Split type BNCT neutron target system

Abstract

The utility model provides a split type BNCT neutron target system, the BNCT neutron target system comprises a function assembly and an interception assembly which are separated from each other, the function assembly comprises a continuous band-shaped action layer and a bearing layer used for bearing the action layer, and the width and the length of the bearing layer are not less than those of the action layer; one end of the functional assembly is mounted on the first winding and unwinding assembly, the other end of the functional assembly is mounted on the second winding and unwinding assembly, and a working area is formed between the first winding and unwinding assembly and the second winding and unwinding assembly; the interception assembly comprises a heat dissipation layer and a hydrogen storage layer which are arranged in a mutual contact mode, and the hydrogen storage layer and one side of the bearing layer of the functional assembly are oppositely arranged and do not make contact with each other. According to the utility model, the problem that the target material is scrapped due to the defects of short service life of the target material, bubbling in the use process and the like in the conventional fixed BNCT neutron target is solved.

Description

Technical Field

[0001] The utility model relates to the technical field of boron neutron capture therapy (BNCT for short), and in particular to a split 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. The neutrons react with boron-10 ( 10 B) The property of nuclear reactions, by selectively delivering boron compounds to cancer cells and irradiating these cells with neutron beams, triggering nuclear reactions and releasing high-energy particles that can damage the DNA of cancer cells, leading to cancer cell death.

[0003] Neutron target is a key component of BNCT equipment, which is used to generate neutron beam for cancer treatment. The selection and design of neutron target is crucial to the efficacy and safety of BNCT. Neutron target is 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 Reaction B, 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, and 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 attracted wide attention.

[0004] In accelerator boron neutron capture therapy, a proton beam is accelerated by an accelerator to an energy sufficient to overcome the Coulomb repulsion of the target nuclei, reacting with the target to produce neutrons. During this neutron production process, the target is bombarded by the very high-energy accelerated proton beam. A small number of protons react with the neutron target to produce neutrons, while a large number of high-speed protons gradually slow down within the neutron target until their speed reaches zero, where they are deposited. The energy of the high-speed protons is absorbed by the neutron target, causing the target material to heat up significantly and causing blistering in the metal portion of the target, which can affect its service life.

[0005] Patent application number 201911264901.0 discloses a target material for a neutron beam generator. Patent application number 202210824444.1 discloses a target material for a particle beam generator. Both of these patents employ conventional fixed targets, extending the target's service life to a certain extent by arranging various heat dissipation and anti-foaming layers. Patent application number 202210788155.0 discloses a lithium target for BNCT. This solution attempts to address the issues of neutron target heating and blistering by incorporating an anisotropic carbon substrate. However, this technical solution presents certain issues: without an intermediate metal, the protons passing through the target cannot be captured. With an intermediate metal, the protons passing through the intermediate metal are captured, effectively dissipating the heat from the protons bombarding the lithium target and the intermediate metal layer through conduction through the anisotropic carbon substrate. This additional heat dissipation process, coupled with the anisotropic carbon substrate, is actually inferior to the heat dissipation method without an anisotropic carbon substrate, which directly conducts heat through the intermediate metal layer, resulting in a shorter heat conduction distance and a shorter path.

[0006] While the above technical solutions address the issues of neutron target heat dissipation and blistering to a certain extent, existing solutions all utilize a fixed target, resulting in a relatively small loading of the active layer material used for the nuclear reaction with protons. Once the reaction reaches a certain point, the thickness of the active layer material decreases significantly, resulting in extremely low neutron yield. Consequently, this low loading of active layer material results in a short service life for these neutron targets. Furthermore, after neutron bombardment, the neutron target becomes radioactive due to the nuclear reaction or activation, resulting in a certain degree of contamination and inconvenience in replacement.

[0007] Therefore, it is necessary to propose a new technical solution to solve the above problems. Utility Model Content

[0008] The utility model aims to overcome the deficiencies of the prior art and provide a BNCT neutron target system with a long life cycle.

