Neutron capture therapy system and method for recovering neutron generating part thereof

Abstract

The neutron capture therapy system includes an accelerator that generates a charged particle beam, a transport device that transports the charged particle beam, a neutron generating unit that reacts with the charged particle beam to generate a neutron beam, a beam shaper that performs energy spectrum adjustment on the neutron beam, and a guide device, the transport device includes at least a first transport unit and a second transport unit detachably connected to the first transport unit, the first transport unit includes a first position and a second position, the guide device guides the first transport unit and the neutron generating unit to move from the first position to the second position, and when the first transport unit is in the first position, the neutron generating unit provided in the first transport unit is accommodated in the beam shaper, and when the first transport unit is in the second position, the neutron generating unit provided in the first transport unit is separated from the beam shaper. In this way, a safe, reliable and stable solution is provided for maintaining a safe distance between the operator and the neutron generating unit, reducing the contact time between the operator and radiation, and recovering the neutron generating unit.

Description

[Technical field]

[0001] One aspect of the present invention relates to a radioactive radiation irradiation system, and in particular to a neutron capture therapy system. Another aspect of the present invention relates to a method for recovering radioactive consumables of a radioactive radiation irradiation system, and in particular to a method for recovering a neutron generating unit of a neutron capture therapy system. [Background technology]

[0002] With the development of atomic science, radiation therapy such as cobalt 60, linear accelerator, and electron beam has become one of the main means of cancer treatment. However, traditional photon or electron therapy kills tumor cells due to the limitations of the physical conditions of radiation itself, and also damages many normal tissues in the beam path. In addition, because tumor cells have different degrees of sensitivity to radiation, traditional radiation therapy is not very effective in treating malignant tumors with high radiation resistance (e.g., glioblastoma multiforme, melanoma).

[0003] To reduce radiation damage to normal tissues surrounding tumors, the concept of targeted therapy in chemotherapy has been used in radiotherapy, and for tumor cells with high radiation resistance, radiation sources with high relative biological effectiveness (RBE), such as proton therapy, heavy particle therapy, and neutron capture therapy, are currently being actively developed. Among these, neutron capture therapy combines the above two concepts. For example, in boron neutron capture therapy, boron-containing drugs specifically collect in tumor cells, and when combined with highly precise neutron beam control, it provides a better cancer treatment option than conventional radiation.

[0004] In a neutron capture therapy system using an accelerator, a charged particle beam is accelerated by the accelerator, and the charged particle beam is accelerated to an energy sufficient to overcome the Coulomb repulsion between atomic nuclei of the neutron generating part in the beam shaper, and a nuclear reaction occurs with the neutron generating part to generate neutrons. In the process of generating neutrons, the neutron generating part is irradiated with a high-power accelerated charged particle beam, and the temperature of the neutron generating part rises significantly, which affects the service life of the neutron generating part. In order to generate neutrons stably, it is necessary to collect and maintain the old neutron generating part, and replace it with a new neutron generating part, so the neutron generating part needs to be replaced regularly. Since a large amount of radiation is inevitably present in the neutron generating part irradiated with a high-energy level accelerated charged particle beam, when the neutron generating part is replaced in a close distance, there is inevitably a potential risk of radiation safety unless there are sufficient protective or isolation measures. Summary of the Invention

[0005] A neutron capture therapy system according to one aspect of the present invention includes an accelerator that generates a charged particle beam, a transport device that transports the charged particle beam, a neutron generating unit having a radioactive consumable that reacts with the charged particle beam to generate a neutron beam, a beam shaper that performs energy spectrum adjustment on the neutron beam, and a guide device, wherein the transport device includes at least a first transport unit and a second transport unit, the first transport unit and the second transport unit are detachably connected, and the neutron generating unit is provided at an end of the first transport unit, The first transport section includes a first position and a second position, and the guide device can guide the first transport section to move from the first position to the second position, and when the first transport section is in the first position, the neutron generating section at the end of the first transport section is contained within the beam shaper and can react with the charged particle beam to generate neutrons, and when the first transport section is in the second position, the neutron generating section and the beam shaper are separated from each other, and in this case, the first transport section and the neutron generating section are in a replaceable state.

