BNCT neutron target system

Abstract

The utility model provides a BNCT neutron target system, which comprises a continuous band-shaped functional assembly, a continuous band-shaped active layer and a continuous bearing layer, the continuous band-shaped functional assembly comprises a continuous or intermittent band-shaped active layer and the continuous bearing layer is used for bearing the active layer, and the continuous band-shaped active layer comprises a continuous band-shaped active layer and a continuous band-shaped active layer. One end of the functional assembly is mounted on the unwinding assembly, the other end of the functional assembly is mounted on the winding assembly, and a working area is formed between the unwinding assembly and the winding assembly; the intercepting assembly has the width and the length which are not smaller than those of the working area, the intercepting assembly comprises a heat dissipation layer and a hydrogen storage layer which are arranged in a mutual contact mode, and the hydrogen storage layer is arranged opposite to one side of the bearing layer in the functional assembly and makes contact with the bearing layer in a non-fixed mode. The utility model solves the problems that the service life of the conventional fixed BNCT neutron target material is short, and the target material is scrapped due to the separation of an action layer caused by the defects of bubbling and the like in the use process.

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 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. 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 the accelerator boron neutron capture therapy, the proton beam is accelerated by the accelerator, the proton beam is accelerated to an energy sufficient to overcome the Coulomb repulsion of the target nucleus, and a nuclear reaction occurs with the target to generate neutrons, so that the target will be bombarded by the accelerated proton beam with very high energy level in the process of generating neutrons, a small amount of protons and neutrons in the target occur nuclear reaction to generate neutrons, and a large number of high-speed protons gradually decelerate in the neutron target until the speed is zero and then deposited in the neutron target. The energy of the high-speed protons is absorbed by the neutron target, which causes the temperature of the target to rise sharply, and the metal part of the target is prone to blistering, thereby affecting the service life of the target.

[0005] Patent No. 201911264901.0 discloses a target for a neutron line generating device. Patent No. 202210824444.1 discloses a target for a particle beam generating device. The above patents all use the conventional fixed target method, which prolongs the service life of the target to a certain extent by arranging different heat dissipation layers and anti-bubbling layers. Patent No. 202210788155.0 discloses a lithium target for BNCT, which attempts to solve the problems of neutron target heating and blistering by setting an anisotropic carbon substrate, but its technical solution has certain problems: when no intermediate metal is set, the passing protons cannot be captured; when the intermediate metal is set, the passing protons are captured by the intermediate metal, which is equivalent to the heat generated by the proton bombardment of the lithium target and the intermediate metal layer being conducted through the anisotropic carbon substrate and then being dissipated; the heat dissipation of the anisotropic carbon substrate is longer, and the heat conduction distance is shorter than that without the anisotropic carbon substrate, and the path is shorter.

[0006] The above technical solutions have solved the problems of neutron target heat dissipation and blistering to a certain extent, but the existing solutions all use the fixed target method, and the material load of the active layer 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 very low neutron yield, so this type of neutron target has a short service life due to the small load of the active layer material. In addition, the neutron target is radioactive after being bombarded by neutrons due to nuclear reaction or activation, which has a certain degree of pollution and is inconvenient to replace.

[0007] Therefore, it is necessary to propose a new technical solution to solve the above problems. Practical new type content

[0008] The utility model aims at overcoming the deficiency of prior art, provides a long service life BNCT neutron target system.

[0009] To solve the above technical problems, the utility model adopts the basic idea of technical scheme as follows: (1) through the way of changing the action layer material into continuous or intermittent strip material, the service life of the neutron target is greatly improved. (2) through separating the conventional integrated neutron target material into two parts, the service life, heat dissipation and blistering problem of the target material are solved. One part of the proton bombardment action layer material produces neutrons, and the functional assembly containing the action layer and the bearing layer is designed; another part of the most high-speed protons that do not occur nuclear reaction penetrates the action layer and is intercepted and absorbed by the hydrogen storage layer arranged in the interception assembly. The two parts are closely attached during the work of the target material, which can greatly improve the load of the action layer material and the service life of the target material without affecting the heat dissipation of the target material. In the utility model, the functional assembly is arranged as a continuous strip material, which not only solves the service life problem of the target material, but also improves the heat absorption capacity of the functional assembly through precooling of the roll-shaped functional assembly, cools and absorbs heat of the functional assembly after unwinding, cools through various channels such as the heat dissipation layer in the interception assembly, and improves the heat dissipation efficiency of the target material.

