A semi-separated BNCT neutron target system with a long life cycle

Abstract

The present invention provides a semi-separated BNCT neutron target system with a long life cycle, the 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; one end of the functional component is mounted on an unwinding component, and the other end is mounted on a rewinding component, and a working area is formed between the unwinding component and the rewinding component, the working area being the incident area of ​​the incident particle line; an interception component, the interception component is located at the downstream side of the working area, and 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, and contacts each other during the operation of the neutron target. The present invention solves the problem that the conventional fixed BNCT neutron target has a short service life, and the active layer separation caused by defects such as bubbling during use leads to the scrapping of the target.

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 semi-separated 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 widespread 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 conventional one-piece neutron target is divided into two parts to solve the problems of target life, heat dissipation and blistering. 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 have not undergone nuclear reaction penetrate the active layer and are intercepted and absorbed by the hydrogen storage layer set in the interception component. When the target is working, the two parts are tightly fitted, which can greatly increase the load of the active layer material without affecting the heat dissipation of the target, thereby greatly improving the service life of the target. In the present invention, the functional component is set as a continuous strip, which not only solves the service life of the target, but also can be cooled or cooled by multiple channels such as pre-cooling the rolled functional component to improve the heat absorption capacity of the functional component, cooling and absorbing heat of the unrolled functional component, and dissipating heat through the heat dissipation layer in the interception component by close contact with the interception component, thereby improving the heat dissipation efficiency of the target.

[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 semi-separated BNCT neutron target system of the present invention has an active layer of a continuous strip, which can be used to move the strip to keep the neutron target at a relatively large neutron yield over a long period of use.

[0011] The present invention aims to provide a semi-separated BNCT neutron target system with a long life cycle, the semi-separated BNCT neutron target system comprising: a functional component, the functional component comprising a continuous strip-shaped action layer and a bearing layer for bearing the action layer, the action layer can react with the incident particle beam to generate a neutron beam, the material of the action layer at least comprises any one of the following materials: metallic lithium, lithium alloy, beryllium, beryllium alloy, the bearing layer has a width and length not less than the action layer; an unwinding component and a winding component respectively located at both ends of the functional component, one end of the functional component is mounted to On the unwinding component, the other end is installed on the winding component, and a working area is formed between the unwinding component and the winding component, and the working area is the incident area of ​​the incident particle line; the intercepting component, the intercepting component can be detachably arranged on the downstream side of the working area in the incident direction of the incident particle line, and has a width and length not less than the working area, the intercepting component includes 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, wherein the functional component and the intercepting component are in contact with each other during the operation of the neutron target.

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

[0013] 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.

[0014] Optionally, the bearing layer has a thickness of 2-50 μm, preferably 3-8 μm.

[0015] 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.

[0016] Optionally, the thickness of the hydrogen storage layer is 10-100 μm, preferably 30-80 μm.

[0017] 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.

[0018] Optionally, a channel for cooling liquid flow is provided in the heat dissipation layer.

[0019] Optionally, the semi-separated 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.

[0020] Optionally, the cooling assembly includes cooling rollers located on both sides of the working area.

[0021] Optionally, the semi-separated 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.

[0022] Optionally, the functional component is continuously transferred from the unwinding component to the winding component. That is, during the neutron target working process, the functional component is slowly moved from the unwinding component to the winding component, and the position of the high-speed proton beam bombardment on the active layer is also slowly changed until the unwinding of the functional component is completed and the target life ends.

[0023] Optionally, the functional component is intermittently transferred from the unwinding component to the winding component. That is, during the operation of the neutron target, the functional component first remains stationary, and when the neutron yield of the active layer in the proton beam bombardment area becomes low, the functional component moves a certain distance from the unwinding component to the winding component, and the distance is greater than the range of proton beam bombardment (working area), which is equivalent to replacing a new neutron target active layer area.

[0024] By adopting the above technical solution, the present invention has the following beneficial effects compared with the prior art:

[0025] 1. Solve the heat dissipation problem of neutron target. The semi-separated design of neutron target can separate the heat into two parts. The first part can dissipate heat efficiently by absorbing heat through nuclear reaction, cooling the functional components to remove heat, pre-cooling the functional components to improve the heat carrying capacity, etc. It can also reduce the heat generation by reducing the thickness of the bearing layer and dissipate heat by close contact with the interception component; the second part is quickly cooled by the heat dissipation layer. The heat dissipation channel is increased, which solves the problem of melting of the action layer caused by heat problems of conventional target materials.