[0006] When the neutron generating unit having radioactive consumables is located in the beam shaper, the radiation shielding in the beam shaper can shield the radiation leaking from the neutron generating unit to avoid radiation exposure to the worker, and after the neutron generating unit is separated from the beam shaper, the neutron generating unit is exposed to the working space, shortening the working time of the worker and / or extending the working distance between the worker and the neutron generating unit, thereby realizing the prevention of radiation leaking from the neutron generating unit from being irradiated to the worker as much as possible during the process of the neutron generating unit being moved from the first position to the second position by the first transporter. According to the technical means of one aspect of the present invention, the guide device can quickly, stably and reliably guide the neutron generating unit to be retrieved from the first working position into the radiation shielding device at the second position, and during the operation process of replacing the neutron generating unit, the worker maintains a sufficient safety distance from the neutron generating unit and even has a working condition of being completely isolated, thereby effectively avoiding excessive radiation damage.

[0007] Preferably, the guide device includes a first guide part and a second guide part, and the guide directions of the first guide part and the second guide part are different. According to one embodiment of the present invention, when the available space in the operation room is narrow and limited, the first guide part of the guide device first guides the first transport part of the transport device to move along the first direction of the transport device arrangement and then enter the second guide part of the guide device, thereby avoiding some facilities and obstacles that may exist in the first direction, and such an arrangement is helpful to make the operation room smaller and more compact, improves the space utilization rate, and reduces the site area and construction costs.

[0008] Preferably, a projection of a connecting line between the first end and the second end of the second guide part onto a plane parallel to the ground in which the first guide part is located forms a first angle with the first guide part, and a projection of a connecting line between the first end and the second end of the second guide part onto a plane perpendicular to the ground in which the first guide part is located forms a second angle with the first guide part.

[0009] Preferably, the second guide portion includes at least two guide rails, one of which is a fixed rail removably connected to the first guide portion and another of which is a movable rail rotatably connected to the fixed rail.

[0010] Preferably, the movable rail is connected to the fixed rail by a hinge connection structure and has two positions, when the movable rail is in the first position, the movable rail maintains a normal guiding state together with the fixed rail, and after the movable rail is subjected to a force, when the movable rail is in the second position, the movable rail moves forming a certain angle with respect to the fixed rail and can then automatically return to the first position.

[0011] Preferably, 90% or more (weight percent) of the material of the guide device is composed of at least one of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, Ca, and Ti.

[0012] Preferably, the first guide portion is selected from an aluminum alloy, a magnesium aluminum alloy, a carbon fiber composite material, a glass fiber composite material, or a combination thereof.

[0013] Preferably, the material selected for the second guide part may be the same as that for the first guide part, or may be a different material than that for the first guide part, for example stainless steel, a ferrous material.

[0014] Preferably, a radiation prevention coating may be applied to the surface of the second guide part, and a radiation prevention and removable protective cover may be added.

[0015] Preferably, the shape surface of the radiation prevention protective cover is adapted to the cross-sectional shape of the second guide part.

[0016] A neutron capture therapy system according to a second aspect of the present invention includes an accelerator that generates a charged particle beam, a transport device that transports the charged particle beam, a neutron generating section that reacts with the charged particle beam to generate a neutron beam, a beam shaper that adjusts the energy spectrum of the neutron beam, and a guide device, wherein the transport device includes at least a first transport section and a second transport section, the first transport section and the second transport section are detachably connected, and the neutron generating section is provided in the first transport section, and the neutron capture therapy system further includes a movable radiation shielding device that accommodates the first transport section and the neutron generating section guided by the guide device, and the radiation shielding device recovers both the first transport section that moves along the guide device and the neutron generating section at its end.