[0010] One key parameter of the BNCT neutron target is 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 the treatment effect with the increase of the use time. The functional assembly of the semi-separation type BNCT neutron target system of the utility model is a continuous strip material, which can keep the neutron target at a relatively large neutron yield during a long use cycle by moving the strip material.

[0011] Specifically, the utility model provides a kind of BNCT neutron target system, the BNCT neutron target system includes: continuous strip functional assembly, the functional assembly includes continuous or intermittent strip action layer and the continuous bearing layer for bearing the action layer, the bearing layer has not less than the width and length of action layer;Respectively located at the both ends of functional assembly and unwinding assembly and winding assembly, one end of the functional assembly is installed to unwinding assembly, the other end is installed to winding assembly, and working area is formed between unwinding assembly and winding assembly, in the case where the functional assembly includes intermittent action layer, the working area does not exceed one action layer area in intermittent action layer;Interception assembly has not less than the width and length of the working area, the interception assembly includes 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 assembly and is in contact with the bearing layer in a non-fixed manner.

[0012] In the utility model, the neutron line is generated by the action of the action layer and the incident particle line, and the working area is the incident area of the incident particle line.

[0013] The hydrogen storage layer of the intercepting assembly and the bearing layer of the functional assembly are in non-fixed contact, that is, the contact between the two is not permanent, for example, when the neutron target system is working (the functional assembly is bombarded by the incident particle line), the hydrogen storage layer and the bearing layer are in close contact, and when the neutron target system is not working (the incident particle line does not bombard the functional assembly), the hydrogen storage layer of the intercepting assembly and the bearing layer of the functional assembly can be separated from each other.

[0014] Optionally, the material of the action layer at least contains any one of the following materials: metallic lithium, lithium alloy, beryllium, beryllium alloy.

[0015] Optionally, the thickness of the action layer is 20-300 μm, preferably 100-200 μm.

[0016] Optionally, the bearing layer is a material with good heat conduction performance, and the material at least contains any 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 at least contains any 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 at least contains any one of the following materials: copper, copper alloy, aluminum, aluminum alloy, carbon-based material.

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

[0022] Optionally, the semi-separable BNCT neutron target system further comprises a pre-cooling assembly for pre-cooling the functional assembly in the rolled state.

[0023] Optionally, the semi-separable BNCT neutron target system further comprises a cooling assembly located on at least one side of the working area for cooling the functional assembly in the unwound state during the working process of the neutron target material.

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

[0025] Optionally, when the functional assembly comprises intermittent action layers, the cooling assembly is located at the interval of the intermittent action layers.

[0026] Optionally, when the functional assembly comprises continuous action layers, the functional assembly can be continuously or intermittently transferred from the unwinding assembly to the winding assembly. When continuously transferred, the functional assembly is always slowly moved from the unwinding assembly to the winding assembly in the neutron target working process, and the position of the high-speed proton beam hitting on the action layer is also slowly changed until the functional assembly is completely unwound and the target life ends. When intermittently transferred, the functional assembly is first kept stationary in the neutron target working process, and then moved a certain distance from the unwinding assembly to the winding assembly when the neutron yield of the action layer in the proton beam hitting area is low, the distance being greater than the range (working area) of the proton beam hitting, which is equivalent to replacing a new neutron target action layer area.

[0027] Optionally, when the functional assembly comprises intermittent action layers, the functional assembly is intermittently transferred from the unwinding assembly to the winding assembly, and the distance of each transfer is the length of one action layer of the intermittent action layers plus the length of the interval.

[0028] By adopting the technical scheme, the utility model has the following beneficial effects compared with the prior art:

[0029] 1. The heat dissipation problem of the neutron target is solved, and the heat is organically separated into two parts through the semi-separation design of the neutron target. The first part is efficiently cooled through nuclear reaction heat absorption, cooling of the functional assembly, pre-cooling of the functional assembly to improve the heat carrying capacity, and other ways, and can also be cooled through reducing the thickness of the bearing layer to reduce the heat generation and through close contact with the interception assembly. The second part is quickly cooled through the heat dissipation layer. The heat dissipation channel is increased, and the problems such as melting of the action layer caused by the heat problem of the conventional target material are solved.