[0026] 2. A continuous strip-shaped 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.

[0027] 3. The semi-separated 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, reducing 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.

[0028] 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

[0029] Figure 1 This is a schematic diagram of a conventional circular neutron target and its proton beam bombardment range;

[0030] Figure 2 It is a schematic diagram of a conventional rectangular neutron target and its proton beam bombardment range;

[0031] Figure 3 This is a schematic diagram of a semi-separated BNCT neutron target system of the present invention;

[0032] Figure 4 It is a front view of the semi-separated BNCT neutron target system of the present invention;

[0033] Figure 5 A top view of a semi-separated BNCT neutron target system of the present invention;

[0034] Figure 6 Schematic diagram of functional components of the semi-separated BNCT neutron target system of the present invention;

[0035] Figure 7 This is a schematic diagram of the working process of a conventional neutron target;

[0036] Figure 8 This is a schematic diagram of the working process of the semi-separated BNCT neutron target system of the present invention.

[0037] Description of the figure number:

[0038] CnT conventional circular neutron target; RnT conventional rectangular neutron target; SnT semi-separated neutron target system; 100 functional component; 110 action layer; 120 bearing layer; 121 target backing plate; 200 interception component; 210 hydrogen storage layer; 220 heat dissipation layer; 230 cooling channel; 310 unwinding component; 320 winding 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

[0039] 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.

[0040] Figure 1 The 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.

[0041] 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.

[0042] refer to Figure 1 , Figure 2 and Figure 7 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.

[0043] refer to Figures 3 to 5 , showing the semi-separated BNCT neutron target system of the present invention. The semi-separated neutron target system SnT 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 unwinding component 310, and the other end is connected to the winding component 320; 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 the interception component 200, and the functional component 100 and the interception component 200 are in non-fixed contact, and maintain close contact when the semi-separated neutron target system SnT is working, and can be separated from each other when not working. When the semi-separated neutron target system SnT is working, the functional component 100 is slowly transferred or intermittently transferred from the unwinding component 310 to the winding component 320.

[0044] refer to Figures 3 to 5As a specific embodiment of the present invention, the semi-separated neutron target system SnT 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 unwinding component 310, and the second precooling component 420 is used to precool the coil of the functional component 100 on the winding 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 heat without melting. As a specific embodiment of the present invention, the semi-separated neutron target system SnT 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 unwinding component 310 and the winding 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 unwinding component 310 and the winding component 320 is avoided, and the functional components 100 after the proton beam bombardment are quickly cooled.

[0045] refer to Figures 3 to 6 During operation of the semi-separated neutron target system SnT 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. When the semi-separated neutron target system SnT functional component 100 of the present invention is moved slowly from the unwinding component 310 to the winding component 320 in a continuous manner, its proton bombardment area is a continuous rectangular area; when the semi-separated neutron target system SnT functional component 100 of the present invention is moved from the unwinding component 310 to the winding component 320 in an intermittent manner, its proton bombardment area presents a plurality of intermittent circular areas distributed along the length direction on the functional layer (when the proton beam bombardment range is circular).

[0046] refer to Figure 1 and Figure 2 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:

[0047]

[0048] 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.

[0049] The functional component in the semi-separated neutron target system SnT 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. When the functional component 100 of the semi-separated neutron target system SnT of the present invention is moved slowly from the unwinding component 310 to the winding component 320 in a continuous manner, the effective area of ​​the active layer 110 that can be bombarded by the proton beam is approximately:

[0050]

[0051] In the above formula, S S It is the effective bombardment area of ​​the active layer 110 in the semi-separated neutron target system of the present invention.

[0052] When the functional component 100 in the semi-separated neutron target system SnT of the present invention moves slowly from the unwinding component 310 to the winding component 320 in a continuous manner, the effective bombardment area S of the active layer 110 in the semi-separated neutron target system SnT S is the effective bombardment area S of the conventional circular neutron target CnT active layer 110 C Or the effective bombardment area S of the conventional rectangular neutron target RnT active layer 110 R The multiples of are:

[0053]

[0054] When the SnT functional component 100 of the semi-separated neutron target system of the present invention moves from the unwinding component 310 to the winding component 320 in an intermittent manner, assuming that the distance of each intermittent movement is 150 mm, the effective area of ​​the active layer 110 that can be bombarded by the proton beam is approximately:

[0055]

[0056] In the above formula, S S It is the effective bombardment area of ​​the active layer 110 in the semi-separated neutron target system of the present invention.