[0017] Preferably, the guide device includes a first guide portion and a second guide portion, and the first guide portion and the second guide portion have different guide directions.

[0018] Preferably, the guide device further includes a third guide part fixedly accommodated within the moveable radiation shielding device.

[0019] Preferably, the second guide part and the third guide part are removably connected or flexibly aligned and connected to facilitate guiding the first transport part of the transport device into the radiation shielding device.

[0020] Preferably, the radiation shielding device is made of a radiation shielding material and includes an openable / closable member, and when the openable / closable member is opened, the radiation shielding device forms an accommodation opening and a first transporting part of a transporting device enters the radiation shielding device from the accommodation opening, and when the openable / closable member is closed, the radiation shielding device forms a sealed shielded space to prevent radiation leakage from the neutron generating unit.

[0021] Preferably, the movable radiation shielding device further includes a buffer device, which is elastically deformed after the first transporter contacts the buffer device, and applies a force opposite to the moving direction of the first transporter after the elastic deformation, so that the first transporter is safely stopped in the radiation shielding device, thereby avoiding damage to the first transporter and / or the radiation shielding device. Furthermore, the neutron capture therapy system includes a positioning system that can move the radiation shielding device to a preset position to realize alignment and connection with the guide device. The positioning system can pre-mark the position based on means such as structure positioning, three-dimensional algorithm positioning, etc., so that the radiation shielding device can be moved to an ideal position to align with the guide device, so that the first transporter and the neutron generating unit at its end can be reliably collected in the radiation shielding device after moving to the end of the guide device.

[0022] Preferably, the movable radiation shielding device further includes a positioning system that can realize alignment and connection between the second guide part and the third guide part by moving the radiation shielding device to a preset position.

[0023] Preferably, the neutron generating unit enters the accommodation opening of the movable radiation shielding device after the first transport unit along the guide device, and the openable / closable member closes after the neutron generating unit has completely entered the movable radiation shielding device.

[0024] Preferably, after the openable and closable member of the movable radiation shielding device is closed, an internal vacuum environment or inert gas filling can be realized, and physical isolation from the outside air can be realized.

[0025] Preferably, the neutron capture therapy system further includes a control unit capable of realizing opening and closing of the openable member of the movable radiation shielding device by remote control via a wired or wireless connection.

[0026] A neutron capture therapy system according to a third aspect of the present invention includes an accelerator that generates a charged particle beam, a transport device that transports the charged particle beam, a neutron generating unit that reacts with the charged particle beam to generate a neutron beam, a beam shaper that performs energy spectrum adjustment on the neutron beam, and a guide device, the transport device including at least a first transport unit and a second transport unit, the first transport unit and the second transport unit being detachably connected, the neutron generating unit being provided in the first transport unit, and the first transport unit including a first position and a second position. The guide device can guide the first transport section to move from a first position to a second position, and when the first transport section is in the first position, the neutron generating section is contained within the beam shaper and can react with the charged particle beam to generate neutrons, and when the first transport section is in the second position, the neutron generating section and the beam shaper are separated from each other, and the neutron capture therapy system further includes a drive device that provides power to separate the first transport section from the beam shaper, move it out of the first position, and move it along the guide device.

[0027] Preferably, the neutron capture therapy system further includes a support device that stably supports the first transport section along an arrangement direction of the transport device.

[0028] Preferably, the guide device includes a first guide portion and a second guide portion, and the first guide portion and the second guide portion have different guide directions.

[0029] Preferably, the drive device includes a drive frame and a power structure, the drive frame mounting the first transport section and the neutron generating section, and the power structure providing a drive force.

[0030] Preferably, the neutron capture therapy system further includes a control unit capable of providing power for moving the first transport unit and the neutron generating unit between the first position and the second position by remotely controlling the power structure of the drive unit via a wired or wireless connection.

[0031] Preferably, the drive frame of the drive device includes at least one set of roller structures.

