Neutron capture therapy system and neutron generation unit recovery method

Abstract

A neutron capture therapy system includes an accelerator generating a charged particle beam, a transmission device transmitting the charged particle beam, a neutron generating part generating a neutron beam in reaction with the charged particle beam, a beam shaping body adjusting the energy spectrum of the neutron beam, and a guide device, the transmission device at least including a first transmission part and a second transmission part detachably connected with the first transmission part, the first transmission part including a first position and a second position, the guide device guiding the first transmission part and the neutron generating part to move from the first position to the second position, the neutron generating part arranged on the first transmission part being accommodated in the beam shaping body when the first transmission part is located at the first position, and the neutron generating part arranged on the first transmission part being separated from the beam shaping body when the first transmission part is located at the second position. In this way, a safe distance between the operator and the neutron generating part is maintained, the time of the operator contacting the radiation is reduced, and a safe, reliable and stable solution for recycling the neutron generating part is provided.

Description

Technical Field

[0001] This invention relates in one aspect to a radioactive irradiation system, and more particularly to a neutron capture therapy system; this invention also relates in another aspect to a method for recovering radioactive consumables from a radioactive irradiation system, and more particularly to a method for recovering the neutron generating part of a neutron capture therapy system. Background Technology

[0002] With the development of atomic science, radiation therapy, such as cobalt-60, linear accelerators, and electron beams, has become one of the main methods of cancer treatment. However, traditional photon or electron therapy is limited by the physical conditions of radiation itself. While killing tumor cells, it also damages a large amount of normal tissue along the beam path. In addition, due to the different sensitivities of tumor cells to radiation, traditional radiation therapy is often ineffective for more radiation-resistant malignant tumors (such as glioblastoma multiforme and melanoma).

[0003] To reduce radiation damage to surrounding normal tissues, the concept of targeted therapy in chemotherapy has been applied to radiotherapy. Furthermore, for highly radiation-resistant tumor cells, radiation sources with high relative biological effects (RBEs) are being actively developed, such as proton therapy, heavy ion therapy, and neutron capture therapy. Neutron capture therapy combines these two concepts; for example, boron neutron capture therapy utilizes the specific accumulation of boron-containing drugs on tumor cells, combined with precise neutron beam modulation, to provide a better cancer treatment option than traditional radiation.

[0004] In accelerator neutron capture therapy systems, a charged particle beam is accelerated by an accelerator to an energy level sufficient to overcome the Coulomb repulsion between the atomic nuclei in the neutron generator within the beam-shaping unit. The charged particles then undergo a nuclear reaction with the neutron generator to produce neutrons. Therefore, during neutron production, the neutron generator is irradiated by the high-power accelerated charged particle beam, causing a significant increase in its temperature and affecting its lifespan. To ensure stable neutron production, the old neutron generator needs to be recycled and replaced with a new one; therefore, regular replacement of the neutron generator is essential. However, the neutron generator irradiated by the high-energy accelerated charged particle beam inevitably contains a large amount of radiation. Therefore, if sufficient protective or isolation measures are not taken when replacing the neutron generator at close range, there will inevitably be radiation safety hazards. Summary of the Invention

[0005] This invention provides a neutron capture therapy system, comprising an accelerator for generating a charged particle beam, a transmission device for transmitting the charged particle beam, a radioactive consumable neutron generating section that reacts with the charged particle beam to generate a neutron beam, a beam shaper for energy spectrum modulation of the neutron beam, and a guiding device. The transmission device includes at least a first transmission section and a second transmission section, wherein the first transmission section and the second transmission section are detachably connected. The neutron generating section is disposed at the end of the first transmission section, and the first transmission section includes a first position and a second position. The guiding device is capable of guiding the first transmission section from the first position to the second position. When the first transmission section is in the first position, the neutron generating section at the end of the first transmission section is housed in the beam shaper and can react with the charged particle beam to generate neutrons. When the first transmission section is in the second position, the neutron generating section and the beam shaper are separated from each other, at which time the first transmission section and the neutron generating section are in a replaceable state.

[0006] When the neutron generator of the radioactive consumable is located within the beam shaping body, the radiation shielding within the beam shaping body can shield the radiation leaking from the neutron generator to prevent radiation exposure to the operator. After the neutron generator detaches from the beam shaping body, it is exposed to the operating space. By shortening the operator's working time and / or extending the working distance between the operator and the neutron generator, the radiation leaking from the neutron generator can be minimized from irradiating the operator as it moves from the first position to the second position along with the first transmission unit. According to one aspect of the technical solution provided by the present invention, the guiding device can quickly, stably, and reliably guide the neutron generator from the first working position back to the radiation shielding device in the second position. During the replacement of the neutron generator, the operator has the working conditions to maintain a sufficient safe distance from the neutron generator or even be completely isolated from it, effectively avoiding excessive radiation damage.

[0007] As a preferred embodiment, the guiding device includes a first guiding section and a second guiding section, wherein the first guiding section and the second guiding section have different guiding directions. According to one embodiment of the invention, in situations where the usable space inside the operating room is small and limited, the first guiding section of the guiding device guides the first transmission section of the transmission device to move first along a first direction in which the transmission device is arranged, and then enters the second guiding section of the guiding device, thus avoiding some facilities and obstacles that may exist in the first direction. This arrangement is beneficial for the miniaturization and compactness of the operating room, improves space utilization, and reduces the floor area and construction costs.

[0008] As a preferred embodiment, in a plane parallel to the ground where the first guide portion is located, the projection of the line connecting the first end and the second end of the second guide portion forms a first angle with the first guide portion; in a plane perpendicular to the ground where the first guide portion is located, the projection of the line connecting the first end and the second end of the second guide portion forms a second angle with the first guide portion.

[0009] As a preferred embodiment, the second guide section includes at least two guide rails, wherein a fixed rail is detachably connected to the first guide section, and a movable rail is rotatably connected to the fixed rail.

[0010] As a preferred embodiment, the movable track is connected to the fixed track via a hinge structure and has two positions. When the movable track is in the first position, it maintains a normal guiding state together with the fixed track. When the movable track is subjected to force, it is in the second position and moves at a certain angle relative to the fixed track, and then automatically returns to the first position.

[0011] As a preferred embodiment, the material of the guiding device comprises more than 90% (by weight) of at least one of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, Ca, and Ti.

[0012] As a preferred embodiment, the first guide portion is made of aluminum alloy, magnesium-aluminum alloy, carbon fiber composite material, glass fiber composite material, or a combination thereof.

[0013] As a preferred embodiment, the material used for the second guide portion can be the same as that used for the first guide portion, or it can be a different material used for the first guide portion, such as stainless steel or iron.

[0014] As a preferred embodiment, the surface of the second guide portion may be coated with an anti-radiation film, or an additional removable anti-radiation protective cover may be provided.

[0015] Preferably, the shape and surface of the radiation shield match the cross-sectional shape of the second guide portion.