[0009] To solve the above technical problems, the utility model adopts technical scheme's basic thought as follows: (1) through the way of changing the action layer material into the continuous strip material which can be recycled, the service life of the neutron target is greatly improved. (2) the heat dissipation and blistering problem are solved by separating the process of high-speed proton bombardment target material into two parts. One part of the proton bombardment produces neutrons, and the utility model discloses a functional assembly comprising an action layer and a bearing layer for this part. Another part of the high-speed proton which does not occur nuclear reaction penetrates the functional assembly and is intercepted and absorbed by the hydrogen storage layer arranged in the interception assembly. The first part of the proton bombardment produces neutrons, and the heat of this part is mainly generated by the high-speed proton penetration, and the heat generated by this part can be reduced by reducing the thickness of the action layer and the bearing layer. In addition, the functional assembly can be cooled to avoid excessive temperature rise. On the other hand, the functional assembly can be pre-cooled to improve the heat absorption capacity of the functional assembly. The second part of the heat is generated by the proton bombardment deposition of most of the protons which do not occur nuclear reaction. This part is also the part of the conventional target blistering. The utility model discloses an interception assembly composed of a hydrogen storage layer and a heat dissipation layer for this part. The hydrogen storage layer can store a large number of protons which do not occur nuclear reaction. The heat dissipation layer is closely attached to the hydrogen storage layer. The heat can be quickly removed by the cooling liquid inside the heat dissipation layer to avoid the problem of excessive temperature rise of this part. At the same time, due to the design of the functional assembly and the interception assembly, even if the interception assembly produces defects such as blistering or deformation, it will not affect the normal work of the neutron target system. The service life of the neutron target system is greatly improved.

[0010] One of the key parameters of the BNCT neutron target is the neutron yield. When the action layer material of the neutron target is metal lithium, the energy of the proton beam and the thickness of the action layer have great influence on the neutron yield. Through simulation calculation, it is known that when the energy of the proton beam is 2.2MeV, the thickness of the metal lithium layer is about 50μm, the neutron yield is the largest; when the energy of the proton beam is 2.5MeV, the thickness of the metal lithium layer is about 98μm, the neutron yield is the largest; when the energy of the proton beam is 3MeV, the thickness of the metal lithium layer is about 188μm, the neutron yield is the largest. This also shows that the conventional BNCT neutron target will affect the neutron yield and thus affect the treatment effect with the increase of the use time. The action layer of the split type BNCT neutron target system of the utility model is a continuous strip material which can be recycled, so that the neutron target can always maintain a relatively large neutron yield in a long use cycle.

[0011] Specifically, the utility model provides a kind of split type BNCT neutron target system, the split type BNCT neutron target system includes functional component and intercepting component separated from each other, wherein, the functional component contains continuous strip-shaped active layer and the bearing layer for carrying the active layer, the bearing layer has not less than the width and length of active layer;The one end of the functional component is installed to first take-up and pay-off assembly, the other end is installed to second take-up and pay-off assembly, and working area is formed between first take-up and pay-off assembly and second take-up and pay-off assembly;The take-up and pay-off state of first take-up and pay-off assembly and second take-up and pay-off assembly is opposite, and one is in pay-off state, and the other is in winding state;The intercepting component contains heat dissipation layer and hydrogen storage layer, which are 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 does not contact each other, and the projection of the working area along the normal direction of the hydrogen storage layer is located in the hydrogen storage layer area.

[0012] In the utility model, the active layer and the incident particle line are used to generate neutron line, and the working area is the bombardment range of the incident particle line. From the incident direction of the incident particle line, the active layer, the bearing layer, the hydrogen storage layer and the heat dissipation layer are arranged in sequence. The projection of the working area on the opposite side of the hydrogen storage layer and the bearing layer is the projection of the working area on the hydrogen storage layer according to the incident direction of the incident particle line.

[0013] Optionally, the material of the active layer comprises at least one of the following materials: metallic lithium, lithium alloy, beryllium, beryllium alloy.

[0014] Optionally, the thickness of the active layer is 20-300 μm, preferably 100-200 μm.

[0015] Optionally, the distance between the functional component and the intercepting component is 0.1-200 mm, preferably 1-10 mm.