[0032] Preferably, 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] Preferably, the rolling planes of the two sets of rollers of said drive frame are different and perpendicular to each other.

[0034] Preferably, 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 realize transport movement, and one or two sets of rollers compatible with the structures of the concave and / or convex slide rails can be arbitrarily selected to realize rolling transport.

[0035] Furthermore, the neutron capture therapy system further includes a cooling device that cools the neutron generating unit and includes a cooling line, and when the first transport unit is in a first position, the cooling line is in a connected state and the cooling device performs cooling operation, and when the first transport unit is in a second position, the cooling line is in a blocked state and the cooling device cannot perform normal operation, and the cooling device is recovered and replaced together with the first transport unit.

[0036] Preferably, the neutron capture therapy system further includes a detection device including a detection circuit, and when the first transporter is in the first position, the detection device performs detection by being in a connected state, and when the first transporter is in the second position, the detection circuit cannot perform normal operation by being in a disconnected state, and the detection device is retrieved and replaced together with the cooling device, the neutron generating unit, and the first transporter. The "detection device" referred to here may be a charged particle sensor, or a device suitable for being attached to the first transporter, such as a vacuum pressure sensor and / or a neutron detector.

[0037] In a method for retrieving a neutron generating unit of the above-mentioned neutron capture therapy system according to a fourth aspect of the present application, the neutron capture therapy system further includes an auxiliary piping connected to the neutron generating unit or a first transport unit, and the method for retrieving the neutron generating unit includes the steps of disassembling the first transport unit and the second transport unit, disconnecting the auxiliary piping from the neutron generating unit, applying a first power to the first transport unit in which the neutron generating unit is provided, thereby separating the first transport unit from the beam shaper at a first position along a guide device, and applying a second power to the first transport unit in which the neutron generating unit is provided, thereby causing the first transport unit to move again along the guide device and stop until it reaches a retrieval position.

[0038] Preferably, the neutron capture therapy system further includes a shielding device having an opening, and when the shielding device is in a closed state, the first transport section passes through the opening.

[0039] Furthermore, the neutron generating portion is recovered through the opening when the shielding device is in a closed state.

[0040] Further, the shielding device is provided with an auxiliary door, which when closed, at least partially shields the opening of the shielding device and conforms to the outer shape of the first transport part, the guide device, and the auxiliary pipe provided at the opening of the shielding device. opening and a method for recovering the neutron generating portion is performed through the opening when the shielding device is in a closed state and the auxiliary door is in an open state.

[0041] Furthermore, the neutron capture therapy system further includes a radiation shielding device that houses the recovered neutron generating unit, and a first space and a second space partitioned by the shielding device, the guide device is provided with a radiation prevention protective cover, the neutron generating unit is located in the first space, and the second transport unit is located in the second space, and a method of recovering the neutron generating unit includes moving the radiation shielding device to the second space before applying a first power to the first transport unit in which the neutron generating unit is provided, and and a step of fixing the radiation shielding device, a step of opening an opening / closing member of the radiation shielding device, and a step of removing a radiation prevention protective cover on the guide device. The method further includes a step of applying a second power to the first transporting part in which the neutron generating part is provided, and then moving the first transporting part along the guide device into the radiation shielding device, a step of closing the opening / closing member of the radiation shielding device, a step of covering the guide device with the radiation prevention protective cover, and a step of pushing the radiation shielding device out of the second space.

[0042] In the method for recovering the neutron generator of the neutron capture therapy system according to a fifth aspect of the present application, the neutron capture therapy system further includes a shielding device that is kept closed during recovery, and an opening is provided in the shielding device, and the method for recovering the neutron generator includes the steps of: blocking a cooling line connected to the neutron generator through the opening of the shielding device; applying a first power to a first transporter provided with the neutron generator, so that the first transporter separates from the beam shaper at a first position along the guide device and moves close to the opening of the shielding device; and applying a second power to the first transporter provided with the neutron generator, so that the first transporter moves again along the guide device and stops until it reaches the recovery position. Preferably, the method for recovering the neutron generator further includes the steps of blocking the cooling line and blocking the detection circuit and other connection paths of the detection device. If the neutron generating unit and the beam shaping body are separated, exposure of the neutron generating unit will result in large radiation, so by keeping the shielding device closed during retrieval, workers can perform the replacement work of the neutron generating unit only through the opening on the shielding device, significantly reducing radiation leakage in the work environment and improving work safety.