[0030] 2. The continuous or intermittent strip-shaped action layer is designed, which greatly improves the carrying capacity of the action layer material of the neutron target system and greatly improves the service life of the neutron target.

[0031] 3. The semi-separation type BNCT neutron target system is innovatively designed, which separates the part prone to foaming and deformation of the conventional target material from the part generating neutrons in nuclear reaction, thereby reducing the influence of foaming, deformation and other defects on the action layer. The influence of the defects such as foaming and deformation of the action layer is fundamentally solved.

[0032] The specific implementation manner of the utility model will be further described in detail below with reference to the drawings. BRIEF DESCRIPTION OF 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 semi-separated BNCT neutron target system of the present invention;

[0036] Figure 4 for Figure 3 A front view of the BNCT neutron target system is shown;

[0037] Figure 5 for Figure 3 A top view of the BNCT neutron target system is shown;

[0038] Figure 6 A schematic diagram of the functional components of the semi-separated BNCT neutron target system of the present invention;

[0039] Figure 7 This is a schematic diagram of the working process of a conventional neutron target;

[0040] Figure 8 This is a schematic diagram of the working process of the semi-separated BNCT neutron target system of the present invention.

[0041] Description of the figure number:

[0042] CnT Conventional Circular Neutron Target

[0043] RnT conventional rectangular neutron target

[0044] SnT semi-separated neutron target system

[0045] 100 functional components

[0046] 110 active layer

[0047] 120 bearing layer

[0048] 121 target backing plate

[0049] 200 Interception Component

[0050] 210 Hydrogen Storage Layer

[0051] 220 heat dissipation layer

[0052] 230 cooling channels

[0053] 310 Unwinding Component

[0054] 320 Winding Components

[0055] 410 First pre-cooling component

[0056] 420 Second pre-cooling component

[0057] 510 first cooling component

[0058] 520 Second Cooling Assembly

[0059] p proton

[0060] neutron

[0061] Q1 First part of heat

[0062] Q2 Second part of heat

[0063] Q is the total heat generated by the proton beam bombardment. DETAILED DESCRIPTION

[0064] 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.

[0065] 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.

[0066] 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.

[0067] refer to Figure 1 、 Figure 2 and Figure 7 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.

[0068] Reference Figures 3 to 5 , shows the semi-separation type BNCT neutron target system of the utility model. The semi-separation type neutron target system SnT is mainly composed of functional assembly 100 and intercept assembly 200. Functional assembly 100 is continuous strip and is in the form of roll, one end is connected to unwinding assembly 310, the other end is connected to winding assembly 320;Intercept assembly 200 is composed of hydrogen storage layer 210 and heat dissipation layer 220. Functional assembly 100 is located above intercept assembly 200, and the contact between functional assembly 100 and intercept assembly 200 is non-fixed type, which keeps close contact when the semi-separation type neutron target system SnT works, and can be separated from each other when not working. When the semi-separation type neutron target system SnT works, functional assembly 100 is slowly transferred or intermittently transferred from unwinding assembly 310 to winding assembly 320.

[0069] Reference Figures 3 to 5 , as a specific embodiment of the utility model, the semi-separation type neutron target system SnT further includes first pre-cooling assembly 410 and second pre-cooling assembly 420, wherein the first pre-cooling assembly 410 is used for pre-cooling the roll material of functional assembly 100 on unwinding assembly 310, and the second pre-cooling assembly 420 is used for pre-cooling the roll material of functional assembly 100 on winding assembly 320. By pre-cooling functional assembly 100, the temperature of functional assembly 100 can be greatly reduced, so that it can absorb more heat without melting. As a specific embodiment of the utility model, the semi-separation type neutron target system SnT can further 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, which not only isolates the part of functional assembly 100 bombarded by proton beam from the roll-shaped functional assembly 100 on unwinding assembly 310 and winding assembly 320, but also cools the functional assembly 100 during unwinding and winding;That is to say, it not only avoids the influence of proton beam bombardment on the roll-shaped functional assembly 100 on unwinding assembly 310 and winding assembly 320, but also quickly cools the functional assembly 100 after proton beam bombardment.