[0016] Optionally, the bearing layer is a material with good heat conduction performance, and the material comprises at least one of the following materials: copper, aluminum, iron, graphite or carbon-based material such as graphene.

[0017] Optionally, the thickness of the bearing layer is 2-50 μm, preferably 3-8 μm.

[0018] Optionally, the material of the hydrogen storage layer comprises at least one of the following materials: tantalum, palladium, tantalum alloy, palladium alloy, magnesium alloy, titanium alloy.

[0019] Optionally, the thickness of the hydrogen storage layer is 10-100 μm, preferably 30-80 μm.

[0020] Optionally, the material of the heat dissipation layer comprises at least one of the following materials: copper, copper alloy, aluminum, aluminum alloy, carbon-based material.

[0021] Optionally, a channel for cooling liquid flow is provided in the heat dissipation layer.

[0022] Optionally, the split BNCT neutron target system further includes a pre-cooling component, which is used to pre-cool the functional component in the rolled-up state.

[0023] Optionally, the split 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 operation of the neutron target.

[0024] Optionally, the cooling assembly includes cooling rollers located on both sides of the working area.

[0025] Optionally, the interception assembly is disk-shaped or annular, and the hydrogen storage layer is disposed in an annular shape on the heat dissipation layer. When the bombardment range of the incident particle beam on the active layer (i.e., the working range of the active layer) is circular, the annular width of the annular hydrogen storage layer is greater than or equal to the diameter of the bombardment range of the incident particle beam.

[0026] Optionally, the interception assembly is rotatable.

[0027] After adopting the above technical solution, the utility model has the following beneficial effects compared with the prior art:

[0028] 1. Solve the heat dissipation problem of the neutron target. The split design of the neutron target organically divides the heat into two parts. The first part efficiently dissipates heat through nuclear reaction absorption, cooling the functional components to remove heat, and pre-cooling the functional components to improve heat carrying capacity. Heat generation can also be reduced by reducing the thickness of the load-bearing layer. The second part is rapidly cooled by the heat dissipation layer, fundamentally solving the problem of melting the active layer caused by heat in conventional targets.

[0029] 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.

[0030] 3. The innovative design of a split BNCT neutron target system structurally separates the portion of the conventional target material prone to foaming and deformation from the portion that produces neutrons during nuclear reactions, thus preventing the effects of defects such as foaming and deformation on the active layer. This fundamentally solves the problem of defects such as detachment and deformation of the active layer caused by foaming.

[0031] 4. The interceptor layer adopts a disc-shaped or ring-shaped design and can rotate, allowing high-speed protons to bombard different locations, avoiding heat accumulation. Compared with conventional targets, this significantly increases the heat dissipation area, converting the conventional target's continuous bombardment heat generation process into intermittent localized bombardment, and achieving a breakthrough improvement in heat dissipation compared to conventional solutions.

[0032] The specific embodiments of the present invention will be described in further detail below with reference to the accompanying drawings. BRIEF DESCRIPTION OF THE DRAWINGS

[0033] Figure 1 Schematic diagram of a conventional circular neutron target and its proton beam bombardment range;

[0034] Figure 2 Schematic diagram of a conventional rectangular neutron target and its proton beam bombardment range;

[0035] Figure 3 This is a schematic diagram of the split BNCT neutron target system of the utility model;

[0036] Figure 4 This is a top view of the split BNCT neutron target system of the utility model;

[0037] Figure 5 Schematic diagram of the functional components of the split BNCT neutron target system of the present invention;

[0038] Figure 6 A schematic diagram of the effective proton beam bombardment area of ​​the functional components of the present invention;

[0039] Figure 7 Schematic diagram of the interception assembly of the split BNCT neutron target system of the present invention;

[0040] Figure 8 This is a schematic diagram of the working process of a conventional neutron target;

[0041] Figure 9 This is a schematic diagram of the working process of the split BNCT neutron target system of the utility model.