[0043] A method for retrieving a neutron generating unit of the above-mentioned neutron capture therapy system according to a sixth aspect of the present application includes the steps of keeping the shielding device closed during the retrieval operation, providing an auxiliary door in the shielding device and maintaining the auxiliary door closed when the system is operating, opening the auxiliary door and blocking the cooling line connected to the neutron generating unit through an opening on the auxiliary door when the system is stopped and it is necessary to replace the neutron generating unit, applying a first power to a first transporting unit provided with the neutron generating unit, so that the first transporting unit separates from the beam shaping body at a first position along the guide device and moves close to the opening of the shielding device, applying a second power to the first transporting unit provided with the neutron generating unit, so that the first transporting unit moves again along the guide device and stops until it enters a retrieval position in the radiation shielding device, and closing the auxiliary door. Preferably, the shape of the opening on the auxiliary door generally corresponds to the shape of the first transport section, guide device and associated piping structure, vacuum valve, etc., provided at the location of the opening, and the shape includes, but is not limited to, elliptical, diamond, square, and even irregular shapes.

[0044] In the embodiment of the present application, the time that the worker is exposed to the strong radiation object environment during the process of replacing the radioactive consumables is shortened, and a relatively safe operating distance is provided between the worker and the neutron generating unit, so that during the operation process of replacing the radioactive consumables, the worker can maintain a sufficient safe distance between the radioactive consumables and the neutron generating unit, and even have a working condition of complete isolation, thereby reducing the contact between the worker and radiation and reducing the radiation safety risk. At the same time, the neutron capture therapy system belonging to the radioactive radiation irradiation system in the embodiment of the present application has a compact structure and is easy to install, and when the operating space is limited, it can efficiently utilize the actual space and location, reduce the site area and construction costs, and provide a reliable, stable and safe recovery solution for the neutron generating unit. [Brief description of the drawings]

[0045] [Figure 1]1 is a plan schematic diagram of a neutron capture therapy system according to one embodiment of the present invention. [Diagram 2] FIG. 2 is a perspective view of a neutron capture therapy system according to one embodiment of the present invention, showing a first transport portion of a transport device in a first position and a radiation shielding device in a closed state. [Diagram 3] FIG. 2 is a perspective view of a neutron capture therapy system according to one embodiment of the present invention, showing a first transport portion of the transport device in a second position and a radiation shielding device in an open state. [Figure 4] 2 is a top schematic view of a guide device of the neutron capture therapy system according to the embodiment of FIG. 1. [Diagram 5] FIG. 2 is a plan schematic view of a neutron capture therapy system according to another embodiment of the present invention. [Figure 6] 6 is a perspective view of a guide device of the neutron capture therapy system according to another embodiment of FIG. 5. [Figure 7] FIG. 2 shows a schematic plan view of a first transport part of the transport device. [Figure 8] 1 is a schematic cross-sectional view of a group of rollers of a drive frame of a drive device of a neutron capture therapy system according to one embodiment of the present invention. [Figure 9a-9b] 1 is a schematic diagram of the use of a radiation prevention protective cover of a guide device of a neutron capture therapy system according to one embodiment of the present invention, and a schematic cross-sectional view thereof. [Figure 10] FIG. 2 is a perspective view of a neutron capture therapy system according to one embodiment of the present invention, showing a schematic diagram of recovering a first transport section and a neutron generating section when the shielding device is in a closed state. [Figure 11a] ~ [Figure 11e] 1 is a schematic diagram of an auxiliary door of a radiation shielding device of a neutron capture therapy system according to one embodiment of the present invention and its open and closed states. DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS

