer. The heat can be quickly taken away by passing coolant through the heat dissipation layer to avoid the problem of excessive temperature rise in this part. At the same time, due to the distributed design of functional components and interception components, even if the interception components have defects such as bubbling or deformation, it will not affect the normal operation of the neutron target system. The service life of the neutron target system has been greatly improved.

[0010] A key parameter of the BNCT neutron target is the neutron yield. When the active layer material of the neutron target is metallic lithium, the energy of the proton beam and the thickness of the active layer have a greater impact on the neutron yield. Through simulation calculations, it can be seen that when the proton beam energy is 2.2MeV, the neutron yield is maximum when the thickness of the metallic lithium layer is about 50μm; when the proton beam energy is 2.5MeV, the neutron yield is maximum when the thickness of the metallic lithium layer is about 98μm; when the proton beam energy is 3MeV, the neutron yield is maximum when the thickness of the metallic lithium layer is about 188μm. This also shows that the conventional BNCT neutron target will inevitably affect the neutron yield as the use time increases, thereby affecting the treatment effect. The distributed BNCT neutron target system of the present invention has an active layer of a continuous strip, which can enable the neutron target to always maintain a relatively large neutron yield over a long period of use.

[0011] Specifically, the present invention provides a distributed BNCT neutron target system with a long life cycle, and the distributed BNCT neutron target system includes: a functional component, the functional component includes a continuous strip-shaped active layer and a bearing layer for bearing the active layer, the material of the active layer includes at least any one of the following materials: metallic lithium, lithium alloy, beryllium, beryllium alloy, the bearing layer has a width and length not less than that of the active layer; a first reel assembly and a second reel assembly located at both ends of the functional component, one end of the functional component is mounted on the first reel assembly, and the other end is mounted on the second reel assembly, and a working area is formed between the first reel assembly and the second reel assembly, and the working area includes an inlet The incident area of ​​the radiated particle beam; a disc-shaped or annular intercepting component, which is located on the downstream side of the working area and has no contact with the functional component, and the intercepting component comprises a heat dissipation layer and a hydrogen storage layer which are arranged in contact with each other, and the hydrogen storage layer is arranged opposite to one side of the bearing layer in the functional component; the first retractable reel component and the second retractable reel component have mutually coordinated reeling and unreeling states, when the first retractable reel component is in the unreeling state, the second retractable reel component is in the reeling state, and at this time the functional component is transferred from the first retractable reel component to the second retractable reel component; when the first retractable reel component is in the reeling state, the second retractable reel component is in the unreeling state, and at this time the functional component is transferred from the second retractable reel component to the first retractable reel component.

[0012] Optionally, the thickness of the active layer is 20-300 μm, preferably 100-200 μm.

[0013] Optionally, the distance between the functional component and the interception component is 0.1-200 mm, preferably 1-10 mm.

[0014] Optionally, the bearing layer is a material with good thermal conductivity, and its material includes at least any one of the following materials: copper, aluminum, iron, graphite, or carbon-based materials such as graphene.

[0015] Optionally, the bearing layer has a thickness of 2-50 μm, preferably 3-8 μm.

[0016] Optionally, the material of the hydrogen storage layer includes at least any one of the following materials: tantalum, palladium, tantalum alloy, palladium alloy, magnesium alloy, titanium alloy.

[0017] Optionally, the thickness of the hydrogen storage layer is 10-100 μm, preferably 30-80 μm.

[0018] Optionally, the material of the heat dissipation layer includes at least any one of the following materials: copper, copper alloy, aluminum, aluminum alloy, and carbon-based material.

[0019] Optionally, a channel for cooling liquid flow is provided in the heat dissipation layer.

[0020] Optionally, the distributed BNCT neutron target system further includes a precooling component, and the precooling component is used to precool the functional component in a rolled-up state.

[0021] Optionally, the distributed BNCT neutron target system further includes a cooling component, which is located on at least one side of the working area and is used to cool the functional component in the unwinding state during the working process of the neutron target.

[0022] Optionally, the cooling assembly includes cooling rollers located on both sides of the working area.

[0023] Optionally, the hydrogen storage layer is arranged in a circular ring shape on the heat dissipation layer, and the width of the circular ring of the hydrogen storage layer is greater than or equal to the diameter of the bombardment range of the incident particle beam.