[0016] A second aspect of the present invention provides a neutron capture therapy system, the neutron capture therapy system comprising an accelerator for generating a charged particle beam, a transmission device for transmitting the charged particle beam, a neutron generating section for reacting with the charged particle beam to generate a neutron beam, a beam shaper for energy spectrum modulation of the neutron beam, and a guiding device, wherein the transmission device comprises at least a first transmission section and a second transmission section, wherein the first transmission section and the second transmission section are detachably connected, and the neutron generating section is disposed in the first transmission section. The neutron capture therapy system further comprises a movable radiation shielding device for accommodating the first transmission section and the neutron generating section guided by the guiding device, the radiation shielding device retrieving the first transmission section moving along the guiding device and the neutron generating section at its end together.

[0017] As a preferred embodiment, the guiding device includes a first guiding portion and a second guiding portion, wherein the first guiding portion and the second guiding portion have different guiding directions.

[0018] As a preferred embodiment, the guiding device further includes a third guiding portion, wherein the third guiding portion is fixedly housed within the movable radiation shielding device.

[0019] Preferably, the second guide portion and the third guide portion are detachably connected, or can be flexibly aligned and connected, so as to facilitate guiding the first transmission portion of the transmission device into the radiation shielding device.

[0020] As a preferred embodiment, the radiation shielding device is made of radiation shielding material and includes an openable component. When the openable component is opened, the radiation shielding device forms a receiving opening, through which the first transmission part of the transmission device enters the radiation shielding device. When the openable component is closed, the radiation shielding device forms a sealed shielding space to prevent radiation leakage from the neutron generating part.

[0021] As a preferred embodiment, the movable radiation shielding device further includes a buffer device. This buffer device is capable of elastic deformation after the first transmission unit contacts it, applying an opposite force in the direction of movement of the first transmission unit, thus safely stopping it within the radiation shielding device to prevent damage to the first transmission unit and / or the radiation shielding device. Furthermore, the neutron capture therapy system includes a positioning system that enables the radiation shielding device to move to a preset position and dock with the guiding device. The positioning system can pre-mark the position using structural positioning, three-dimensional algorithm positioning, or other methods, allowing the radiation shielding device to move to the ideal position aligned with the guiding device. This ensures that the first transmission unit and its end-mounted neutron generating unit can be reliably retrieved into the radiation shielding device after moving to the end of the guiding device.

[0022] As a preferred embodiment, the movable radiation shielding device further includes a positioning system that enables the radiation shielding device to move to a preset position, thereby allowing the second guide and the third guide to dock.

[0023] As a preferred embodiment, the neutron generating part enters the receiving opening of the movable radiation shielding device later than the first transmission part along the guiding device, and the opening and closing part closes after the neutron generating part has completely entered the movable radiation shielding device.

[0024] As a preferred embodiment, when the closable component of the movable radiation shielding device is closed, it can achieve an internal vacuum environment or be filled with inert gas, while simultaneously achieving physical isolation from the outside air.

[0025] As a preferred embodiment, the neutron capture therapy system further includes a control unit, which can remotely control the opening and closing of the closable component of the movable radiation shielding device via a wired or wireless connection.

[0026] A third aspect of the present invention provides a neutron capture therapy system, the neutron capture therapy system comprising an accelerator for generating a charged particle beam, a transmission device for transmitting the charged particle beam, a neutron generating section for reacting with the charged particle beam to generate a neutron beam, a beam shaper for energy spectrum modulation of the neutron beam, and a guiding device. The transmission device includes at least a first transmission section and a second transmission section, wherein the first transmission section and the second transmission section are detachably connected, the neutron generating section is disposed in the first transmission section, and the first transmission section includes a first position and a second position. The guiding device is capable of guiding the first transmission section from the first position to the second position. When the first transmission section is in the first position, the neutron generating section is housed in the beam shaper and is capable of reacting with the charged particle beam to generate neutrons; when the first transmission section is in the second position, the neutron generating section is separated from the beam shaper. The neutron capture therapy system further includes a driving device that provides power to separate the first transmission section from the beam shaper, move it out of the first position, and move it along the guiding device.

[0027] As a preferred embodiment, the neutron capture therapy system further includes a support device that stably supports the first transmission unit along the direction in which the transmission device is arranged.

[0028] As a preferred embodiment, the guiding device includes a first guiding portion and a second guiding portion, wherein the first guiding portion and the second guiding portion have different guiding directions.

[0029] As a preferred embodiment, the driving device includes a drive frame and a power structure, the drive frame carrying the first transmission unit and the neutron generation unit, and the power structure providing driving force.

[0030] As a preferred embodiment, the neutron capture therapy system further includes a control unit, which can remotely control the power structure of the drive device via a wired or wireless connection, thereby providing power for the movement of the first transmission unit and the neutron generation unit between a first position and a second position.

[0031] As a preferred embodiment, the drive frame of the drive device includes at least one set of roller structures.

[0032] As a preferred embodiment, the drive frame of the drive device includes at least two sets of roller structures, and the two sets of rollers roll in different directions.

[0033] As a preferred embodiment, the two sets of rollers of the drive frame have different rolling planes, and the rolling planes are perpendicular to each other.

[0034] As a preferred embodiment, at least two sets of roller structures of the drive frame are combined with concave and / or convex slide rails of the guide device to achieve transmission motion, and one or two sets of rollers can be matched with the structure of concave and / or convex slide rails to achieve rolling transmission.

[0035] Furthermore, the neutron capture therapy system also includes a cooling device for cooling the neutron generating unit. The cooling device includes a cooling pipeline. When the first transmission unit is in the first position, the cooling pipeline is in a connected state, and the cooling device performs cooling operations. When the first transmission unit is in the second position, the cooling pipeline is in a disconnected state, the cooling device cannot perform normal operations, and the cooling device and the first transmission unit are recycled and replaced together.

[0036] As a preferred embodiment, the neutron capture therapy system further includes a detection device comprising a detection circuit. When the first transmission unit is in a first position, the detection device is in a connected state to perform detection operations; when the first transmission unit is in a second position, the detection circuit is disconnected and normal operation is impossible. The detection device, along with the cooling device, the neutron generating unit, and the first transmission unit, is then recycled and replaced. The "detection device" referred to herein can be a charged particle sensor, a vacuum pressure sensor, or a neutron detector, or other devices suitable for installation at the first transmission unit.

[0037] A fourth aspect of this application provides a method for recovering the neutron generating section of the aforementioned neutron capture therapy system. The neutron capture therapy system further includes an auxiliary pipeline connected to the neutron generating section or the first transmission section. The method for recovering the neutron generating section includes the following steps: separating the first transmission section from the second transmission section; disconnecting the auxiliary pipeline from the neutron generating section; applying a first power to the first transmission section having the neutron generating section, causing the first transmission section to separate from the beam shaper along a guide device from a first position; and then applying a second power to the first transmission section having the neutron generating section, causing the first transmission section to move again along the guide device until it reaches the recovery position.