[0042] Description of the figure number:

[0043] CnT conventional circular neutron target; RnT conventional rectangular neutron target; DnT split neutron target system; 100 functional component; 110 action layer; 120 bearing layer; 121 target backing plate; 200 interception assembly; 210 hydrogen storage layer; 220 heat dissipation layer; 230 cooling channel; 310 first reel assembly; 320 second reel assembly; 410 first pre-cooling assembly; 420 second pre-cooling assembly; 510 first cooling assembly; 520 second cooling assembly; p proton; n neutron; Q1 first part of the heat; Q2 second part of the heat; Q total heat generated by the proton beam bombardment. DETAILED DESCRIPTION

[0044] In order to make the purpose, technical solutions and advantages of the present invention more clearly understood, the present invention is further described in detail below with reference to 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 intended to limit the present invention.

[0045] Figure 1 A schematic diagram of a conventional circular neutron target is shown. It primarily consists of a target backing plate 121 and an active layer 110, which fits tightly against the target backing plate 121. A cooling liquid channel is typically located within the target backing plate 121. This liquid flows through the target backing plate 121 at high speeds, removing all heat generated by proton beam bombardment of the conventional circular neutron target CnT. The target backing plate 121 and active layer 110 are typically circular, with the diameter of the active layer 110 slightly larger than the proton beam bombardment range.

[0046] Figure 2 A schematic diagram showing a conventional rectangular neutron target is shown, with Figure 1 The conventional circular neutron target has the same structure, differing only in the external dimensions and the internal channel arrangement of the target backing plate 121. The conventional rectangular neutron target RnT is also composed of a target backing plate 121 and an active layer 110, which is tightly fitted to the target backing plate 121.

[0047] refer to Figure 1 、 Figure 2 and Figure 8 When a proton beam bombards a neutron target, most of the protons that don't undergo a nuclear reaction are deposited on the target backing plate 121, causing blistering defects on the target backing plate 121, which can cause deformation or even shedding of the active layer 110. Therefore, a hydrogen storage layer 210 is typically provided between the target backing plate 121 and the active layer 110 to mitigate the effects of blistering to a certain extent.

[0048] refer to Figure 3 and Figure 4, show the utility model's split type BNCT neutron target system. Split type neutron target system DnT is mainly by functional assembly 100 and intercept assembly 200 constitute. Functional assembly 100 is continuous strip and is in roll shape, one end is connected to first take-up and pay-off assembly 310, the other end is connected to second take-up and pay-off assembly 320;Intercept assembly 200 is disc or annular, and intercept assembly 200 is by hydrogen storage layer 210 and heat dissipation layer 220 constitute;Functional assembly 100 is located the upper side of hydrogen storage layer of intercept assembly 200, and functional assembly 100 and intercept assembly 200 keep small distance but do not contact;Split type neutron target system DnT works, and functional assembly 100 reciprocates between first take-up and pay-off assembly 310 and second take-up and pay-off assembly 320, and intercept assembly 200 can rotate.

[0049] Reference Figures 3 to 7 , as a specific embodiment of the utility model, split type neutron target system DnT still includes first precooling assembly 410 and second precooling assembly 420, wherein first precooling assembly 410 is used to precool the roll stock of functional assembly 100 on first take-up and pay-off assembly 310, and second precooling assembly 420 is used to precool the roll stock of functional assembly 100 on second take-up and pay-off assembly 320. By precooling functional assembly 100, the temperature of functional assembly 100 can be greatly reduced, so that it can absorb more energy without melting. As a specific embodiment of the utility model, split type neutron target system DnT can also include first cooling assembly 510 and second cooling assembly 520. First cooling assembly 510 and second cooling assembly 520 are respectively arranged on both sides of the proton beam bombardment range, not only isolate the part of functional assembly 100 bombarded by proton beam from the roll-shaped functional assembly 100 on first take-up and pay-off assembly 310 and second take-up and pay-off assembly 320, but also cool the functional assembly 100 during unwinding and winding;That is to avoid the influence of proton beam bombardment on the roll-shaped functional assembly 100 on first take-up and pay-off assembly 310 and second take-up and pay-off assembly 320, and to cool the functional assembly 100 after proton beam bombardment quickly.

