Neutron treatment system based on multiple neutron tubes
Through the neutron therapy system with multi-neutron tube combined with regulation module, the problems of large size and insufficient flux of neutron therapy equipment are solved, miniaturization and cost optimization of the equipment are achieved, and the needs of boron neutron capture treatment are met.
Patent Information
- Application Number
- CN202510295577.8
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2025-03-12
- Publication Date
- 2025-07-04
AI Technical Summary
The existing neutron therapy equipment is huge in size and is difficult to meet the ultrathermal neutron flux requirements for boron neutron capture treatment, resulting in limited application and promotion of equipment and high operating costs.
A neutron therapy system based on multi-neutron tubes is adopted to regulate the neutron emitted by the neutron tube through the regulation module, and components such as the slowing reflection layer, fission proliferation layer, slowing absorption layer, thermal neutron absorption layer and gamma absorption layer are used to adjust the neutron energy and flux to meet the requirements of neutron therapy.
Significantly reduce the volume of neutron therapy equipment, ensure that neutron flux meets treatment needs, improves equipment failure tolerance, and reduces construction and operation costs.
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Figure CN120242334A_ABST
Abstract
Description
Technical Field
[0001] The present invention relates to the technical field of neutron therapy, and specifically, to a neutron therapy system based on multiple neutron tubes. Background Art
[0002] Boron neutron capture therapy is a combined therapy for cancer. A drug containing 10 10B is directionally aggregated in tumor cells, and irradiated with an external neutron beam of specific energy. Thermal neutrons and 10 10B atomic nuclei will undergo a nuclear reaction to produce α particles and recoil Li atoms, thereby releasing a large amount of energy in tumor cells to cause local damage, while normal tissue cells are minimally damaged due to the absence of 10 10B or a small content, thus realizing the directional treatment of cancer.
[0003] Currently, the number of 10 10B atoms that can be aggregated in tumor cells is limited. In order to effectively achieve treatment, the treatment site needs to be in a sufficiently high neutron field. That is, according to relevant publications of the IAEA in 2023, the epithermal neutron flux is recommended to be > 5E8 n / cm2 / s. To achieve the treatment effect, current neutron therapy systems mainly use reactors and accelerators as neutron sources. Among them, in order to meet the neutron constant parameters for neutron therapy, a huge reactor or a huge accelerator is required, resulting in a large volume of the entire set of neutron therapy equipment. The existing entire set of neutron therapy equipment is too large, which is not conducive to the application and large-scale popularization of neutron therapy equipment. At the same time, in order to ensure the safety of staff, a huge reactor or a huge accelerator requires a fixed and independent space, and both the construction cost and the operation cost are relatively high.
[0004] In addition, although there are relatively miniaturized neutron sources in the prior art, the epithermal neutron fluxes generated by them are far less than 5E8 n / cm2 / s, making it difficult to be applied to boron neutron capture therapy to achieve the desired treatment effect.
[0005] Therefore, how to miniaturize the neutron therapy equipment applied to boron neutron capture therapy and generate an epithermal neutron flux that can meet the requirements of boron neutron capture therapy is a technical problem that needs to be urgently solved by those skilled in the art. Summary of the Invention
[0006] The present invention aims to at least solve one of the technical problems in the related art to some extent. For this purpose, an embodiment of the present invention provides a neutron therapy system based on multiple neutron tubes. By installing n neutron tubes in a regulation module, the regulation module can regulate the neutrons emitted by the neutron tubes so that the flux and energy of the neutrons meet the requirements of neutron therapy.
[0007] The neutron therapy system based on multiple neutron tubes according to the embodiment of the present invention includes
[0008] n neutron tubes;
[0009] A regulation module, on which there are n mounting blind holes arranged at intervals, the central axes of each of the mounting blind holes intersect at a first point, the first point is spaced from the regulation module, the neutron tubes extend into the mounting blind holes, and the outlets of the neutron tubes abut against the bottom surfaces of the mounting blind holes, the neutron tubes correspond to the mounting blind holes one by one, and the regulation module can regulate the neutrons emitted by the neutron tubes so that the neutron flux and the neutron energy meet the requirements of neutron therapy.
[0010] Optionally, the regulation module includes:
[0011] A moderation reflection layer that can multiply and moderate neutrons;
[0012] A moderation absorption layer, which is arranged on the moderation reflection layer, there is a close contact or a gap between the moderation absorption layer and the moderation reflection layer, the moderation absorption layer is located on the side of the moderation reflection layer close to the first point, the moderation absorption layer is spaced from the first point, the moderation absorption layer can receive the neutrons emitted by the moderation reflection layer and moderate and absorb them, and the central axes of each of the mounting blind holes all pass through the moderation absorption layer;
[0013] Wherein, the mounting blind hole penetrates through the moderation reflection layer, and the bottom surface of the mounting blind hole is coplanar with the surface of the moderation absorption layer adjacent to the moderation reflection layer.
[0014] Optionally, the regulation module further includes:
[0015] A fission multiplication layer, which is arranged between the moderation reflection layer and the moderation absorption layer, there is a close contact or a gap between the fission multiplication layer and the moderation reflection layer, there is a close contact or a gap between the fission multiplication layer and the moderation absorption layer, the fission multiplication layer is spaced from the first point, and the fission multiplication layer can receive the neutrons emitted by the moderation reflection layer and perform fission multiplication on them.