[0070] Reference Figures 3 to 6 , one of the functional assemblies 100 in the semi-separation type neutron target system SnT of the utility model is composed of continuous functional layer 110 and bearing layer 120 and is continuous roll-shaped strip. When the functional assembly 100 of the semi-separation type neutron target system SnT of the utility model moves slowly from unwinding assembly 310 to winding assembly 320 in continuous mode, its proton bombardment area is a continuous rectangular area. When the functional assembly 100 of the semi-separation type neutron target system SnT of the utility model moves from unwinding assembly 310 to winding assembly 320 in intermittent mode, its proton bombardment area presents multiple intermittent circular areas on the functional layer along the length direction (when the proton beam bombardment range is circular).

[0071] Reference Figure 1 and Figure 2 , assuming that the proton beam hits a range of φ100mm of a circle, the effective hit area of the action layer 110 of the conventional circular neutron target CnT and the conventional rectangular neutron target RnT is:

[0072]

[0073] 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.

[0074] The functional assembly in the semi-separable neutron target system SnT 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. When the functional assembly 100 of the semi-separable neutron target system SnT in the utility model moves slowly from the unwinding assembly 310 to the winding assembly 320 in a continuous manner, the effective area of the action layer 110 that can be hit by the proton beam is about:

[0075]

[0076] In the above formula, S S is the effective hit area of the action layer 110 in the semi-separable neutron target system in the utility model.

[0077] When the functional assembly 100 in the semi-separable neutron target system SnT in the utility model moves slowly from the unwinding assembly 310 to the winding assembly 320 in a continuous manner, the effective hit area S S of the action layer 110 in the semi-separable neutron target system SnT 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, and is:

[0078]

[0079] When the functional assembly 100 of the semi-separable neutron target system SnT in the utility model moves from the unwinding assembly 310 to the winding assembly 320 in an intermittent manner, assuming that the intermittent moving distance each time is 150mm, the effective area of the action layer 110 that can be hit by the proton beam is about:

[0080]

[0081] In the above formula, SS The effective bombardment area of the action layer 110 of the semi-separation type neutron target system.

[0082] As can be seen from the above formula, when the semi-separation type neutron target system SnT functional assembly 100 of the utility model moves from the unwinding assembly 310 to the winding assembly 320 in an intermittent manner, the effective bombardment area of the action layer 110 of the semi-separation type neutron target system SnT of the utility model can reach more than 6600 times of the effective bombardment area of the conventional circular neutron target CnT and the conventional rectangular neutron target RnT. For the intermittent action layer, the effective bombardment area is similar when it moves in an intermittent manner.

[0083] It can be seen that, under the condition that the proton beam bombardment energy and the thickness of the action layer 110 and other parameters are the same, the semi-separation type neutron target system SnT 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.

[0084] Reference Figure 7 The working process schematic diagram of the conventional circular neutron target CnT or the conventional rectangular neutron target RnT. Figure 7 The improved neutron target after the hydrogen storage layer 210 is added to the conventional circular neutron target CnT or the conventional rectangular neutron target RnT. After proton beam bombardment, part of the protons p and the action layer 110 have nuclear reactions to produce neutrons n; another part of the protons p and the action layer 110 do not have nuclear reactions, 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 generation of this type of 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 especially 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 dissipate heat, increasing the conduction path and the relatively low heat dissipation efficiency. After a long time of work, the hydrogen storage layer 210 inevitably has defects such as blistering to a certain extent, which will also directly cause the action layer 110 to deform or even peel off from the hydrogen storage layer 210, thereby causing the neutron target to be scrapped.