[0046] Neutron capture therapy has been increasingly applied in recent years as an effective means of cancer treatment, among which boron neutron capture therapy has become the most common. Neutrons used in boron neutron capture therapy can be supplied by a nuclear reactor or an accelerator. The embodiment of the present application takes accelerator boron neutron capture therapy as an example, and the base assembly of accelerator boron neutron capture therapy generally includes an accelerator for accelerating charged particles (e.g., protons, deuterium nuclei, etc.), a neutron generator having radioactive consumables, a heat removal system, and a beam shaper. Neutrons are generated by the action of accelerated charged particles and a metal neutron generator, and an appropriate nuclear reaction is selected based on the required neutron yield and energy, the magnitude of the accelerated charged particle energy and current that can be provided, the physical chemistry of the metal neutron generator, and other characteristics. The nuclear reactions that are always considered are 7 Li(p, n) 7 Be and 9 Be(p, n) 9 B, both of which are endothermic reactions, and the energy thresholds of these two nuclear reactions are 1.881 MeV and 2.055 MeV, respectively. The ideal neutron source for boron neutron capture therapy is epithermal neutrons at the keV energy level, so theoretically, bombarding a lithium metal neutron generator with protons with an energy slightly above the threshold can generate neutrons with relatively low energy, which can be used clinically without much moderation, but in order to generate a sufficiently large neutron flux, the cross section of action between the two neutron generators, lithium metal (Li) and beryllium metal (Be), and the protons with the threshold energy is not high, a relatively high energy proton is generally used to initiate the nuclear reaction.

[0047] A neutron generator with an ideal radioactive consumable has the following characteristics: high neutron yield, the energy distribution of the generated neutrons is close to the epithermal neutron energy region (described in detail below), does not generate too much radiation, is safe, inexpensive, easy to operate, and is resistant to high temperatures, but in reality it is impossible to find a nuclear reaction that meets all the requirements. In the embodiment of the present application, a neutron generator made of lithium metal is used. However, as is well known to those skilled in the art, the material of the neutron generator can be made of other metal materials other than the metal materials mentioned above.

[0048] The requirements for the heat removal system depend on the nuclear reaction selected, e.g. 7 Li(p, n) 7 In the case of Be, the low melting point and low thermal conductivity of the metallic neutron generating part (lithium metal) limits the requirements for the heat removal system. 9 Be(p, n) 9 In the embodiment of the present application, 7 Li(p, n) 7 It uses the nuclear reaction of Be. As can be seen from this, the temperature of the neutron generator, which is irradiated with a high-energy level accelerated charged particle beam, inevitably rises significantly, which affects the service life of the neutron generator.

[0049] Therefore, the neutron capture therapy system belonging to the radioactive radiation irradiation system inevitably has the problem of replacing the neutron generating unit with radioactive consumables. In order to solve this problem and reduce the contact between the operator and radiation as much as possible, the neutron capture therapy system according to the embodiment of the present application stably and reliably recovers the neutron generating unit, limits the operation space along the direction of the transport device and the vertical direction of the neutron generating unit, effectively utilizes the space, avoids the interference and obstruction of the operation space of the same horizontal height in the direction of the transport device, reduces the acceleration device for protons in the transport device, reduces the structure of the operation space, and reduces the overall site area and construction costs.

[0050] To solve the problem of replacing a neutron generating unit having radioactive consumables as described above, and to minimize contact between workers and radiation, an embodiment of the present application provides a neutron capture therapy system.