[0016] Optionally, the regulation module further includes:
[0017] A thermal neutron absorption layer, which is arranged on the moderation absorption layer, there is a close contact or a gap between the thermal neutron absorption layer and the moderation absorption layer, the thermal neutron absorption layer is located on the side of the moderation absorption layer close to the first point, the thermal neutron absorption layer is spaced from the first point, the thermal neutron absorption layer can receive the neutrons emitted by the moderation absorption layer and absorb the thermal neutrons, and the central axes of each of the mounting blind holes all pass through the thermal neutron absorption layer.
[0018] Optionally, the regulation module further includes:
[0019] A gamma absorption layer, which is disposed on the thermal neutron absorption layer. There is no gap between the gamma absorption layer and the thermal neutron absorption layer or there is a gap therebetween. The gamma absorption layer is located on the side of the thermal neutron absorption layer close to the first point, and is spaced from the first point. The gamma absorption layer can absorb gamma rays, and the central axes of all the mounting blind holes pass through the gamma absorption layer.
[0020] Optionally, the neutron therapy system based on multiple neutron tubes further includes:
[0021] A collimation layer, which is disposed on the regulation module. There is no gap between the collimation layer and the regulation module or there is a gap therebetween. The collimation layer is located on the side of the regulation module close to the first point, and is spaced from the first point. The central axes of all the mounting blind holes pass through the collimation layer, and collimation holes for collimating neutrons are provided on the collimation layer.
[0022] Optionally, in the direction close to the first point, the aperture of the collimation hole gradually decreases.
[0023] Optionally, the shape of the regulation module is a semi-ellipsoidal shell, where n is greater than or equal to 56; or
[0024] The shape of the regulation module is annular, where n is greater than or equal to 56; or
[0025] The shape of the regulation module is circular, where n is greater than or equal to 100.
[0026] Optionally, the neutron source intensity of the neutron tube is less than or equal to 10 11 .
[0027] Optionally, the material of the regulation module includes:
[0028] A moderation and reflection functional material, which includes one of lead, depleted uranium, bismuth, and beryllium;
[0029] A moderation and absorption functional material, which includes one of magnesium fluoride, aluminum fluoride, and calcium fluoride;
[0030] A fission and proliferation functional material, which includes one of U-235, Pu-239, Th-232, and U-233;
[0031] A thermal neutron absorption functional material, which includes one of cadmium, gadolinium, boron, and lithium;
[0032] Gamma absorption functional material, the gamma absorption functional material including lead or bismuth. Description of the Drawings
[0033] Figure 1 It is a schematic diagram of a neutron therapy system based on multiple neutron tubes according to the first specific embodiment of the present invention.
[0034] Figure 2 It is a schematic diagram of a neutron therapy system based on multiple neutron tubes according to the second specific embodiment of the present invention.
[0035] Figure 3 It is a schematic diagram of a neutron therapy system based on multiple neutron tubes according to the third specific embodiment of the present invention.
[0036] Reference Signs: 1000 - Neutron therapy system based on multiple neutron tubes, 100 - Neutron tube, 200 - Regulation module, 210 - Installation blind hole, 220 - Moderating and reflecting layer, 221 - Circular groove, 230 - Moderating and absorbing layer, 240 - Fission and breeding layer, 250 - Thermal neutron absorption layer, 260 - Gamma absorption layer, 300 - First point, 400 - Collimation layer, 410 - Collimation hole. Detailed Description of the Embodiments
[0037] The embodiments of the present invention will be described in detail below, and the examples of the embodiments are shown in the drawings. The embodiments described below with reference to the drawings are exemplary and are intended to explain the present invention and should not be construed as limiting the present invention.
[0038] The neutron therapy system 1000 based on multiple neutron tubes according to the embodiments of the present invention will be described below with reference to the drawings. As Figures 1 to 3 shown, the neutron therapy system 1000 based on multiple neutron tubes according to the embodiments of the present invention includes n neutron tubes 100 and a regulation module 200.
[0039] The regulation module 200 is provided with n installation blind holes 210 arranged at intervals, the central axes of the respective installation blind holes 210 intersect at a first point 300, the first point 300 is spaced apart from the regulation module 200, the neutron tubes 100 extend into the installation blind holes 210, and the outlets of the neutron tubes 210 abut against the bottom surfaces of the installation blind holes 210. The neutron tubes 100 and the installation blind holes 210 are in one-to-one correspondence, and the regulation module 200 can regulate the neutrons emitted by the neutron tubes 100 so that the flux and energy of the neutrons meet the requirements of neutron therapy.