[0038] As a preferred embodiment, the neutron capture therapy system further includes a shielding facility with an opening through which the first transmission unit passes when the shielding facility is kept closed.

[0039] Furthermore, the neutron generator recovery method is carried out via the opening while the shielding facility remains closed.

[0040] Furthermore, the shielding facility is provided with an auxiliary door, which at least partially blocks the opening of the shielding facility when closed and has an opening that matches the shape of the first transmission part, the guiding device, and the auxiliary pipeline provided at the opening of the shielding facility. The neutron generation part recovery method is performed through the opening while the shielding facility is kept closed and the auxiliary door is kept open.

[0041] Furthermore, the neutron capture therapy system also includes a radiation shielding device for accommodating the recovered neutron generating unit, a first space and a second space separated by the shielding device, a radiation protection shield on the guiding device, the neutron generating unit located in the first space, and the second transmission unit located in the second space. The neutron generating unit recovery method further includes: before applying a first power to the first transmission unit where the neutron generating unit is located: moving the radiation shielding device to the second space and fixing it at a predetermined position, opening the opening and closing mechanism of the radiation shielding device, and removing the radiation protection shield on the guiding device; after applying a second power to the first transmission unit where the neutron generating unit is located: the first transmission unit moves along the guiding device into the interior of the radiation shielding device, closing the opening and closing mechanism of the radiation shielding device, covering the guiding device with the radiation protection shield, and pushing the radiation shielding device out of the second space.

[0042] The fifth aspect of this application provides a method for recovering the neutron generator section of the aforementioned neutron capture therapy system. The neutron capture therapy system further includes a shielding facility that remains closed during recovery operations. The shielding facility has an opening. The neutron generator section recovery method includes the following steps: disconnecting the cooling pipe connected to the neutron generator section through the opening in the shielding facility; applying a first power to a first transmission section containing the neutron generator section, causing the first transmission section to separate from the beam shaper along a guide device from a first position and move to a position close to the opening in the shielding facility; then applying a second power to the first transmission section containing the neutron generator section, causing the first transmission section to move again along the guide device until it reaches the recovery position. Preferably, the neutron generator section recovery method further includes disconnecting the detection circuit and other connecting lines of the detection device while simultaneously disconnecting the cooling pipe. When the neutron generator section separates from the beam shaper, the exposure of the neutron generator section results in significant radiation. By keeping the shielding facility closed during recovery, and allowing operators to replace the neutron generator section only through the opening in the shielding facility, radiation leakage in the working environment is greatly reduced, and operational safety is improved.

[0043] The sixth aspect of this application provides a method for recovering the neutron generator of the aforementioned neutron capture therapy system, comprising the following steps: a shielding facility kept closed during recovery operations, the shielding facility having an auxiliary door. The auxiliary door remains closed during system operation. When the system stops and the neutron generator needs replacement, the auxiliary door is opened, and the cooling pipe connected to the neutron generator is disconnected through the opening in the auxiliary door. A first power is applied to a first transmission section containing the neutron generator, causing the first transmission section to separate from the beam shaper along a guide device from a first position and move to an opening near the shielding facility. A second power is then applied to the first transmission section containing the neutron generator, causing the first transmission section to move again along the guide device until it enters the recovery position within the radiation shielding device, at which point the auxiliary door is closed. Preferably, the shape of the opening in the auxiliary door generally matches the shape of the first transmission section, the guide device, and the associated piping structure, vacuum valve, etc., located at the opening. The shape includes, but is not limited to, elliptical, rhomboid, square, or even irregular shapes.

[0044] This embodiment of the application shortens the time operators are exposed to strong radiation during the replacement of radioactive consumables, providing a relatively safe operating distance between operators and the neutron generating unit. This allows operators to maintain a sufficient safe distance or even complete isolation from the radioactive consumables during replacement, thereby reducing operator contact with radiation and minimizing radiation safety hazards. Furthermore, the neutron capture therapy system, which is part of a radioactive irradiation system, is compact and easy to install. In situations with limited operating space, it efficiently utilizes available space and reduces floor space and construction costs, providing a reliable, stable, and safe recovery solution for the neutron generating unit. Attached Figure Description

[0045] Figure 1 This is a plan view of a neutron capture therapy system according to an embodiment of the present invention.

[0046] Figure 2 This is a perspective view of a neutron capture therapy system according to an embodiment of the present invention, showing a first transmission unit of the transmission device in a first position and a radiation shielding device in a closed state.

[0047] Figure 3 This is a perspective view of a neutron capture therapy system according to an embodiment of the present invention, showing the first transmission unit of the transmission device in the second position and the radiation shielding device in the open state.

[0048] Figure 4 It is based on Figure 1 A top view of the guiding device of the neutron capture therapy system in this embodiment.

[0049] Figure 5 This is a plan view of a neutron capture therapy system according to another embodiment of the present invention.

[0050] Figure 6 It is based on Figure 5 A perspective view of the guiding device for another embodiment of the neutron capture therapy system.

[0051] Figure 7 A plan view of the first transmission section of the transmission device is shown.

[0052] Figure 8 This is a cross-sectional schematic diagram of the drive frame roller assembly of a drive device for a neutron capture therapy system according to an embodiment of the present invention.

[0053] Figure 9a and 9b This is a schematic diagram and a cross-sectional view of the radiation protection shield of the guiding device of a neutron capture therapy system according to an embodiment of the present invention.

[0054] Figure 10 This is a perspective view of a neutron capture therapy system according to an embodiment of the present invention, showing a schematic diagram of the recovery of the first transmission unit and the neutron generation unit when the shielding facility is in the closed state.

[0055] Figures 11a to 11e This is a schematic diagram of the auxiliary door of the radiation shielding device of a neutron capture therapy system according to an embodiment of the present invention, and its open / closed state. Detailed Implementation

[0056] Neutron capture therapy has seen increasing application as an effective cancer treatment in recent years, with boron neutron capture therapy being the most common. Neutrons for boron neutron capture therapy can be supplied by nuclear reactors or accelerators. This application's embodiments use accelerator-based boron neutron capture therapy as an example. The basic components of accelerator-based boron neutron capture therapy typically include an accelerator for accelerating charged particles (such as protons, deuterons, etc.), a radioactive consumable neutron generator and thermal removal system, and a beam shaper. The accelerated charged particles interact with the metallic neutron generator to produce neutrons. The appropriate nuclear reaction is selected based on the required neutron yield and energy, the available energy and current of the accelerated charged particles, and the physicochemical properties of the metallic neutron generator. Commonly discussed nuclear reactions include... 7 Li(p,n) 7 Be and 9 Be(p,n) 9 B. Both of these reactions are endothermic, with energy thresholds of 1.881 MeV and 2.055 MeV, respectively. Since the ideal neutron source for boron neutron capture therapy is hyperthermic neutrons at the keV energy level, theoretically, bombarding the lithium neutron generator with protons whose energy is only slightly above the threshold could produce relatively low-energy neutrons, which could be used clinically without much slowing down. However, the interaction cross-section between the lithium (Li) and beryllium (Be) neutron generators and the threshold-energy protons is not high. To generate a sufficiently large neutron flux, higher-energy protons are usually chosen to initiate the nuclear reaction.