[0051] Since the main radiation to the worker is due to radiation generated by the nuclear reaction that occurs after the charged particle beam irradiates the neutron generating unit having a radioactive consumable, the purpose of the embodiment of the present application is to describe the removal of the neutron generating unit that needs to be retrieved after reaching the end of its useful life after the nuclear reaction occurs, and is not related to the installation of a new neutron generating unit. In addition, the directional terms such as up, down, horizontal, and vertical mentioned in the embodiment of the present invention are used to describe the positional relationship between members according to the directions shown in the drawings for ease of explanation, and do not limit the substantial absolute directions.

[0052] Hereinafter, preferred embodiments of a neutron capture therapy system will be described with reference to the drawings.

[0053] 1 and 2 are a plan view and a perspective view of a neutron capture therapy system according to an embodiment of the present invention, and as shown in Fig. 1 and Fig. 2, the neutron capture therapy system 100 includes a transport device 10, a neutron generating unit 20 having radioactive consumables, a beam shaper 30, a guide 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, and the first space R1 includes an accelerator 200 that generates a charged particle beam P, a part of the transport device 10 that transports the charged particle beam P, a support device that supports the transport device, and a detection device. The transport direction of the charged particle beam P coincides with the arrangement direction of the transport device 10, the transport device 10 penetrates the first space R1 and the second space R2, the second space R2 is the core reaction space of the whole system, the relative radiation amount is large, and the second space R2 is physically blocked from the first space R1 by the shielding device 300, so that the radiation amount of the first space R1 is within a relatively safe and controllable range. The shielding device 300 includes at least one shielding door 301 and / or 302, and further includes at least one opening 303 through which the transport device 10 penetrates when the shielding device 300 is in a closed state. In the illustrated embodiment, the inside of the transport device 10 is in a vacuum state, and includes at least a first transport section 11 and a second transport section 12, and the first transport section 11 and the second transport section 12 are detachably connected. The shape of the first transport section and the second transport section is preferably hollow tubular, and their cross-sectional shapes include, but are not limited to, circular, elliptical, diamond, square, irregular, etc., and the shape of at least one opening of the shielding device 300 may be matched to the shape of the transport section passing through the opening, including, but not limited to, circular, elliptical, diamond, square, irregular, etc. In the process of replacing radioactive consumables and disassembling the transport device, the first transport section and the second transport section of the transport device can preferably maintain a vacuum state. The second space R2 includes the first transport section 11 of the transport device 10, a neutron generating section 20 provided at one end of the transport device 10 to generate a neutron beam N by reacting with the charged particle beam P, and a beam shaper 30 for adjusting the energy spectrum of the neutron beam N.The transport device 10 transports the charged particles P accelerated by the accelerator 200 from the first space R1 to the neutron generating section 20 in the second space R2, and the accelerator 200 accelerates the charged particles P to energy sufficient to overcome the nuclear force of the target and transports them to the neutron generating section 20. 7 Li(p, n) 7 A Be nuclear reaction is generated to generate neutrons, which form a neutron beam N that exits from the beam exit. The beam shaper 30 is generally large in volume and not suitable for moving, and is fixedly installed inside the wall in an embedded form, and includes a moderator, a thermal neutron absorber, a radiation shield, etc. (none of which are shown in the drawings). The main material of the moderator is generally selected from aluminum fluoride and any one or more mixed materials of lithium fluoride, aluminum, lead fluoride, aluminum oxide, calcium fluoride or magnesium fluoride, some of which are highly brittle and therefore have high requirements for the addition and installation process. The moderator moderates the neutrons generated from the neutron generating unit 20 to an epithermal neutron energy region, and the deviated neutrons are conducted to the moderator by the reflector to improve the intensity of the epithermal neutron beam. The thermal neutron absorber absorbs thermal neutrons to avoid excessive dose during treatment causing unnecessary damage to normal tissues in shallow layers. The radiation shield blocks leaked neutrons and photons to reduce the dose of normal tissues in non-irradiated areas. Neutron capture therapy system 100 further includes a third space R3 as an irradiation chamber, where a neutron beam that meets the conditions can exit the beam outlet and enter the irradiation chamber for use.