[0040] According to the neutron therapy system 1000 based on multiple neutron tubes of the present invention, by installing n neutron tubes 100 in the regulation module 200, the regulation module 200 can regulate the neutrons emitted by the neutron tubes 100 so that the neutron flux and neutron energy meet the requirements of neutron therapy. Among them, by using the neutron tubes 100 as the neutron source of the neutron therapy system 1000, the volume of the neutron therapy system 1000 can be greatly reduced. By setting multiple neutron tubes 100, the number, source strength, and position of the neutron tubes 100 can be changed to adapt to different treatment plans. At the same time, it can also prevent the failure of individual neutron tubes 100 from affecting the neutron therapy system 1000, ensuring that the neutron therapy system 1000 can operate normally and making the neutron therapy system 1000 more inclusive of technical failures.
[0041] As Figures 1 to 3 shown, in order to make the technical solution of the present application easier to understand, the technical solution of the present application will be described in more detail below with a specific embodiment of the neutron therapy system 1000 based on multiple neutron tubes.
[0042] In some specific embodiments, the neutron source strength of the neutron tube 100 is less than or equal to 10 11 . Specifically, taking the neutron tube 100 as the neutron source, after the simple acceleration of deuterium ions by the neutron tube 100, and then interacting with the tritium-containing target to generate 14 MeV fast neutrons, it is easy to control the generation of neutrons by controlling deuterium ions. Moreover, the neutron tube 100 usually has a radius of several centimeters and a length of dozens of centimeters, with a small volume. That is, the neutron tube 100 has the advantages of being small and controllable.
[0043] In some specific embodiments, such as Figures 1 to 3As shown, there are n neutron tubes 100, where n is greater than or equal to 50. Specifically, taking the DT neutron tube as an example, for the 14 MeV high-energy neutrons generated by the DT neutron tube, after moderating, energy regulating, and shielding them, and when the beam parameters meet the IAEA (thermal neutron fraction, gamma dose ratio, fast neutron dose ratio) conditions, the epithermal neutron regulation efficiency is 5E-5 to 1E-4. That is, for each neutron generated by the DT neutron tube, 5E-5 to 1E-4 effective epithermal neutrons can be obtained. For the DT neutron tube, the maximum achievable neutron source strength is approximately 1E10 n / s. That is, one neutron tube can obtain a superthermal neutron flux of 5E5 n / cm2 / s. Among them, when considering the use of fissile materials to multiply neutrons, the effective multiplication factor of the fissile materials outside the reactor should be <0.95 to ensure nuclear critical safety. Therefore, the maximum effective multiplication factor of the multiplication system using fissile materials for neutron therapy is 0.95, that is, the neutron multiplication coefficient is 1 / (1-Keff)=20. Therefore, under the condition of fissile material multiplication, one neutron tube can obtain a superthermal neutron flux of 1E7 n / cm2 / s, and using 50 DT neutron sources can meet the requirements of neutron therapy (superthermal neutron flux 5E8 n / cm2 / s).
[0044] In some specific embodiments, as Figures 1 to 3 shown, the regulation module 200 is provided with n mounting blind holes 210 arranged at intervals. The central axes of the respective mounting blind holes 210 intersect at a first point 300. The first point 300 is spaced from the regulation module 200. The neutron tube 100 extends into the mounting blind hole 210, and the outlet of the neutron tube 210 abuts against the bottom surface of the mounting blind hole 210. The neutron tubes 100 and the mounting blind holes 210 are in one-to-one correspondence. The regulation module 200 can regulate the neutrons emitted by the neutron tube 100 so that the flux and energy of the neutrons meet the requirements of neutron therapy. Specifically, the regulation module 200 can regulate the neutrons emitted by the neutron tube 100 to obtain epithermal neutrons that meet the requirements of neutron therapy. In addition, the mounting blind hole 210 penetrates the moderating reflector layer 220, and the bottom surface of the mounting blind hole 210 is coplanar with the surface of the moderating absorber layer 230 adjacent to the moderating reflector layer 220.
[0045] It should be noted that by installing n neutron tubes 100 in the n mounting blind holes 210 of the moderating and regulating module 200, the fast neutrons emitted by the neutron tubes 100 are regulated through the moderating reflector layer 220, the fission multiplication layer 240, the moderating absorber layer 230, the thermal neutron absorber layer 250, the gamma absorber layer 260, and the collimating layer 400 to obtain epithermal neutrons that meet the requirements of neutron therapy.
[0046] In some specific embodiments, as Figures 1 to 3As shown, the n mounting blind holes 210 are arranged in a matrix, that is, the n mounting blind holes 210 are evenly arranged on the regulation module 200 (moderating reflector 100). The central axes of the respective mounting blind holes 210 intersect at a first point 300, which can ensure that the neutrons emitted from the neutron tubes 100 installed in the mounting blind holes 210 are focused on the first point 300, ensuring that the flux of epithermal neutrons meets the requirements of neutron therapy. In addition, the first point 300 is spaced from the regulation module 200 (moderating reflector 100), which can ensure that the neutrons emitted from the neutron tubes 100 are focused outside the regulation module 200 (moderating reflector 100).
[0047] In some specific embodiments, as Figure 1 shown, the regulation module 200 is in the shape of a semi-ellipsoidal shell, where n is greater than or equal to 56.
[0048] In some specific embodiments, as Figure 2 shown, the regulation module 200 is in the shape of a ring, where n is greater than or equal to 56.
[0049] In some specific embodiments, as Figure 3 shown, the regulation module 200 is in the shape of a circle, where n is greater than or equal to 100.