[0050] Reference Figures 3 to 6 , the functional assembly 100 of the split type neutron target system DnT of the utility model is composed of the active layer 110 and the bearing layer 120 and is continuous roll-shaped strip, and the functional assembly 100 reciprocates between first take-up and pay-off assembly 310 and second take-up and pay-off assembly 320, so its proton bombardment range is a continuous rectangular area as shown in Figure 6 .

[0051] Reference Figure 1 、 Figure 2 and Figure 6, assuming that the proton beam hits a range of a circle of φ100mm, the effective hit area of the action layer 110 of the conventional circular neutron target CnT and the conventional rectangular neutron target RnT is:

[0052]

[0053] In the above formula, S C is the effective hit area of the conventional circular neutron target; S R is the effective hit area of the conventional rectangular neutron target.

[0054] The functional assembly in the split-type neutron target system DnT in the utility model is a continuous coiled strip, the length of which can be set arbitrarily according to needs, assuming that the length of the functional assembly 100 is 1000m, that is, the length of the action layer 110 and the bearing layer 120 is also 1000m. The effective area of the action layer 110 that can be hit by the proton beam is about:

[0055]

[0056] In the above formula, S D is the effective hit area of the action layer 110 in the split-type neutron target system of the utility model.

[0057] When the length of the functional assembly 100 in the utility model is 1000m, the effective hit area S D of the action layer 110 in the split-type neutron target system is a multiple of the effective hit area S C of the action layer 110 of the conventional circular neutron target CnT or the effective hit area S R of the action layer 110 of the conventional rectangular neutron target RnT, that is:

[0058]

[0059] As can be seen from the above formula, the effective hit area of the action layer 110 of the split-type neutron target system DnT of the utility model can reach tens of thousands of times of the effective hit areas of the conventional circular neutron target CnT and the conventional rectangular neutron target RnT. When the parameters such as the proton beam hitting energy and the thickness of the action layer 110 are the same, the split-type neutron target system DnT of the utility model greatly improves the lithium carrying capacity in the action layer 110, thereby greatly improving the service life of the neutron target system.

[0060] Reference Figure 8 is a schematic diagram of the working process of the conventional circular neutron target CnT or the conventional rectangular neutron target RnT. Figure 8The conventional circular neutron target CnT or the conventional rectangular neutron target RnT is an improved neutron target with the hydrogen storage layer 210 added. After the proton beam bombardment, part of the protons p has nuclear reaction with the action layer 110 to generate neutrons n, and the other part of the protons p does not have nuclear reaction with the action layer 110, and is decelerated to zero when penetrating the action layer 110 and the hydrogen storage layer 210, and finally deposited in the hydrogen storage layer 210. Therefore, the heat generated by the proton beam bombardment of the conventional neutron target material 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 backing plate 121 in the conventional neutron target), and the heat in the action layer 110 also needs to be conducted to the heat dissipation layer 220 through the hydrogen storage layer 210 to be dissipated, which increases the conduction path and the heat dissipation efficiency is relatively low. After a long time of work, the hydrogen storage layer 210 inevitably has defects such as blistering to a certain extent, which also directly causes the action layer 110 to deform or even peel off from the hydrogen storage layer 210, thereby causing the neutron target to be scrapped.