[0024] Optionally, the interception assembly is rotatable.

[0025] After adopting the above technical solution, the present invention has the following beneficial effects compared with the prior art:

[0026] 1. Solved the heat dissipation problem of neutron target. The heat is organically divided into two parts by distributing the neutron target. The first part dissipates heat efficiently by absorbing heat through nuclear reaction, cooling functional components to remove heat, and precooling functional components to improve heat carrying capacity. The heat generation can also be reduced by reducing the thickness of the bearing layer. The second part is quickly cooled by the heat dissipation layer, which fundamentally solves the problem of melting of the active layer caused by heat problems of conventional target materials.

[0027] 2. A strip-shaped continuous active layer is designed, which greatly increases the material loading capacity of the active layer of the neutron target system and greatly improves the service life of the neutron target.

[0028] 3. The distributed BNCT neutron target system is innovatively designed, which structurally separates the part of the conventional target material that is prone to foaming and deformation from the part that produces neutrons in the nuclear reaction, avoiding the impact of defects such as foaming and deformation on the active layer. It fundamentally solves the impact of defects such as detachment and deformation of the active layer caused by foaming.

[0029] 4. The interception layer adopts a disc or ring design and can rotate, so that high-speed protons bombard different positions to avoid heat accumulation. Compared with conventional targets, the heat dissipation area is greatly increased, and the continuous bombardment heat generation process of conventional targets is converted into intermittent local bombardment. The heat dissipation effect is significantly improved compared with conventional solutions.

[0030] The specific implementation modes of the present invention are further described in detail below in conjunction with the accompanying drawings. BRIEF DESCRIPTION OF THE DRAWINGS

[0031] Figure 1 This is a schematic diagram of a conventional circular neutron target and its proton beam bombardment range;

[0032] Figure 2 It is a schematic diagram of a conventional rectangular neutron target and its proton beam bombardment range;

[0033] Figure 3 It is a schematic diagram of the distributed BNCT neutron target system of the present invention;

[0034] Figure 4 A top view of the distributed BNCT neutron target system of the present invention;

[0035] Figure 5 Schematic diagram of functional components of the distributed BNCT neutron target system of the present invention;

[0036] Figure 6 A schematic diagram of the effective proton beam bombardment area of ​​the functional component of the present invention;

[0037] Figure 7 A schematic diagram of an interception assembly of a distributed BNCT neutron target system of the present invention;

[0038] Figure 8 This is a schematic diagram of the working process of a conventional neutron target;

[0039] Fig. 9 It is a schematic diagram of the working process of the distributed BNCT neutron target system of the present invention.

[0040] Description of the figure number:

[0041] CnT conventional circular neutron target; RnT conventional rectangular neutron target; DnT distributed neutron target system; 100 functional component; 110 action layer; 120 bearing layer; 121 target material backing plate; 200 interception component; 210 hydrogen storage layer; 220 heat dissipation layer; 230 cooling channel; 310 first unwinding and rewinding component; 320 second unwinding and rewinding component; 410 first precooling component; 420 second precooling component; 510 first cooling component; 520 second cooling component; p proton; n neutron; Q1 first part of heat; Q2 second part of heat; Q total heat generated by proton beam bombardment. DETAILED DESCRIPTION

[0042] In order to make the purpose, technical solution and advantages of the present invention more clearly understood, the present invention is further described in detail below in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain the present invention and are not used to limit the present invention.

[0043] Figure 1The schematic diagram of a conventional circular neutron target is shown, which is mainly composed of a target backing plate 121 and an active layer 110, and the active layer 110 is closely attached to the target backing plate 121; a channel for cooling liquid is usually provided inside the target backing plate 121, and the cooling liquid is used to flow at high speed from the inside of the target backing plate 121 to take away all the heat generated when the proton beam bombards the conventional circular neutron target CnT. The target backing plate 121 and the active layer 110 are usually set in a circular shape, and the diameter of the active layer 110 is slightly larger than the proton beam bombardment range.

[0044] Figure 2 A schematic diagram showing a conventional rectangular neutron target, with Figure 1 The conventional circular neutron target has the same structure, and only the appearance size and the internal channel setting of the target backing plate 121 are different. The conventional rectangular neutron target RnT is also composed of the target backing plate 121 and the active layer 110, and the active layer 110 is closely attached to the target backing plate 121.