[0050] In some specific embodiments, the material of the regulation module 200 includes a moderating reflector functional material, a moderating absorption functional material, a fission breeding functional material, a thermal neutron absorption functional material, and a gamma absorption functional material. These functional materials are mainly to enable the regulation module 200 to have moderating breeding function, moderating absorption function, fission breeding function, thermal neutron absorption function, and gamma absorption function.
[0051] In some specific embodiments, the moderating reflector functional material includes one of lead, depleted uranium, bismuth, and beryllium.
[0052] In some specific embodiments, the moderating absorption functional material includes one of magnesium fluoride, aluminum fluoride, and calcium fluoride.
[0053] In some specific embodiments, the fission breeding functional material includes one of U-235, Pu-239, Th-232, and U-233.
[0054] In some specific embodiments, the thermal neutron absorption functional material includes one of cadmium, gadolinium, boron, and lithium.
[0055] In some specific embodiments, the gamma absorption functional material includes lead or bismuth.
[0056] In some specific embodiments, as Figures 1 to 3As shown, the moderation reflector layer 220 can reflect and moderate neutrons. Specifically, the moderation reflector layer 220 can reflect and moderate fast neutrons. First, the moderation reflector layer 220 can moderate the fast neutrons in the neutron tube 100, that is, slow down the 14 MeV high-energy neutrons to a few MeV neutrons; second, the moderation reflector layer 220 can reflect neutrons during the process of moderating neutrons, increasing the number of neutrons entering other layers. That is to say, in the moderation reflector layer 220, the high-energy fast neutrons generated by the neutron tube 100 are mainly proliferated and moderated through the (n,2n) reaction, thereby reducing the energy of high-energy neutrons while minimizing the attenuation of the neutron flux. Since the (n,2n) reaction threshold is usually on the order of MeV, the neutron tube 100 is suitable for initially moderating the neutrons generated by the neutron tube 100 and serving as the back-end reflector of the neutron tube 100.
[0057] In some specific embodiments, the moderation reflector layer 220 is one of lead, depleted uranium, bismuth, and beryllium. Specifically, taking lead as an example, the fast neutrons in the neutron tube 100 combine with lead, that is, using the (n,2n) reaction of lead, not only can the fast neutrons be moderated, but also a certain proliferation effect is achieved.
[0058] In some specific embodiments, as Figures 1 to 3 shown, the moderation absorber layer 230 is provided on the moderation reflector layer 220. There is either close contact or a gap between the moderation absorber layer 230 and the moderation reflector layer 220. The moderation absorber layer 230 is located on the side of the moderation reflector layer 220 close to the first point 300, and the moderation absorber layer 230 is spaced from the first point 300, which can ensure that the neutrons emitted from the neutron tube 100 pass through the moderation absorber layer 230 and then gather at the first point 300. The moderation absorber layer 230 can receive the neutrons emitted from the moderation reflector layer 220 and moderate and absorb them. The central axes of the respective mounting blind holes 210 all pass through the moderation absorber layer 230. Specifically, the moderation absorber layer 230 can moderate and absorb the fast neutrons emitted from the moderation reflector layer 220 or the fission proliferation layer 240. That is to say, the fast neutrons emitted from the moderation reflector layer 220 or the fission proliferation layer 240 enter the moderation absorber layer 230, and the fast neutrons will be moderated and absorbed under the action of the moderation absorber layer 230.
[0059] In some specific embodiments, the material of the moderation absorber layer 230 includes one of magnesium fluoride, aluminum fluoride, and calcium fluoride. Specifically, for the fast neutrons emitted from the moderation reflector layer 220 or the fission proliferation layer 240, fluorides such as high-density magnesium fluoride, aluminum fluoride, and calcium fluoride can be used for moderation, that is, using the neutron resonance cross-section of fluorine with materials such as magnesium, aluminum, and calcium in the range of 0.01 MeV to 1 MeV to moderate and absorb the neutrons with energy above 0.01 MeV, thereby achieving neutron regulation for BNCT.
[0060] That is to say, the moderation absorption layer 230 is realized by the resonance cross section of fluorine for neutrons in the 1 MeV range. Due to the existence of the resonance region, the reaction probability of fluorine for neutrons in the fast neutron energy region is much greater than that in the epithermal neutron energy region, thus achieving the maximum efficiency of obtaining epithermal neutrons. However, due to the peaks and valleys in the resonance region of fluorine, the reaction cross section for neutrons of certain energies is small, and epithermal neutrons cannot be effectively obtained. Therefore, fluoride is used, and materials such as aluminum, magnesium, and calcium with resonance cross sections in the same energy range are used, and materials such as magnesium fluoride, calcium fluoride, and aluminum fluoride are used to achieve the maximum efficiency of obtaining epithermal neutrons.