[0057] An ideal neutron generator for radioactive consumables should possess characteristics such as high neutron yield, neutron energy distribution close to the hyperthermic neutron energy region (described in detail below), minimal strong penetration radiation, safety, low cost, ease of operation, and high temperature resistance. However, in reality, it is impossible to find a nuclear reaction that meets all these requirements. The embodiments in this application use a neutron generator made of lithium metal. However, as those skilled in the art will know, the neutron generator can also be made of other metallic materials besides those discussed above.

[0058] The requirements for a thermal removal system vary depending on the nuclear reaction selected, such as 7 Li(p,n)7 Due to the difference in melting point and thermal conductivity between the neutron-generating component (lithium metal) and benzene, the requirements for the heat removal system are relatively high. 9 Be(p,n) 9 B is high. In the embodiments of this application, the following are used: 7 Li(p,n) 7 The nuclear reaction of Be. It can be seen that the temperature of the neutron generator, which is irradiated by a high-energy accelerated charged particle beam, will inevitably rise significantly, thus affecting the service life of the neutron generator.

[0059] Therefore, neutron capture therapy systems, which are part of radioactive irradiation systems, inevitably involve the replacement of radioactive consumables, specifically the neutron generating unit. To address this issue and minimize operator contact with radiation, embodiments of this application provide a neutron capture therapy system that reliably recovers the neutron generating unit. The operating space along the direction of the transmission device and perpendicular to the neutron generating unit is limited, effectively utilizing space and avoiding interference and obstruction from operating spaces at the same horizontal level along the direction of the transmission device. This reduces the need for acceleration devices for protons within the transmission device, shrinks the operating space layout, and ultimately lowers the overall footprint and construction costs.

[0060] To address the issue of replacing the neutron generating part of the aforementioned radioactive consumables, and to minimize operator contact with radiation, embodiments of this application provide a neutron capture therapy system.

[0061] Since the primary radiation exposure to operators originates from the nuclear reaction that occurs after charged particle beams irradiate the neutron generator of the radioactive consumable, the embodiments of this application aim to illustrate the disassembly of neutron generators that have undergone nuclear reaction and reached the end of their service life, without involving the installation of new neutron generators. Furthermore, the directional terms such as "up," "down," "horizontal," and "vertical" mentioned in the embodiments of this invention are used for ease of description, depicting the positional relationship between components according to the directions shown in the illustrations, and are not intended to define their absolute directions.

[0062] Hereinafter, a preferred embodiment of the neutron capture therapy system will be described with reference to the accompanying drawings.

[0063] Figure 1 , Figure 2 These are plan and perspective schematic diagrams of a neutron capture therapy system according to an embodiment of the present invention, such as... Figure 1 and Figure 2As shown, the neutron capture therapy system 100 includes a transmission device 10, a neutron generating unit 20 containing radioactive consumables, a beam shaper 30, a guiding device 40, a radiation shielding device 50, and a support device 60. The neutron capture therapy system 100 includes at least a first space R1 and a second space R2. The first space R1 includes an accelerator 200 for generating a charged particle beam P, a portion of the transmission device 10 for transmitting the charged particle beam P, support equipment for supporting the transmission device, and detection equipment. The transmission direction of the charged particle beam P is consistent with the arrangement direction of the transmission device 10. The transmission device 10 connects the first space R1 and the second space R2. The second space R2 is the core reaction space of the entire system and has a relatively large radiation dose. The second space R2 is physically separated from the first space R1 by the shielding facility 300, therefore the radiation dose in the first space R1 is relatively within a safe and controllable range. The shielding facility 300 includes at least one shielding door 301 and / or 302, and at least one opening 303 for the transmission device 10 to pass through when the shielding facility 300 is closed. In the illustrated embodiment, the transmission device 10 is in a vacuum state and includes at least a first transmission section 11 and a second transmission section 12, which are detachably connected. The first and second transmission sections are preferably hollow tubular in shape, and their cross-sectional shapes include, but are not limited to, circular, elliptical, rhomboid, square, and irregular shapes. The shape of at least one opening of the shielding facility 300 can conform to the shape of the transmission section passing through the opening, including but not limited to circular, elliptical, rhomboid, square, and irregular shapes. During the replacement of radioactive consumables and disassembly of the transmission device, the first and second transmission sections of the transmission device are preferably kept in a vacuum state. The second space R2 includes a first transmission section 11 of a transmission device 10, a neutron generating section 20 located at one end of the transmission device 10 and reacting with the charged particle beam P to generate a neutron beam N, and a beam shaper 30 for adjusting the energy spectrum of the neutron beam N. The transmission device 10 transmits the charged particles P, accelerated by the accelerator 200, from the first space R1 to the neutron generating section 20 of the second space R2. The accelerator 200 accelerates the charged particles P to an energy sufficient to overcome the nuclear force of the target material, causing them to react with the neutron generating section 20. 7 Li(p,n) 7The Be nuclear reaction produces neutrons, which form a neutron beam N that exits from the beam exit. The beam shaper 30 is usually large and not suitable for movement, so it is fixedly installed inside the wall in an embedded form. It includes a decelerator, a thermal neutron absorber, and a radiation shield (not shown in the attached figures). The decelerator is usually made of aluminum fluoride as the main material, and optionally one or more mixed materials of lithium fluoride, aluminum, lead fluoride, alumina, calcium fluoride, or magnesium fluoride. Some of these materials are brittle, so the installation process requires high precision. It slows down the neutrons generated from the neutron generator 20 to the hyperthermal neutron energy region. The deviated neutrons are guided back to the decelerator by the reflector to increase the intensity of the hyperthermal neutron beam. The thermal neutron absorber absorbs the thermal neutrons to avoid unnecessary damage to superficial normal tissues due to excessive dose during treatment. The radiation shield is used to shield leaked neutrons and photons to reduce the dose to normal tissues in non-irradiated areas. The neutron capture therapy system 100 further includes a third space R3 as an irradiation chamber, through which a compliant neutron beam can exit from the beam exit and enter the irradiation chamber for use.

[0064] Figure 2 The diagram shows the shielding facility 300 between the first space R1 and the second space R2 in an open state. When shielding door 301 and / or shielding door 302 are open, the first space R1 and the second space R2 are connected. (In conjunction with...) Figure 1 The neutron capture therapy system 100 includes a support device 60 and / or 61 for stably supporting the transmission device 10 along the direction in which the transmission device is arranged. The support device 60 is disposed at the lower part of the first transmission section 11, one end of which has a neutron generating section 10 housed in a beam shaper 30, and the first transmission section 11 is located at a first position L1. In alternative embodiments, the support device 60 may also be disposed above or to the side of the first transmission section 11 for support.