[0061] Reference Figure 9This is a schematic diagram of the operating process of the split neutron target system DnT of the present invention. The functional assembly 100, consisting of an active layer 110 and a supporting layer 120, and the interception assembly 200, consisting of a hydrogen storage layer 210 and a heat dissipation layer 220, are separated by a certain distance and do not contact each other. After proton beam bombardment, some protons p undergo nuclear reactions with the active layer 110, producing neutrons n. Other protons p do not undergo nuclear reactions with the active layer 110, but are decelerated to zero upon penetrating the functional assembly 100 and the hydrogen storage layer 210, ultimately depositing within the hydrogen storage layer 210 of the interception assembly 200. The heat generated within the functional assembly 100, or the first portion of heat Q1, is converted from the kinetic energy loss of the non-reactive protons p penetrating the active layer 110 and the supporting layer 120. The heat generated within the interception assembly 200, or the second portion of heat Q2, is converted from the kinetic energy loss of the non-reactive protons p decelerating to zero within the hydrogen storage layer 210. The nuclear reaction that occurs when protons p bombard the active layer 110 (when the active layer 110 is made of metallic lithium or a lithium alloy) is endothermic. Therefore, the first portion of heat Q1 generated by the functional assembly 100 can be dissipated through multiple channels, including nuclear reaction absorption, pre-cooling of the functional assembly 100 to enhance its heat absorption capacity, and cooling and dissipation of the functional assembly 100. This provides more dissipation pathways and higher dissipation efficiency than conventional neutron targets. Furthermore, the first portion of heat Q1 can be reduced by reducing the thickness of the carrier layer 120. The second portion of heat Q2 generated by protons p that do not undergo a nuclear reaction in the interceptor assembly 200 is dissipated by the heat dissipation layer 220 via the cooling liquid within the cooling channels 230. While conventional neutron target heat dissipation layer 220 (i.e., target backing plate 121) must dissipate the total heat Q generated by proton beam bombardment, the split-type neutron target heat dissipation layer 220 of the present invention only needs to dissipate the second portion of heat Q2 generated within the hydrogen storage layer 210, significantly reducing the burden on the heat dissipation layer 220 and improving its heat dissipation efficiency. 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 conventional neutron targets.

[0062] The split type neutron target system DnT adopts split type design for the functional assembly 100 and the intercepting assembly 200, not only increases the heat dissipation channel of the functional assembly 100, but also reduces the heat dissipation burden of the intercepting assembly 200, which increases the service life of each part. In addition, even if the hydrogen storage layer 210 in the intercepting assembly 200 produces a blister defect due to long-time work, since the functional assembly 100 and the intercepting assembly 200 are not in contact, the functional assembly 100 will not be affected. Therefore, the split type neutron target system DnT has great advantages in the metal lithium load of the active layer 110, the heat dissipation efficiency of the functional assembly 100, the heat dissipation efficiency of the hydrogen storage layer 210, the heat dissipation efficiency of the heat dissipation layer 220, the blister suppression of the hydrogen storage layer 210 and the like compared with the conventional circular neutron target CnT and the conventional rectangular neutron target RnT, and is a revolutionary design and breakthrough.

[0063] It should be understood that the above description is only a preferred embodiment of the utility model, and is not used to limit the utility model, and any modification, equivalent replacement and improvement within the spirit and principle of the utility model should be included in the protection scope of the utility model.

Claims

1. A split BNCT neutron target system, characterized in that The split BNCT neutron target system includes a functional component and an interception component that are separated from each other. Wherein, the functional component comprises a continuous strip-shaped active layer and a bearing layer for bearing the active layer, wherein the bearing layer has a width and a length not less than that of the active layer; One end of the functional component is mounted on the first retractable reel assembly, and the other end is mounted on the second retractable reel assembly, and a working area is formed between the first retractable reel assembly and the second retractable reel assembly; the retractable and unretractable states of the first retractable reel assembly and the second retractable reel assembly are opposite, and when one is in the unreeling state, the other is in the reeling state; The interception 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 supporting layer in the functional component and does not contact each other, wherein the projection of the working area along the normal direction of the hydrogen storage layer is located within the hydrogen storage layer area.

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

3. The split-type 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 split BNCT neutron target system according to claim 1, characterized in that: The thickness of the bearing layer is 2-50 μm.

5. The split BNCT neutron target system according to claim 1, characterized in that: The thickness of the hydrogen storage layer is 10-100 μm.

6. The split BNCT neutron target system according to claim 1, characterized in that: The heat dissipation layer is provided with a channel for the flow of cooling liquid.

7. The split-type BNCT neutron target system according to claim 1, characterized in that: The split 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.

8. The split-type BNCT neutron target system according to claim 1, characterized in that: The split BNCT neutron target system further includes a pre-cooling component, which is used to pre-cool the functional component in a rolled-up state.

9. The split-type BNCT neutron target system according to claim 1, characterized in that: The interception component is in the shape of a disk or a ring, and the hydrogen storage layer is arranged in the shape of a ring on the heat dissipation layer.

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

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