[0061] In some specific embodiments, such as Figures 1 to 3 As shown, the fission multiplication layer 240 is arranged between the moderation reflection layer 220 and the moderation absorption layer 230. There is no gap or a gap is provided between the fission multiplication layer 240 and the moderation reflection layer 220. There is no gap or a gap is provided between the fission multiplication layer 240 and the moderation absorption layer 230. The fission multiplication layer 240 is arranged at an interval from the first point 300. The fission multiplication layer 240 can receive the neutrons emitted by the moderation reflection layer 230 and perform fission multiplication on them. Specifically, the fast neutrons emitted from the moderation absorption layer 230 enter the fission multiplication layer 240, and the fast neutrons will undergo fission multiplication under the action of the fission multiplication layer 240. That is, the fission multiplication layer 240 can slow down neutrons of several MeV to about 1 MeV and increase the neutron flux. Among them, the maximum multiplication ability of the fission multiplication layer 240 is 20 times.
[0062] It should be noted that the fission multiplication layer 240 mainly generates fission neutrons through (n,f) fission reactions. The number of fission neutrons generated is related to the number of neutrons entering the fission multiplication layer 240 and the magnitude of the effective multiplication factor of the fission multiplication layer 240. Since the effective multiplication factor of the fissile material stored outside the reactor needs to be less than 0.95, the maximum multiplication efficiency of the fission multiplication layer 240 is 20. Since the average energy of the fission neutrons is 1 MeV, the fission multiplication layer 240 can effectively reduce the fast neutrons in the neutron tube 100 and increase the epithermal neutron flux.
[0063] In some specific embodiments, the material of the fission multiplication layer 240 includes one of U-235, Pu-239, Th-232, and U-233. Specifically, one of the materials U-235, Pu-239, Th-232, and U-233 can perform fission multiplication on neutrons of several MeV, thereby further slowing down neutrons of several MeV to about 1 MeV, and the neutron flux can be increased during this process.
[0064] In some specific embodiments, such as Figures 1 to 3As shown, the thermal neutron absorption layer 250 is provided on the moderation absorption layer 230. There is either close contact or a gap between the thermal neutron absorption layer 250 and the moderation absorption layer 230. The thermal neutron absorption layer 250 is located on the side of the moderation absorption layer 230 close to the first point 300, and the thermal neutron absorption layer 250 is spaced from the first point 300. The thermal neutron absorption layer 250 can receive the neutrons emitted by the moderation absorption layer 230 and absorb the thermal neutrons. The central axes of all the mounting blind holes 210 pass through the thermal neutron absorption layer 250. Specifically, the thermal neutron absorption layer 250 can absorb the thermal neutrons emitted from the moderation absorption layer 300. During the process of fast neutrons being moderated to epithermal neutrons, it is inevitable that some epithermal neutrons are over-moderated to thermal neutrons. Therefore, it is necessary to use the thermal neutron absorption layer 250 to absorb the thermal neutrons, so as to ensure that the thermal neutron flux for neutron therapy led out is low without affecting the treatment.
[0065] In some specific embodiments, the material of the thermal neutron absorption layer 250 includes one of cadmium, gadolinium, boron, and lithium. Specifically, the thermal neutron absorption layer 250 uses materials with extremely large cross-sections for thermal neutrons, such as cadmium, gadolinium, boron, and lithium. Due to the extremely large cross-section for thermal neutrons, thermal neutrons can be absorbed at a very thin thickness, while the influence on epithermal neutrons is minimized.
[0066] In some specific embodiments, as Figures 1 to 3 shown, the gamma absorption layer 260 is provided on the thermal neutron absorption layer 250. There is either close contact or a gap between the gamma absorption layer 260 and the thermal neutron absorption layer 250. The gamma absorption layer 260 is located on the side of the thermal neutron absorption layer 250 close to the first point 300, and the gamma absorption layer 260 is spaced from the first point 300. The gamma absorption layer 260 can absorb gamma rays. The central axes of all the mounting blind holes 210 pass through the gamma absorption layer 260. Specifically, the gamma absorption layer 260 can absorb the gamma rays emitted from the thermal neutron absorption layer 250. During the moderation process, gamma rays are generated due to the (n,γ) reaction of thermal neutron absorption. For neutron therapy, gamma rays are harmful rays that affect the treatment effect and are not conducive to the protection of normal tissues. Therefore, it is necessary to shield the gamma rays. The gamma absorption layer 260 uses materials with high density and high atomic number Z to absorb the gamma rays, thereby minimizing the influence of the gamma absorption layer 260 on the acquisition efficiency of epithermal neutrons.
[0067] In some specific embodiments, the material of the gamma absorption layer 260 includes lead or bismuth.
[0068] In some specific embodiments, the collimation layer 400 is provided on the regulation module 200. There is close contact or a gap between the collimation layer 400 and the regulation module 200. The collimation layer 400 is located on the side of the regulation module 200 close to the first point 300. The collimation layer 400 is arranged at an interval from the first point 300. The central axes of the respective mounting blind holes 210 all pass through the collimation layer 400. The collimation layer 400 is provided with collimation holes 410 for collimating neutrons.
[0069] In some specific embodiments, in the direction close to the first point 300, the aperture of the collimation hole 410 gradually decreases.