[0045] refer to Figure 1 , Figure 2 and Figure 8 When the proton beam bombards the neutron target, most of the protons that do not undergo nuclear reactions will be deposited on the target backing plate 121, causing blister defects on the target backing plate 121, which may cause the active layer 110 to deform or even fall off. Therefore, a hydrogen storage layer 210 is usually provided between the target backing plate 121 and the active layer 110 to alleviate the impact of blistering to a certain extent.

[0046] refer to Figure 3 and Figure 4 , showing the distributed BNCT neutron target system of the present invention. The distributed neutron target system DnT is mainly composed of a functional component 100 and an interception component 200. The functional component 100 is a continuous strip and is in a roll shape, one end of which is connected to the first reel assembly 310, and the other end is connected to the second reel assembly 320; the interception component 200 is disc-shaped or ring-shaped, and the interception component 200 is composed of a hydrogen storage layer 210 and a heat dissipation layer 220; the functional component 100 is located above one side of the hydrogen storage layer of the interception component 200, and the functional component 100 and the interception component 200 maintain a small distance but do not contact each other; when the distributed neutron target system DnT is working, the functional component 100 reciprocates between the first reel assembly 310 and the second reel assembly 320, and the interception component 200 can rotate.

[0047] refer to Figures 3 to 7As a specific embodiment of the present invention, the distributed neutron target system DnT further includes a first precooling component 410 and a second precooling component 420, wherein the first precooling component 410 is used to precool the coil of the functional component 100 on the first reeling and unreeling component 310, and the second precooling component 420 is used to precool the coil of the functional component 100 on the second reeling and unreeling component 320. By precooling the functional component 100, the temperature of the functional component 100 can be greatly reduced, so that it can absorb more energy without melting. As a specific embodiment of the present invention, the distributed neutron target system DnT can also include a first cooling component 510 and a second cooling component 520. The first cooling component 510 and the second cooling component 520 are respectively arranged on both sides of the proton beam bombardment range, which not only isolates the partial functional components 100 bombarded by the proton beam from the rolled functional components 100 on the first reel-and-unreel component 310 and the second reel-and-unreel component 320, but also cools the functional components 100 during the unwinding and winding processes; that is, the influence of the proton beam bombardment on the rolled functional components 100 on the first reel-and-unreel component 310 and the second reel-and-unreel component 320 is avoided, and the functional components 100 after the proton beam bombardment are quickly cooled.

[0048] refer to Figures 3 to 6 In the distributed neutron target system DnT of the present invention, the functional component 100 is composed of an action layer 110 and a bearing layer 120 and is a continuous coiled strip. The functional component 100 reciprocates between the first unwinding and rewinding component 310 and the second unwinding and rewinding component 320, so the proton bombardment range is as follows: Figure 6 Shown are continuous rectangular areas.

[0049] refer to Figure 1 , Figure 2 and Figure 6 Assuming that the proton beam bombardment range is a circle of φ100 mm, the effective bombardment area of ​​the active layer 110 of the conventional circular neutron target CnT and the conventional rectangular neutron target RnT is:

[0050]

[0051] In the above formula, S C is the effective bombardment area of ​​the conventional circular neutron target; S R is the effective bombardment area of ​​a conventional rectangular neutron target.

[0052] The functional component in the distributed neutron target system DnT of the present invention is a continuous coiled strip, and its length can be set arbitrarily as needed. Assuming that the length of the functional component 100 is 1000m, the length of the active layer 110 and the bearing layer 120 is also 1000m. The effective area of ​​the active layer 110 that can be bombarded by the proton beam is approximately:

[0053]

[0054] In the above formula, S D It is the effective bombardment area of ​​the active layer 110 in the distributed neutron target system of the present invention.

[0055] When the length of the functional component 100 in the present invention is 1000 m, the effective bombardment area S of the active layer 110 in the distributed neutron target system is D is the effective bombardment area S of the conventional circular neutron target active layer 110 C Or the effective bombardment area S of the conventional rectangular neutron target action layer 110 R The multiples of are:

[0056]

[0057] It can be seen from the above formula that the effective bombardment area of ​​the active layer 110 of the distributed neutron target system DnT of the present invention can reach tens of thousands of times the effective bombardment area of ​​the conventional circular neutron target CnT and the conventional rectangular neutron target RnT. When the parameters such as the proton beam bombardment energy and the thickness of the active layer 110 are the same, the distributed neutron target system DnT of the present invention greatly increases the lithium loading in the active layer 110, thereby greatly increasing the service life of the neutron target system.