[0057] It can be seen from the above formula that when the semi-separated neutron target system SnT functional component 100 of the present invention moves from the unwinding component 310 to the winding component 320 in an intermittent manner, the effective bombardment area of ​​the active layer 110 of the semi-separated neutron target system SnT of the present invention can reach more than 6600 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 semi-separated neutron target system SnT 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 7 Schematic diagram of the working process of a conventional circular neutron target CnT or a conventional rectangular neutron target RnT. Figure 7 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 blistering 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 Figure 8The figure is a schematic diagram of the working process of the semi-separated neutron target system SnT of the present invention. The functional component 100 composed of the action layer 110 and the bearing layer 120 contacts the interception component 200 composed of the hydrogen storage layer 210 and the heat dissipation layer 220. After the proton beam bombardment, part of the protons p undergo nuclear reaction with the action layer 110 to produce neutrons n; another part of the protons p do not undergo 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 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 nuclear reaction decelerated to zero in the hydrogen storage layer 210. The nuclear reaction that occurs when protons p bombard 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, cooling and heat dissipation of the functional component 100, and heat conduction and heat dissipation through the interception component 200. 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 carrier layer 120. The second part of the heat Q2 generated by the protons p that have not undergone 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 heat dissipation layer 220 in the semi-separated neutron target system SnT of the present invention only needs to dissipate a small part of the second part of the heat Q2 generated in the hydrogen storage layer 210 and the first part of the heat Q1 generated in the functional component 100, which greatly reduces the burden on the heat dissipation layer 220 and improves the heat dissipation efficiency of the heat dissipation layer 220.

[0060] The semi-separated neutron target system SnT of the present invention adopts a semi-separated 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 layer 110 in the functional component 100 and the interception component 200 are separated by the bearing layer 120 in the functional component 100, the functional layer 110 and the hydrogen storage layer 210 that is prone to defects are not in direct contact, so there will be no impact on the functional layer 110 in the functional component 100. Therefore, the semi-separated neutron target system SnT of the present invention has huge advantages over the conventional circular neutron target CnT and the conventional rectangular neutron target RnT in many aspects such as the metal lithium loading of the active layer 110, the heat dissipation efficiency of the functional component 100, the heat dissipation efficiency of the hydrogen storage layer 210, the heat dissipation efficiency of the heat dissipation layer 220, and the bubbling suppression of the hydrogen storage layer 210. It 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 semi-separated BNCT neutron target system with a long life cycle, characterized in that The semi-separated BNCT neutron target system comprises: A functional component, the functional component comprises a continuous strip-shaped active layer and a supporting layer for supporting the active layer, the active layer can react with an incident particle beam to generate a neutron beam, the material of the active layer comprises at least any one of the following materials: metallic lithium, lithium alloy, beryllium, beryllium alloy, and the supporting layer has a width and length not less than that of the active layer; An unwinding assembly and a rewinding assembly are respectively located at two ends of the functional assembly, one end of the functional assembly is mounted on the unwinding assembly, and the other end is mounted on the rewinding assembly, and a working area is formed between the unwinding assembly and the rewinding assembly, and the working area is the incident area of ​​the incident particle beam; An interception component, which is detachably arranged at the downstream side of the working area in the incident direction of the incident particle beam, has a width and a length not less than that of the working area, and comprises a hydrogen storage layer and a heat dissipation layer 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; Wherein, during the operation of the neutron target, the functional component and the interception component are in contact with each other.

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

3. The semi-separated 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.

4. The semi-separated 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.

5. The semi-separated 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.

6. The semi-separated BNCT neutron target system according to claim 1, characterized in that: The semi-separated 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.

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

8. The semi-separated BNCT neutron target system according to claim 1, characterized in that: The functional components are continuously transferred from the unwinding component to the rewinding component.

9. The semi-separated BNCT neutron target system according to claim 1, characterized in that: The functional components are intermittently transferred from the unwinding component to the rewinding component.

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