[0070] Preferably, in the regulation module 200, neutrons are regulated through the moderation reflection layer 220, the fission multiplication layer 240, the moderation absorption layer 230, the thermal neutron absorption layer 250, the gamma absorption layer 260, and the collimation layer 400, which can concentrate the neutrons emitted by the neutron tube 100 and solve the problem that the neutrons emitted by the neutron tube 100 are relatively dispersed. In addition, the neutrons moderated and reflected can directly enter the fission multiplication layer 240 for multiplication to improve the neutron multiplication efficiency and ensure that the generated epithermal neutron flux meets the treatment requirements of BNCT.
[0071] In a traditional neutron therapy system, the accelerator is usually more than ten meters wide, resulting in a large floor area of the neutron therapy system. Compared with the traditional neutron therapy system, in this specific embodiment, the regulation module 200 is used to regulate at least 50 neutron tubes 100, that is, the neutron tubes 100 are in the mounting blind holes 210 and are regulated through the moderation reflection layer 220, the fission multiplication layer 240, the moderation absorption layer 230, the thermal neutron absorption layer 250, the gamma absorption layer 260, and the collimation layer 400. This not only meets the requirements of neutron therapy but also reduces the size of the entire neutron therapy system to within a few meters, greatly reducing the volume of the neutron therapy system. Among them, the neutron tube 100 has a diameter of a few centimeters and a length of dozens of centimeters. That is to say, by using multiple neutron tubes 100 as the neutron source for neutron therapy, an accelerator of more than ten meters can be replaced, and the size of the neutron therapy system can be reduced to within a few meters, greatly reducing the volume of the neutron therapy system. The technical effects of this specific embodiment are as follows:
[0072] 1. By using multiple neutron tubes 100 as the neutron source of the neutron therapy device, the volume of the neutron therapy system is greatly reduced.
[0073] 2. Different treatment plans can be customized by changing the number, source strength, and position of the neutron tubes 100;
[0074] 3. By using multiple DT neutron tubes 100, it can be ensured that the failure of individual neutron tubes 100 affects the operation of neutron therapy, that is, it is ensured that the neutron therapy system can operate normally, making the neutron therapy system more inclusive of technical failures.
[0075] Example 1
[0076] As Figure 1 shown, the shapes of the moderation reflector layer 220, the fission breeding layer 240, the moderation absorber layer 230, the thermal neutron absorber layer 250, and the gamma absorber layer 250 are all semi-ellipsoidal shell shapes; where n is greater than or equal to 56. Specifically, the moderation reflector layer 220, the fission breeding layer 240, the moderation absorber layer 230, the thermal neutron absorber layer 250, and the gamma absorber layer 260 together form a shell of a semi-ellipsoid with a certain thickness. The first point 300 is located at the focus of the semi-ellipsoidal shell. By using the focus characteristics of the ellipsoid or ellipse, it is ensured that the neutron beam can be concentrated at the focus of the ellipsoid or ellipse, thus solving the technical problem of difficult focusing of the neutron beam. By using a plurality of neutron tubes 100 as the neutron source for neutron therapy, an accelerator of more than ten meters can be replaced, and the size of the neutron therapy system can be reduced to within a few meters, greatly reducing the volume of the neutron therapy system. In addition, the fast neutrons emitted by at least 56 neutron tubes 100 can successively obtain epithermal neutrons that meet the requirements of neutron therapy under the action of the moderation reflector layer 220, the fission breeding layer 240, the moderation absorber layer 230, the thermal neutron absorber layer 250, and the gamma absorber layer 260, and the flux of the epithermal neutrons also meets the requirements of neutron therapy. Among them, the array method of the neutron tubes 100 is to be arrayed on half of the spherical surface.
[0077] Example 2
[0078] As Figure 2 shown, the shapes of the moderation reflector layer 220, the fission breeding layer 240, the moderation absorber layer 230, the thermal neutron absorber layer 250, the gamma absorber layer 250, and the collimator layer 400 are all annular; where n is greater than or equal to 56. Specifically, the moderation reflector layer 220, the fission breeding layer 240, the moderation absorber layer 230, the thermal neutron absorber layer 250, the gamma absorber layer 260, and the collimator layer 400 together form a tubular body with a certain thickness and a certain length. The first point 300 is located at the center of the tubular body. By using a plurality of neutron tubes 100 as the neutron source for neutron therapy, an accelerator of more than ten meters can be replaced, and the size of the neutron therapy system can be reduced to within a few meters, greatly reducing the volume of the neutron therapy system. In addition, the fast neutrons emitted by at least 56 neutron tubes 100 can successively obtain epithermal neutrons that meet the requirements of neutron therapy under the action of the moderation reflector layer 220, the fission breeding layer 240, the moderation absorber layer 230, the thermal neutron absorber layer 250, the gamma absorber layer 260, and the collimator layer 400, and the flux of the epithermal neutrons also meets the requirements of neutron therapy. Among them, the array method of the neutron tubes 100 is to be arrayed on the surface of the tubular body.
[0079] Among them, the outer surface of the collimation layer 400 is attached to the inner surface of the gamma absorption layer 260. Collimation holes 410 are formed in the collimation layer 400. The shape of the collimation holes 410 is annular, that is, the axial section of the collimation holes 410 is a funnel shape that is mirror image to each other. The narrow openings of the axial section of the funnel shape are away from the gamma absorption layer 260.