[0058] refer to Figure 8 Schematic diagram of the working process of a conventional circular neutron target CnT or a conventional rectangular neutron target RnT. Figure 8 The structure in the figure is an improved neutron target with a conventional circular neutron target CnT or a conventional rectangular neutron target RnT with a hydrogen storage layer 210 added. After the proton beam bombardment, part of the protons p undergo a nuclear reaction with the action layer 110 to produce neutrons n; another part of the protons p do not undergo a nuclear reaction with the action layer 110, and are decelerated to zero when penetrating the action layer 110 and the hydrogen storage layer 210, and are finally deposited in the hydrogen storage layer 210. Therefore, the heat generated by this type of conventional neutron target is mainly in the action layer 110 and the hydrogen storage layer 210, and the total heat generated by the proton beam bombardment is Q. The heat in the action layer 110 and the hydrogen storage layer 210 is dissipated through the heat dissipation layer 220 (i.e., the target material back plate 121 in the conventional neutron target), especially the heat in the action layer 110 needs to be conducted to the heat dissipation layer 220 through the hydrogen storage layer 210 to dissipate the heat, which increases the conduction path and the heat dissipation efficiency is relatively low. After working for a long time, the hydrogen storage layer 210 will inevitably have defects such as bubbling to a certain extent, which will directly cause the active layer 110 to deform or even peel off from the hydrogen storage layer 210, thereby causing the neutron target to be scrapped.

[0059] refer to Fig. 9The figure is a schematic diagram of the working process of the distributed neutron target system DnT of the present invention. The functional component 100 composed of the action layer 110 and the bearing layer 120 does not contact the interception component 200 composed of the hydrogen storage layer 210 and the heat dissipation layer 220, and has a certain distance. After the proton beam bombardment, part of the protons p undergo a nuclear reaction with the action layer 110 to produce neutrons n; another part of the protons p do not undergo a nuclear reaction with the action layer 110, and are decelerated to zero when penetrating the functional component 100 and the hydrogen storage layer 210, and are finally deposited in the hydrogen storage layer 210 in the interception component 200. The heat generated in the functional component 100, that is, the first part of the heat Q1, is converted from the kinetic energy loss of the protons p that do not undergo a nuclear reaction penetrating the action layer 110 and the bearing layer 120; the heat generated in the interception component 200, that is, the second part of the heat Q2, is converted from the kinetic energy loss of the protons p that do not undergo a nuclear reaction and are decelerated to zero in the hydrogen storage layer 210. The nuclear reaction that occurs when the proton p bombards the action layer 110 (when the action layer 110 is made of metallic lithium or lithium alloy) is an endothermic reaction, so the first part of the heat Q1 generated by the functional component 100 can be dissipated through multiple channels such as nuclear reaction heat absorption, precooling of the functional component 100 to improve the heat absorption capacity, and cooling and heat dissipation of the functional component 100. Compared with conventional neutron targets, there are more heat dissipation channels and high heat dissipation efficiency. On the other hand, the first part of the heat Q1 can be reduced by reducing the thickness of the bearing layer 120. The second part of the heat Q2 generated by the proton p that has not undergone a nuclear reaction in the interception component 200 is dissipated by the heat dissipation layer 220 through the cooling liquid in the cooling channel 230. The conventional neutron target heat dissipation layer 220 (i.e., the target material back plate 121) needs to dissipate the total heat Q generated by the proton beam bombardment, while the distributed neutron target heat dissipation layer 220 of the present invention only needs to dissipate the second part of the heat Q2 generated in the hydrogen storage layer 210, which greatly reduces the burden of the heat dissipation layer 220 and improves the heat dissipation efficiency of the heat dissipation layer 220. As a specific embodiment of the present invention, the interception assembly 200 is designed in a disc or ring shape, and the heat dissipation area is dozens of times larger than that of conventional targets; and the heat dissipation layer 220 in the present invention can rotate together with the interception assembly 200, which is equivalent to intermittent heat dissipation, and has higher heat dissipation efficiency than the continuous heat dissipation method of the heat dissipation layer in the conventional neutron target.