[0065] Reference Figure 1 and Figure 2 The guide device 40 is disposed between the support device 60 and the first transmission unit 11 (see reference). Figure 4 The neutron capture therapy system 100 also includes a drive unit 70 (see reference). Figure 7 The guiding device 40 may include a first track (first guiding section) 41 and a second track (second guiding section) 42. The first track 41 extends substantially along a first direction in which the transmission device is arranged, the first direction being substantially opposite to or the same as the direction of motion of the charged particle beam P. The first end of the second track 42 is connected to the first track 41 via a connecting section 43, and the second end extends along a second direction, different from the first direction. That is, the guiding device 40 has at least two guiding directions, and the guiding direction of the second track 42 is different from that of the first track 41. This arrangement is advantageous for application in compact buildings. Figure 4In one embodiment, in a plane parallel to the ground where the first track is located, the projection of the line connecting the first and second ends of the second track 42 forms a first angle with the first track 41, such as 10° to 150°, preferably 30° to 90°; in a plane perpendicular to the ground where the first track is located, the projection of the line connecting the first and second ends of the second track 42 forms a second angle with the first track 41. The extension direction of the second track 42 can avoid other structures such as the support device 61 or beam splitter of the second transmission unit 12 and / or the third transmission unit 13; when the operating space in the first space R1 along the horizontal direction arranged along the transmission device 10 and the vertical direction perpendicular to the ground is limited, the limited operating space is efficiently utilized. In an alternative embodiment, the second track 42 may also be located in a plane perpendicular to the ground where the first track 41 is located. The first track 41 and the second track 42 are detachably connected by a connecting part 43, or they may be integrally formed with the first track 41 or the second track 42. When the connection between them is detachable, the connecting part 43 can be a linkage, a latch, a snap-fit, or other structure that can securely engage the first track 41 and the second track 42, allowing the first transmission part 11 to slide smoothly from the first track 41 to the second track 42. The extension length of the first track 41 limits a certain safe distance, allowing operators to perform disassembly and debugging operations while remaining outside this safe distance. The second track 42 is at least partially located in the first space R1. Preferably, the second track 42 may further include at least two track segments 421 and 422. One end of track 421 is fixedly connected to the first track 41 via a connecting part 43. Track 422 is preferably hinged to the other end of track 421 via a hinge structure 45 and has two positions. The first position is a position that maintains a normal guiding state with the fixed track 421. The second position is a buffer position that can form an angle relative to the first position after being subjected to force during transmission. Subsequently, track 422 can automatically rotate back to the first position. This flexible track segment is beneficial to improving the overall flexibility and adaptability of the transmission device, protecting the entire system and equipment from rigid damage during transmission operations, and facilitating subsequent alignment operations. The downward-extending end of the second track 42 faces a radiation shielding device 50. The second track 42 may not be connected to the radiation shielding device, or it may be at least partially connected. Preferably, the movable track 422 of the second track 42 is rotatably aligned with the radiation shielding device.Since neutrons are generated within the beam shaper 30, the surrounding materials are most severely activated. The guiding device is located in the core reaction space R2, which has a relatively high radiation level. Therefore, the material selection for the guiding device must be carefully considered. To avoid excessively rapid depletion due to severe activation, elements with small neutron interaction cross-sections or short half-lives (less than 1 year) of the radioactive isotopes produced after neutron activation are typically selected. For example, over 90% (by weight) of the material in the irradiated portion of the guiding device is composed of at least one of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, Ca, and Ti. In this embodiment, if aluminum alloy is selected as the guiding material, aluminum has a short half-life after neutron activation, only 2.2 minutes; while traditional steel materials, rich in elements such as iron, cobalt, and nickel, have longer half-lives after neutron activation, such as cobalt-60 with a half-life of 5.27 years. Using aluminum alloy significantly reduces the radioactivity derived from neutron activation within a limited time, not only reasonably suppressing the dose caused by secondary radiation but also facilitating future equipment dismantling. The guiding device can be made of aluminum-magnesium alloy, carbon fiber composite material, glass fiber composite material, or a combination thereof. The radiation shielding device 50 includes an openable shielding plate 51, a receiving opening 52 formed by opening the openable shielding plate 51, a moving part 53, and an internal buffer device 54. The radiation shielding device 50 is made of radiation shielding material, including but not limited to radiation shielding made of lead (Pb). The radiation shielding device 50 has a wheeled moving part 53 at the bottom and an openable shielding plate 51 made of shielding material on the top as an openable part. The opening and closing of the openable shielding plate includes, but is not limited to, rotation, sliding, and other opening methods. When replacing the neutron generator, the operator controls the radiation shielding device 50 to move from the external space into the first space R1, position it at a preset location, and dock with the lower end of the second track 42. In this embodiment, a positioning part 55 is also preset on the ground to stop and position the radiation shielding device 50. In alternative embodiments, the moving part can be a pre-laid track or trolley, the positioning part can be one or more markers, stops or recessed structures, etc.; the driving device can be a hook, rope or cylinder, linear motor, chain drive structure, etc. controlled at a certain distance, and can also be controlled by wired or wireless signals; the radiation shielding device 50 includes, but is not limited to, cubes, spheres, etc.