[0080] The collimation layer 400 uses a hydrogen-containing material to slow down epithermal neutrons to thermal neutrons with the maximum efficiency, and uses thermal neutron absorption materials such as Li and B therein to absorb the thermal neutrons and generate fewer gamma rays. The purpose of the collimation layer 400 is to limit the neutron beam within the collimator, so that the neutron beam is only led out from the collimator opening. That is, during neutron therapy, the collimator can limit the neutron beam within the tumor area, and the normal tissues outside the area are not affected or the influence is limited to the minimum range.
[0081] The material of the collimation layer 400 is polyethylene containing lithium fluoride.
[0082] Embodiment 3
[0083] As Figure 3 shown, the shapes of the moderation reflection layer 220, the fission breeding layer 240, the moderation absorption layer 230, the thermal neutron absorption layer 250, the gamma absorption layer 250, and the collimation layer 400 are all circular. The center lines of the moderation reflection layer 220, the fission breeding layer 240, the moderation absorption layer 230, the thermal neutron absorption layer 250, the gamma absorption layer 260, and the collimation layer 400 coincide with each other. The first bottom surface of the moderation reflection layer 220 has a circular groove 221, and the first bottom surface is close to the first point 300. The fission breeding layer 240 and the moderation absorption layer 230 are both embedded in the circular groove 221; n is greater than or equal to 100. Specifically, the moderation reflection layer 220, the fission breeding layer 240, the moderation absorption layer 230, the thermal neutron absorption layer 250, the gamma absorption layer 260, and the collimation layer 400 together form a columnar body with a certain length. The first point 300 is located outside the columnar body, and the first point 300 is located on the center line of the columnar body. By using a plurality of neutron tubes 100 as the neutron source for neutron therapy, an accelerator of more than ten meters can be replaced, and the size of the neutron therapy system can be reduced to within a few meters, greatly reducing the volume of the neutron therapy system. In addition, the fast neutrons emitted by at least 100 neutron tubes 100 can sequentially obtain epithermal neutrons that meet the requirements of neutron therapy under the action of the moderation reflection layer 220, the fission breeding layer 240, the moderation absorption layer 230, the thermal neutron absorption layer 250, the gamma absorption layer 260, and the collimation layer 400.
[0084] Among them, the collimation layer 400 is attached to the gamma absorption layer 260. The collimation layer 400 is located on the side of the gamma absorption layer 260 close to the first point 300. The center lines of the moderation reflection layer 220, the fission breeding layer 240, the moderation absorption layer 230, the thermal neutron absorption layer 250, the gamma absorption layer 260, and the collimation layer 400 coincide with each other. The collimation layer 400 is provided with collimation holes 410. The shape of the collimation holes 410 is circular. The narrow openings of the collimation holes 410 are away from the gamma absorption layer 500. The material of the collimation layer 400 is polyethylene containing lithium fluoride.
[0085] In the description of the present invention, it should be understood that the terms "center", "longitudinal", "transverse", "length", "width", "thickness", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", "clockwise", "counterclockwise", "axial", "radial", "circumferential", etc. indicate the orientation or positional relationship based on the orientation or positional relationship shown in the drawings, and are only for the convenience of describing the present invention and simplifying the description, rather than indicating or implying that the device or element referred to must have a specific orientation, be constructed and operated in a specific orientation, and therefore should not be construed as a limitation of the present invention.
[0086] In addition, the terms "first" and "second" are only used for descriptive purposes and cannot be understood as indicating or implying relative importance or implicitly specifying the quantity of the indicated technical features. Thus, the features defined with "first" and "second" may explicitly or implicitly include at least one of such features. In the description of the present invention, the meaning of "a plurality" is at least two, such as two, three, etc., unless otherwise specifically and clearly defined.
[0087] In the present invention, unless otherwise clearly specified and limited, the terms "mounted", "connected", "connected to", "fixed", etc. should be understood in a broad sense. For example, it may be a fixed connection, a detachable connection, or integrated; it may be a mechanical connection, an electrical connection, or communicable with each other; it may be directly connected, or indirectly connected through an intermediate medium, and may be the internal communication of two elements or the interaction relationship between two elements, unless otherwise clearly limited. For those of ordinary skill in the art, the specific meanings of the above terms in the present invention can be understood according to specific circumstances.
[0088] In the present invention, unless otherwise clearly defined or limited, a first feature being "on" or "under" a second feature may mean that the first and second features are in direct contact, or the first and second features are indirectly in contact via an intermediate medium. Moreover, a first feature being "above", "over" and "on top of" a second feature may mean that the first feature is directly above or obliquely above the second feature, or merely indicates that the horizontal height of the first feature is higher than that of the second feature. A first feature being "under", "below" and "beneath" a second feature may mean that the first feature is directly below or obliquely below the second feature, or merely indicates that the horizontal height of the first feature is less than that of the second feature.
[0089] In the present invention, the terms "an embodiment", "some embodiments", "an example", "a specific example", or "some examples", etc. mean that the specific features, structures, materials, or characteristics described in connection with the embodiment or example are included in at least one embodiment or example of the present invention. In this specification, the schematic representations of the above terms do not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials, or characteristics described may be combined in any one or more embodiments or examples in a suitable manner. In addition, without contradiction, those skilled in the art may combine and combine the different embodiments or examples described in this specification and the features of different embodiments or examples.