[0085] Reference Figure 8The working process schematic diagram of the semi-separation type neutron target system SnT of the utility model. The functional assembly 100 composed of the action layer 110 and the bearing layer 120 contacts the intercepting assembly 200 composed of the hydrogen storage layer 210 and the heat dissipation layer 220. After proton beam bombardment, part of the proton p and the action layer 110 occur nuclear reaction to produce neutron n; another part of the proton p and the action layer 110 do not occur nuclear reaction, slow down to zero when penetrating the functional assembly 100 and the hydrogen storage layer 210, and finally deposit in the hydrogen storage layer 210 in the intercepting assembly 200. The heat production in the functional assembly 100, namely the first part of heat Q1, is the kinetic energy loss of the proton p that does not occur nuclear reaction penetrating the action layer 110 and the bearing layer 120 to produce conversion; the heat production in the intercepting assembly 200, namely the second part of heat Q2, is the kinetic energy loss conversion of the proton p that does not occur nuclear reaction slowing down to zero in the hydrogen storage layer 210. The nuclear reaction that occurs when the proton p bombards the action layer 110 (when the material of the action layer 110 is metallic lithium or lithium alloy) is an endothermic reaction, so the first part of heat Q1 generated by the functional assembly 100 can be cooled by nuclear reaction, the heat absorption capacity of the pre-cooling of the functional assembly 100, the cooling and heat dissipation of the functional assembly 100, and the heat conduction and heat dissipation of the intercepting assembly 200, compared with the conventional neutron target heat dissipation approach, the heat dissipation efficiency is high. And on the other hand, the thickness of the bearing layer 120 can be reduced to make the first part of heat Q1 smaller. The second part of heat Q2 generated by the proton p that does not occur nuclear reaction in the intercepting assembly 200 is cooled by the heat dissipation layer 220 through the cooling liquid in the cooling channel 230. The heat dissipation layer 220 (namely the target material back plate 121) of the conventional neutron target needs to dissipate the total heat Q generated by the proton beam bombardment, and the heat dissipation layer 220 of the semi-separation type neutron target SnT of the utility model only needs to dissipate the second part of heat Q2 generated in the hydrogen storage layer 210 and a small part of the first part of heat Q1 generated in the functional assembly 100, greatly reducing the burden of the heat dissipation layer 220 and improving the heat dissipation efficiency of the heat dissipation layer 220.

[0086] The semi-separation type neutron target system SnT adopts the semi-separation type design for the functional assembly 100 and the interception assembly 200, not only increases the heat dissipation channel of the functional assembly 100, but also reduces the heat dissipation burden of the interception assembly 200, which increases the service life of each part. In addition, even if the hydrogen storage layer 210 in the interception assembly 200 produces a blister defect due to long-time work, since the functional assembly 100 is separated from the hydrogen storage layer 210 in the interception assembly 200 by the bearing layer 120 in the functional assembly 100, the functional layer 110 and the hydrogen storage layer 210 prone to defects do not directly contact, so the functional layer 110 in the functional assembly 100 will not be affected. Therefore, the semi-separation type neutron target system SnT has great advantages in the metal lithium load of the functional 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.

[0087] It should be understood that the above description is only a preferred embodiment of the present application, and is not intended to limit the present application. Any modification, equivalent replacement and improvement within the spirit and principle of the present application shall be included in the protection scope of the present application.

Claims

1. A BNCT neutron target system, characterized by The BNCT neutron target system comprises: a continuous strip-shaped functional assembly comprising continuous or intermittent strip-shaped active layers and a continuous carrier layer for carrying the active layers, the carrier layer having a width and a length not less than those of the active layers; an unwinding assembly and a winding assembly respectively located at two ends of the functional assembly, one end of the functional assembly being mounted to the unwinding assembly and the other end being mounted to the winding assembly, and a working area being formed between the unwinding assembly and the winding assembly, in the case where the functional assembly comprises intermittent active layers, the working area not exceeding an area of one of the intermittent active layers; an intercepting assembly having a width and a length not less than those of the working area, the intercepting assembly comprising a hydrogen storage layer and a heat dissipation layer arranged in contact with each other, the hydrogen storage layer being arranged opposite to one side of the carrier layer in the functional assembly and in non-fixed contact with the carrier layer.

2. The BNCT neutron target system of claim 1, wherein: The thickness of the active layer is 20-300 μm.

3. The BNCT neutron target system of claim 1, wherein: The thickness of the carrier layer is 2-50 μm.

4. The BNCT neutron target system of claim 1, wherein: The thickness of the hydrogen storage layer is 10-100 μm.

5. The BNCT neutron target system of claim 1, wherein: Channels for the flow of cooling liquid are arranged in the heat dissipation layer.

6. The BNCT neutron target system of claim 1, wherein: The BNCT neutron target system further comprises a pre-cooling assembly for pre-cooling the functional assembly in the wound state.

7. The BNCT neutron target system of claim 1, wherein: The BNCT neutron target system further comprises a cooling assembly located at least one side of the working area for cooling the functional assembly in the unwound state.

8. The BNCT neutron target system of claim 7, wherein: The functional assembly comprises intermittent active layers, and the cooling assembly is located at intervals of the intermittent active layers.

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