[0066] Figure 3 The embodiment illustrates a replacement operation for the first transmission unit 11 with the neutron generation unit 20 at its end. The shielding facility 300 is open, and shielding doors 301 and / or 302 are open, connecting the first space R1 and the second space R2. The operator manually or automatically opens the openable shielding plate 51 of the radiation shielding device 50, checks the connection and position of the first track 41, the second track 42, and the radiation shielding device 50, and performs the replacement operation. (In conjunction with...) Figure 1 The transmission device 10 also includes a third transmission section 13. The first transmission section 11 and the second transmission section 12 are separated, and the second transmission section 12 and the third transmission section 13 are also separated. By removing the second transmission section 12, the overall length of the transmission device 10 is changed, thus making room for the first transmission section 11, which has a neutron generating section 20 at one end, to move out along the track. During the separation process, the third transmission section can preferably also be kept in a vacuum state. In an alternative embodiment, the second transmission section 12 can be fixedly connected to one end of the third transmission section 13, and the second transmission section 12 is designed as a structure such as a bellows or telescopic tube (not shown) to leave room for replacement. From the drive device 70 (see reference) Figure 7The power of the beam stunner separates the first transmission section 11, which has a neutron generating section 20 at its end, from the beam shaper 30. The first transmission section 11 moves onto the second track 42 through the opening formed by the shielding doors 301 and 302 along the first direction of the transmission device 10 on the first track 41. Under the action of gravity or track power, it continues to move along the direction of the second track 42. The first transmission section 11 enters the receiving opening 52 formed by the opening of the openable shielding plate 51. At this time, the first transmission section 11 is located at the second position L2. The interior of the radiation shielding device 50 includes at least one buffer device 54, which can buffer the sliding first transmission section 11 and the neutron generating section 20. After the first transmission section 11 comes into contact with the buffer device 54 in the cavity of the radiation shielding device 50, the buffer device undergoes elastic deformation, so that the first transmission section 11 and the neutron generating section 20 are stationary and accommodated in the radiation shielding device 50, avoiding damage to the first transmission section and the neutron generating section from the radiation shielding device due to rapid collision. In an alternative embodiment, when the second track 42 of the neutron capture therapy system 100 is short, a third track 44 may be included. One end of the third track 44 is connected to the second track 42 via a connecting part 43, and the other end is installed inside the radiation shielding device 50. In a more preferred embodiment, the second track 42 is hinged with a flexible rotating track 422 structure. This structure facilitates linkage alignment with the third track 44 inside the radiation shielding device 50 without rigid connection to the connecting part 43, thus saving installation steps. A buffer cylinder 54 is provided next to the bottom of the third track 44. This cylinder can deform in the direction of movement of the first transmission part 11 and the neutron generating part 20 to apply opposite forces, thus stopping and protecting the first transmission part 11 and the radiation shielding device 50. Under the action of the buffer cylinder 54, the first transmission part 11 and the neutron generating part 20 are safely stopped inside the radiation shielding device 50. In an alternative embodiment, the buffer device may also be a spring or other mechanical buffer structure, or an elastic material such as a rubber pad or an airbag. It is worth noting that the section where the first transmission section 11 and the neutron generation section 20 preferentially enter the radiation shielding device 50 is the opposite side of the neutron generation section 20 containing radioactive consumables. That is, when the recycling operation is finally completed, the neutron generation section 20 containing radioactive consumables is closer to the containment opening 52 of the radiation shielding device 50 and stays at the far end of the buffer device.This recycling direction design prioritizes improving the recyclability of the neutron generator 20 containing radioactive consumables. Since the neutron generator 20, located within the beam shaper 30, is made of relatively reactive lithium metal (Li) and / or beryllium metal (Be), and its coating thickness is only about 100 micrometers, it is easily damaged by impact. Therefore, the recycling direction where the neutron generator 20 finally enters the containment opening and remains at the far end of the buffer device is safer than other recycling directions and less prone to damage, significantly improving the reusability of the neutron generator containing radioactive consumables and avoiding unnecessary radiation leakage after impact. Simultaneously, the direction of the neutron generator 20 does not need to be switched, eliminating the need for cumbersome direction-switching structures, saving space, and preventing radiation leakage caused by switching structure malfunctions. The radiation shielding device 50 can also achieve a vacuum environment or be filled with inert gas to physically isolate it from the outside air, thereby improving the safety and reliability of transporting and storing the first transmission unit 11 and the neutron generator 20, or other highly reactive elements.

[0067] Figure 5 and 6 A guide device 40' according to another embodiment of the present invention is shown. The guide device 40' includes a first track 41' and a second track 42'. The first track 41' extends substantially along a first direction in which the transmission device is arranged. One end of the second track 42' is connected to the first track 41' via a connecting portion 43'. The second track 42' defines a second direction of upward extension. The top of the first space R1 includes an operable movable mechanical structure 53' that supports the radiation shielding device 50' to achieve spatial positioning through three-dimensional calculation or manual adjustment, moves to a preset three-dimensional positioning mark, and connects to the second track 42'. The bottom of the radiation shielding device 50' has an openable shielding plate 51', which can be operablely opened to form a receiving opening 52'. The inner side of the radiation shielding device 50' has a third track 44', which is operablely aligned and connected to the other end of the second track 42' via the connecting portion 43'. Drive unit 70 (reference) Figure 7 Power is transmitted via rails to move the first transmission unit 11 and the neutron generator 20 from the first position L1, along the first rail 41' and through the second rail 42', to the third rail 44' within the radiation shielding device 50, where they are fixed and positioned, reaching the second position (not shown). The connection 43' between the second rail 42' and the third rail 44' is operably disengaged, and the openable shielding plate 51' is operably closed, completing the retrieval of the first transmission unit 11 and the neutron generator 20. In an alternative embodiment, the moving mechanical structure 53' may also be located at different positions, such as the side wall of the first space R1, and the second rail may be arranged in any direction other than the extension direction of the first rail (i.e., the direction in which the transmission device is arranged), depending on the actual situation.

[0068] Figure 7 A schematic diagram of the first transmission section 11 of the transmission device 10 is shown. The neutron capture therapy system 100 includes, in addition to the drive structure 70, a cooling device 80 for cooling the neutron generating section 20 and a detection device 90. The drive structure 70 is powered and further includes a drive frame 72 supporting the first transmission section 11 and the neutron generating section 20, and a power structure 71. The power structure 71 includes, but is not limited to, electronic or pneumatic linkages, robots and their structures, robotic arms, etc., combined with... Figure 1 and Figure 2 This invention aims to address the situation where, after the neutron generator 20 separates from the beam shaper 30, and the environmental radiation dose in the second space R2 is high, the operator leaves the radiation exposure space R2 unattended. Therefore, the drive structure is remotely operated by the operator from a radiation-free safe area R via the main control panel 400. In this remote operation, the power structure 71 of the drive device 70 drives the drive frame 72 carrying the first transmission unit 11 and the neutron generator 20 to move. This causes the drive frame 72 to separate the first transmission unit 11 and the neutron generator 20 from the beam shaper 30 and move them along the guide device. When the first transmission unit 11 and the neutron generator 20 reach the radiation shielding device 50, the pneumatic lever of the buffer device 54 is driven by the main control panel 400 to achieve safe retrieval. Then, the operable shielding plate 51 of the radiation shielding device 50 is closed by operating the main control panel 400, thus completing the retrieval operation. (Refer to...) Figure 3In an alternative embodiment, the shielding facility 300 and its auxiliary doors can also be remotely controlled via wired or wireless means through the main control panel 400. The cooling device 80 includes a pipe located at the end of the transmission device 10 and in planar contact with the neutron generator 20, and two cooling pipes arranged vertically along the direction of the transmission device. These two vertically arranged cooling pipes may be partially housed within a buffer body. The cooling pipes have a U-shaped structure and are connected to an external cooling system. The neutron generator 20 is heated by high-energy-level accelerated irradiation, and the cooling medium flowing through the cooling pipes efficiently cools the neutron generator 20. In the illustrated embodiment, the detection device 90 can be a temperature sensor, including detection lines arranged along the transmission device 10 and connected to the control terminal, used to detect the real-time temperature of the cooling device. In alternative embodiments, the detection device may also be a charged particle sensor for detecting the charged particle beam before the reaction between the first transmission unit 11 and the neutron generating unit 20; it may also be a vacuum pressure sensor for detecting the vacuum level of the first transmission unit 11; or it may be a neutron detector for detecting the neutrons produced after the nuclear reaction. The detection device 90 includes, but is not limited to, electronic sensors, proximity sensors, capacitive sensors, transducers, or other types of sensors. When the first transmission unit 11 is in the first position L1, the external cooling system of the cooling pipe is connected, and cooling is possible; the detection line and the control terminal are connected, enabling real-time monitoring and data transmission and feedback. When the first transmission unit 11 is in the second position L2, the external cooling system of the cooling pipe is disconnected, and the connection between the detection line and the control terminal is disconnected. The cooling device, the partially disconnected pipe, and the partially disconnected line of the detection device are all located in the first transmission unit and move together with the first transmission unit 11 to the second position for recycling and replacement.