[0090] Although the above embodiments have been shown and described, it can be understood that the above embodiments are exemplary and should not be construed as limiting the present invention. Any changes, modifications, substitutions, and variations made by those of ordinary skill in the art to the above embodiments are within the protection scope of the present invention.
Claims
1. A neutron therapy system based on multiple neutron tubes, characterized in that Comprising: n neutron tubes; A regulation module, on which there are n installation blind holes arranged at intervals, the central axes of each of the installation blind holes intersect at a first point, the first point is spaced from the regulation module, the neutron tubes extend into the installation blind holes, and the outlets of the neutron tubes abut against the bottom surfaces of the installation blind holes, the neutron tubes and the installation blind holes correspond one by one, and the regulation module can regulate the neutrons emitted by the neutron tubes so that the neutron flux and the neutron energy meet the requirements of neutron therapy.
2. The neutron therapy system based on multiple neutron tubes according to claim 1, wherein The regulation module includes: A moderation reflection layer, which can reflect and moderate neutrons; A moderation absorption layer, which is arranged on the moderation reflection layer, there is no gap or a gap is provided between the moderation absorption layer and the moderation reflection layer, the moderation absorption layer is located on the side of the moderation reflection layer close to the first point, the moderation absorption layer is spaced from the first point, the moderation absorption layer can receive the neutrons emitted by the moderation reflection layer and moderate and absorb them, and the central axes of each of the installation blind holes all pass through the moderation absorption layer; Wherein, the installation blind holes penetrate through the moderation reflection layer, and the bottom surfaces of the installation blind holes and the surfaces of the moderation absorption layer adjacent to the moderation reflection layer are coplanar.
3. The neutron therapy system based on multiple neutron tubes according to claim 2, characterized in that, The regulation module further includes: A fission multiplication layer, which is arranged between the moderation reflection layer and the moderation absorption layer, there is no gap or a gap is provided between the fission multiplication layer and the moderation reflection layer, the fission multiplication layer is spaced from the first point, the fission multiplication layer can receive the neutrons emitted by the moderation reflection layer and perform fission multiplication on them.
4. The neutron therapy system based on multiple neutron tubes according to claim 2 or 3, characterized in that, The regulation module further includes: A thermal neutron absorption layer, which is arranged on the moderation absorption layer, there is no gap or a gap is provided between the thermal neutron absorption layer and the moderation absorption layer, the thermal neutron absorption layer is located on the side of the moderation absorption layer close to the first point, the thermal neutron absorption layer is spaced from the first point, the thermal neutron absorption layer can receive the neutrons emitted by the moderation absorption layer and absorb the thermal neutrons, and the central axes of each of the installation blind holes all pass through the thermal neutron absorption layer.
5. The neutron therapy system based on multiple neutron tubes according to claim 4, characterized in that, The regulation module further includes: A gamma absorption layer, which is arranged on the thermal neutron absorption layer, there is no gap or a gap is provided between the gamma absorption layer and the thermal neutron absorption layer, the gamma absorption layer is located on the side of the thermal neutron absorption layer close to the first point, the gamma absorption layer is spaced from the first point, the gamma absorption layer can absorb gamma rays, and the central axes of each of the installation blind holes all pass through the gamma absorption layer.
6. The neutron therapy system based on multiple neutron tubes according to any one of claims 1-5, characterized in that, Further comprising: A collimation layer, which is arranged on the regulation module, there is no gap or a gap is provided between the collimation layer and the regulation module, the collimation layer is located on the side of the regulation module close to the first point, the collimation layer is spaced from the first point, the central axes of each of the installation blind holes all pass through the collimation layer, and the collimation layer is provided with collimation holes for collimating neutrons.
7. The neutron therapy system based on multiple neutron tubes according to claim 6, wherein in the direction close to the first point, the aperture of the collimation hole gradually decreases.
8. The neutron therapy system based on multiple neutron tubes according to any one of claims 1-5, wherein the shape of the regulation module is a semi-ellipsoidal shell, where n is greater than or equal to 56; or the shape of the regulation module is annular, where n is greater than or equal to 56; or the shape of the regulation module is circular, where n is greater than or equal to 100.
9. The neutron therapy system based on multiple neutron tubes according to any one of claims 1-5, wherein The neutron source intensity of the neutron tube is less than or equal to 10 11 .
10. The neutron therapy system based on multiple neutron tubes according to claim 5, characterized in that, the material of the regulation module includes: a moderation and reflection functional material, and the moderation and reflection functional material includes one of lead, depleted uranium, bismuth, and beryllium; a moderation and absorption functional material, and the moderation and absorption functional material includes one of magnesium fluoride, aluminum fluoride, and calcium fluoride; a fission and proliferation functional material, and the fission and proliferation functional material includes one of U-235, Pu-239, Th-232, and U-233; a thermal neutron absorption functional material, and the thermal neutron absorption functional material includes one of cadmium, gadolinium, boron, and lithium; a gamma absorption functional material, and the gamma absorption functional material includes lead or bismuth.
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