[0060] The distributed neutron target system DnT of the present invention adopts a distributed design for the functional component 100 and the interception component 200, which not only increases the heat dissipation channel of the functional component 100, but also reduces the heat dissipation burden of the interception component 200, which increases the service life of each part. In addition, even if the hydrogen storage layer 210 in the interception component 200 produces blistering defects due to long-term operation, since the functional component 100 and the interception component 200 are not in contact, there will be no impact on the action layer 110 in the functional component 100. Therefore, the distributed neutron target system DnT of the present invention has huge advantages over conventional circular neutron targets CnT and conventional rectangular neutron targets RnT in terms of metal lithium loading of the action layer 110, heat dissipation efficiency of the functional component 100, heat dissipation efficiency of the hydrogen storage layer 210, heat dissipation efficiency of the heat dissipation layer 220, and blistering suppression of the hydrogen storage layer 210, and is a revolutionary design and breakthrough.

[0061] It should be understood that the above description is only a preferred embodiment of the present invention and is not intended to limit the present invention. Any modifications, equivalent substitutions and improvements made within the spirit and principles of the present invention should be included in the protection scope of the present invention.

Claims

1. A distributed BNCT neutron target system with a long life cycle, characterized in that The distributed BNCT neutron target system includes: A functional component, the functional component comprises a continuous strip-shaped active layer and a bearing layer for bearing the active layer, the material of the active layer comprises at least any one of the following materials: metallic lithium, lithium alloy, beryllium, beryllium alloy, and the bearing layer has a width and length not less than that of the active layer; A first reel assembly and a second reel assembly are respectively located at two ends of the functional component, one end of the functional component is mounted on the first reel assembly, and the other end is mounted on the second reel assembly, and a working area is formed between the first reel assembly and the second reel assembly, and the working area includes an incident area of ​​the incident particle beam; A disc-shaped or annular interception component, the interception component is located at the downstream side of the working area and is not in contact with the functional component, the interception component comprises a heat dissipation layer and a hydrogen storage layer arranged in contact with each other, the hydrogen storage layer is arranged opposite to one side of the bearing layer in the functional component, The first reel assembly and the second reel assembly have mutually coordinated reeling and unreeling states. When the first reel assembly is in the unreeling state, the second reel assembly is in the reeling state, and the functional component is transferred from the first reel assembly to the second reel assembly; when the first reel assembly is in the reeling state, the second reel assembly is in the unreeling state, and the functional component is transferred from the second reel assembly to the first reel assembly.

2. The distributed BNCT neutron target system according to claim 1, characterized in that: The thickness of the active layer is 20-300 μm.

3. The distributed BNCT neutron target system according to claim 1, characterized in that: The distance between the functional component and the interception component is 0.1-200 mm.

4. The distributed BNCT neutron target system according to claim 1, characterized in that: The bearing layer is a heat-conducting material, and its material includes at least any one of the following materials: copper, aluminum, iron, graphite or graphene; the thickness of the bearing layer is 2-50 μm.

5. The distributed BNCT neutron target system according to claim 1, characterized in that: The material of the hydrogen storage layer includes at least any one of the following materials: tantalum, palladium, tantalum alloy, palladium alloy, magnesium alloy, titanium alloy; the thickness of the hydrogen storage layer is 10-100 μm.

6. The distributed BNCT neutron target system according to claim 1, characterized in that: The material of the heat dissipation layer includes at least any one of the following materials: copper, copper alloy, aluminum, aluminum alloy, and carbon-based material; and a channel for the flow of cooling liquid is provided in the heat dissipation layer.

7. The distributed BNCT neutron target system according to claim 1, characterized in that: The distributed BNCT neutron target system further includes a cooling component, which is located on at least one side of the working area and is used to cool the functional components in the unwinding state during the working process of the neutron target material.

8. The distributed BNCT neutron target system according to claim 1, characterized in that: The distributed BNCT neutron target system further includes a precooling component, which is used to precool the functional components in a rolled-up state.

9. The distributed BNCT neutron target system according to claim 1, characterized in that: The hydrogen storage layer is arranged in an annular shape on the heat dissipation layer, and the width of the annular hydrogen storage layer is greater than or equal to the diameter of the bombardment range of the incident particle beam.

10. The distributed BNCT neutron target system according to claim 9, characterized in that: The interception assembly is rotatable.

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