[0069] Figure 8 The drive frame 72 of the drive structure 70 is shown to include at least one set of rollers, and in a preferred embodiment, it includes at least two sets of rollers 73 and 74. Figure 1 , Figure 4 , Figure 6 and Figure 8The guiding device 40 also includes a track base 46 and multiple track sections. Preferably, the first track, the second track 41, and 42 are laid on the track base 46. The two sets of rollers 73 and 74 on the drive frame 72 have different rolling planes, and preferably, their rolling directions are also different. It should be noted that the rolling directions of the rollers in a single set are consistent. The roller set 73 and the track section above the base is a combination of rollers and convex tracks, while the roller set 74 and the track base 46 are a combination of rollers and concave tracks. These different combination modes allow them to roll on different planes, and their rolling directions are perpendicular to each other. This reliably ensures the high stability of the entire guiding operation in two dimensions. It also greatly contributes to the matching and adaptability of the tracks when switching tracks later, and even the flexibility of selecting one or two sets of rollers. In a preferred embodiment, the second track 42, which is flexibly rotatable, only has a track base 46. Therefore, when switching to the track 422 segment, only the roller assembly 74 engages with the concave track base 46 of the track 422 segment, while the roller assembly 73 disengages from the convex track of the track 422 segment to enter the already aligned third track 44 inside the radiation shielding device 50. The third track 44 is then aligned with the concave track base 46 of the track 422 segment. Considering the large weight of the first transmission unit 11 and the neutron generating unit 20, and that the rollers and concave or convex tracks used in this embodiment are employed for guidance and transmission, in addition to considering metals that are not easily activated by neutrons and have short half-lives, the load-bearing capacity and wear resistance of the guiding device must also be considered. Therefore, simply choosing aluminum alloy or aluminum-magnesium alloy may not be able to withstand the large weight of the first transmission unit 11 and the neutron generating unit 20, as well as the wear of the rollers on the guiding track. Therefore, the guiding device further considers selecting a wear-resistant material with high rigidity, and coating its surface with a film that prevents neutron activation and can withstand roller wear, in order to reduce the probability of activation and extend the service life of the track. Through cross-sectional stress analysis of multiple sections of the guiding track, it is found that the load and deformation borne by the curved section of the track are much greater than those of the straight section. The first track 41 and the second track 42 are partially straight sections, while the remaining part of the second track 42 needs to form a curved section due to the change in guiding direction; therefore, this section requires high material rigidity and wear resistance. Based on the above research and analysis, in an alternative embodiment, the straight guiding part located in the core reaction space R2 near the beam shaper 30 is considered to be made of aluminum alloy, magnesium-aluminum alloy, and / or a material with a wear-resistant coating. The curved guiding part is considered to be made of a material with high rigidity, such as stainless steel, and is considered to be coated with a film that prevents neutron activation and can withstand roller wear, or refer to... Figure 9a and 9bA radiation shield 47, shaped to fit the guiding structure, is constructed using radiation-shielding materials such as boron-containing PE and / or boron-containing resin to shield against neutrons or photons. During operation of the radioactive irradiation system, this shield 47 remains constantly covering the surface of the easily activated material in the guiding device. When replacing radioactive consumables, at which point the radioactive irradiation system stops operating, the shield 47 can be removed, and the guiding track can be used normally. By selecting various materials in sections along the guiding track as needed, the service life of the guiding device can be significantly extended, improving its reliability.

[0070] Figure 10 This is a schematic diagram of another embodiment for replacing the neutron generator. This embodiment shows the shielding facility 300 between the first space R1 and the second space R2 in a closed state. When the shielding door 301 and / or shielding door 302 are closed, the first space R1 and the second space R2 are physically separated, and the guiding device 40 enters the second space R2 from the first space R1 through the opening 303 of the shielding facility. Preferably, in this state, the operator is located in the first space R1, enabling safe operation to recover the first transmission unit and the neutron generator under conditions of less radiation. Figure 3 Following the same steps as in the embodiment, the operator prepares for the replacement work, disassembles the second transmission section 12, and checks the connection and position of the first track 41, the second track 42, and the radiation shielding device 50. In this embodiment, preferably, the operator uses their hand or other object to pass through the opening 303 to remove the cooling device 80 and the detection device 90 (see reference 50) from the first transmission section 11. Figure 7 The corresponding pipeline is removed and cut off. Preferably, there may be other pneumatic devices (not shown) on the first transmission section 11. These are also removed and cut off. The first transmission section 11 with the neutron generator is then moved to a third position (not shown) near the opening 303 of the shielding facility 300, while keeping the end with the neutron generator always in the second space R2. (From the drive device 70 (see reference...)) Figure 7 The first power source, such as the force from the drive unit 70 or the pulling force from the operator, is applied to the first transmission unit 11. The first transmission unit 11, which contains the neutron generator, thus undergoes a small initial movement, separating from the beam shaper 30. At this point, due to the exposure of the neutron generator, the radiation value of the second space R2 is much higher than that of the first space R1. It should be noted that if the neutron generator is separated manually, the operator should take appropriate protective measures and quickly evacuate to a safe area R. Figure 7The power from the first transmission unit 11 or the pulling force from the operator is used as a second power source. Under the action of the second power, the first transmission unit 11 moves a relatively large distance along the first direction of the transmission device 10 on the first track 41, passing through the opening 303 on the shielding facility 300 which is kept closed without any obstruction, and moves to the second track 42 located in the first space R1. Under the action of gravity or track power, it continues to move along the direction of the second track 42 to the second position L2. The opening 303 of the shielding facility 300 can be circular, square, or even irregular in shape. Preferably, it is adapted to the shape of the cross-section of the first transmission unit 11 with the neutron generator and the guide device. This ensures that the first transmission unit 11 with the neutron generator can pass smoothly through the shielding facility 303 and continue to move to the recovery position after the water, electricity and gas auxiliary pipelines are disconnected, while minimizing radiation leakage. The opening 303 of the shielding facility 300 may also be provided with a shielding cover (not shown) made of radiation shielding material. During normal operation, the shielding cover does not shield the opening 303. When replacing the neutron generator using the above steps, after the operator disassembles and disconnects the auxiliary pipeline and removes the first transmission unit 11 with the neutron generator, the opening 303 is shielded to the maximum extent by the movable shielding cover, so as to further reduce the radiation leakage from the second space R2 to the first space R1.

[0071] Reference Figures 11a to 11e The shielding facility 300 between the first space R1 and the second space R2 is in a closed state. When the shielding door 301 and / or the shielding door 302 are closed, the first space R1 and the second space R2 are physically separated, and the guiding device 40 enters the second space R2 from the first space R1 through the opening 303 of the shielding facility. Figure 10 Preferably, an auxiliary door 304 is provided at the opening 303 of the shielding facility 300, similar to the movable shielding cover described above. The auxiliary door 304 includes a fixing member 305 and a movable member 306. The movable member 306 is divided into left and right sections, respectively located on the fixing member 305 fixed to the shielding doors 301 and 302. When the movable member 306 is closed, it has at least one opening 303' in the middle. In this embodiment, the shape of at least one opening 303' of the auxiliary door 304 generally matches the shape of the first transmission section 11, the guiding device 40, and the corresponding pipeline structure, vacuum valve, etc., provided at the opening 303', so as to reduce radiation leakage from the opening 303' when the shielding facility 300 and the auxiliary door 304 are closed for neutron beam irradiation therapy. The shape includes, but is not limited to, elliptical, rhomboid, square, or even irregular shapes. Figures 11a to 11eWhen retrieving the first transmission unit and neutron generator, only the auxiliary door 304 can be opened while the shielding facility 300 remains closed. After replacing the first transmission unit and neutron generator, the auxiliary door 304 can be closed. Alternatively, when retrieving the first transmission unit and neutron generator, the shielding facility 300 can be opened, the first transmission unit and neutron generator can be replaced, and then the shielding facility 300 and the auxiliary door 304 can be closed. The auxiliary door 304 is made of a material with good shielding performance. Its movable part 306 can open or close along the preset path of the fixing part 305 while keeping the shielding doors 301 and 302 closed. This flexible, small, and shape-fitting auxiliary door design is beneficial for further reducing radiation dose during neutron beam irradiation therapy. At the same time, when the shape or structure of the first transmission unit or guiding device needs to be adjusted, only the auxiliary door needs to be adjusted or customized, without having to spend manpower and resources to modify the bulky and large shielding door, and also saving energy for moving large shielding doors.

[0072] In one embodiment, the neutron generator recovery method specifically includes the following steps:

[0073] S1: Move the radiation shielding device to the second space;

[0074] S2: The first transmission section is kept in a vacuum state, and the second transmission section between the first transmission section and the third transmission section is removed;

[0075] S3: Dismantle auxiliary pipelines related to water, electricity, and gas, such as cooling pipes and testing lines;

[0076] S4: Push the radiation shielding device to the position of the ground positioning piece, lock the stop, and fix the radiation shielding device. At this time, the opening and closing parts of the radiation shielding device will open.

[0077] S5: Remove the radiation protection cover from the guide device, connect and align the second guide part with the third guide part inside the radiation shielding device;

[0078] S6: Operators exit the secondary space to a safe area;

[0079] S7: Trigger the drive device switch on the main control panel, and the drive power structure will push out the drive frame with the first transmission part and neutron generation part installed, and move it along the guide device into the radiation shielding device.

[0080] S8: Triggers the control switch of the opening and closing part of the radiation shielding device on the main control panel, so that the opening and closing part is closed to prevent radiation leakage;

[0081] S9: Cover the guiding device with a radiation shield;

[0082] S10: Unlock the ground positioning device and push the radiation shielding device out of the second space;

[0083] S11: Install the new neutron generating unit and complete the connection of the first, second and third transmission units;

[0084] S12: Connects auxiliary pipelines related to water, electricity, and gas, such as cooling pipes and testing lines, and debugs transmission devices.

[0085] The neutron capture therapy system disclosed in this application is not limited to the content described in the above embodiments and the structure shown in the accompanying drawings. For example... Figure 5 and Figure 6 The embodiments described herein are all applicable to the operation steps of replacing the neutron generator in the open or closed state of the shielding facility; the structure for detachably connecting the transmission device can be fixed by a quick-clamp structure or by bolts and nuts, and some transmission devices are configured as retractable corrugated tubes, folding tubes, and telescopic tubes, etc. Furthermore, the methods for driving the first transmission unit to detach and move from the beam shaping body, controlling the radiation shielding device to move to a predetermined position, opening and closing the openable shielding component, and docking and separating the track are not limited to manual or gravity-induced movements, but can also be remote or near-range operation by operators and automatic control. Any obvious changes, substitutions, or modifications made to the material, shape, and position of the components based on this application are within the scope of protection claimed in this application.

Claims

1. A neutron capture therapy system, characterized in that: The neutron capture therapy system includes an accelerator for generating a charged particle beam, a transmission device for transmitting the charged particle beam, a neutron generating section that reacts with the charged particle beam to generate a neutron beam, a beam shaper for energy spectrum modulation of the neutron beam, and a guiding device. The transmission device includes at least a first transmission section and a second transmission section, wherein the first transmission section and the second transmission section are detachably connected, and the neutron generating section is disposed in the first transmission section. The neutron capture therapy system also includes a movable radiation shielding device for accommodating the first transmission section and the neutron generating section guided by the guiding device. The radiation shielding device includes an openable member. When the openable member is opened, the radiation shielding device forms a receiving opening. The neutron generating section enters the receiving opening later than the first transmission section along the guiding device. When the first transmission section and the neutron generating section are accommodated in the radiation shielding device, the neutron generating section is closer to the receiving opening, and the first transmission section is farther away from the receiving opening.

2. The neutron capture therapy system as described in claim 1, characterized in that: The guiding device includes a first guiding part and a second guiding part, wherein the first guiding part and the second guiding part have different guiding directions.

3. The neutron capture therapy system as described in claim 2, characterized in that: The guiding device further includes a third guiding part, which is fixedly housed within the movable radiation shielding device.

4. The neutron capture therapy system as described in claim 3, characterized in that: The second guide portion and the third guide portion are detachably connected, or can be flexibly aligned and connected.

5. The neutron capture therapy system as described in claim 1, characterized in that: The radiation shielding device is made of radiation shielding material. When the openable part is closed, the radiation shielding device forms a sealed shielding space to prevent radiation leakage from the neutron generating part.

6. The neutron capture therapy system as described in claim 1, characterized in that: The movable radiation shielding device further includes a buffer device, which is capable of elastic deformation after the first transmission part comes into contact with the buffer device to avoid damage to the first transmission part and / or the radiation shielding device.

7. The neutron capture therapy system as described in claim 4, characterized in that: The movable radiation shielding device also includes a positioning system that enables the radiation shielding device to move to a preset position, allowing the second guide and the third guide to dock.

8. The neutron capture therapy system as described in claim 5, characterized in that: Once the neutron generating unit has completely entered the movable radiation shielding device, the opening and closing mechanism is closed.

9. The neutron capture therapy system as described in claim 8, characterized in that: When the closable part of the movable radiation shielding device is closed, it can achieve an internal vacuum environment or fill with inert gas, while simultaneously achieving physical isolation from the outside air.

10. The neutron capture therapy system as described in claim 5, characterized in that: The neutron capture therapy system also includes a control unit, which can remotely control the opening and closing of the closable component of the movable radiation shielding device via a wired or wireless connection.

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