[0054] 2 shows a state in which the shielding device 300 between the first space R1 and the second space R2 is open, and when the shielding door 301 and / or the shielding door 302 are opened, the first space R1 communicates with the second space R2. Referring to FIG. 1, the neutron capture therapy system 100 includes a support device 60 and / or 61 that stably supports the transport device 10 along the arrangement direction of the transport device. The support device 60 is provided at the bottom of the first transport section 11, and one end of the first transport section 11 where the neutron generating section 10 is provided is accommodated in the beam shaper 30, and the first transport section 11 is at the first position L1. In an alternative embodiment, the support device 60 can be further provided in a different orientation, such as above and to the side of the first transport section 11, to support it.

[0055] As shown in Fig. 1 and Fig. 2, the guide device 40 is provided between the support device 60 and the first transport section 11 (see Fig. 4), and the neutron capture therapy system 100 further includes a drive device 70 (see Fig. 7), and the guide device 40 may include a first rail (first guide section) 41 and a second rail (second guide section) 42. The first rail 41 basically extends along a first direction of the transport device arrangement, the first direction is basically opposite to or the same as the moving direction of the charged particle beam P, the first end of the second rail 42 is connected to the first rail 41 by a connecting section 43, and the second end extends along a second direction, the second direction is different from the first direction, that is, the guide device 40 has at least two guide directions, and the second rail 42 and the first rail 41 have different guide directions, and such an arrangement is conducive to application in a compact building. As shown in FIG. 4, in the embodiment, the projection of the connection line between the first end and the second end of the second rail 42 on a plane parallel to the ground where the first rail is located forms a first angle with the first rail 41, for example, 10° to 150°, preferably 30° to 90°, and the projection of the connection line between the first end and the second end of the second rail 42 on a plane perpendicular to the ground where the first rail is located forms a second angle with the first rail 41. The extension direction of the second rail 42 can avoid other structures such as the support device 61 or the beam splitter of the second transport section 12 and / or the third transport section 13, and efficiently utilize the limited operable space when the operation space along the horizontal direction of the transport device 10 arrangement in the first space R1 and the vertical direction perpendicular to the ground is limited. In an alternative embodiment, the second rail 42 may be located in a plane perpendicular to the ground where the first rail 41 is located. The first rail 41 and the second rail 42 are detachably connected by a connecting part 43, and may be a structure integrally formed with the first rail 41 or the second rail 42. When the connection structure between them is detachable, the connecting part 43 may be a structure such as a connecting rod, a locking catch, a concave-convex buckle, etc., and the first rail 41 and the second rail 42 are firmly locked together, thereby realizing the first transport part 11 to smoothly slide from the first rail 41 to the second rail 42. The extension length of the first rail 41 limits a certain safety distance, so that the operator can perform operations such as disassembly and debugging while remaining outside the safety distance.The second rail 42 is at least partially located in the first space R1, and preferably the second rail 42 may further include at least two parts of rails 421 and 422, in which one end of the rail 421 is fixedly connected to the first rail 41 by a connecting part 43, and the rail 422 is preferably hingedly connected to the other end of the rail 421 by a hinge connection structure 45, and has two positions, the first position is a position that maintains a normal guiding state with the fixed rail 421, and the second position is a buffer position that can form an angle with the first position after receiving a force during the transportation process, and then the rail 422 can automatically rotate and return to the first position, and the flexible rail part is helpful to improve the toughness and flexibility of the entire transportation device, and when realizing the transportation operation, can protect the entire system and device from rigidity damage, and is helpful to the subsequent alignment operation. The lower end of the second rail 42 extending downward faces the radiation shielding device 50, and the second rail 42 may not be connected to the radiation shielding device or may be at least partially connected to it, and preferably, the movable rail 422 of the second rail 42 is rotatably aligned with the radiation shielding device. Since neutrons are generated in the beam shaper 30, the surrounding materials are most seriously activated, and the guide device portion is provided in the core reaction space R2 where the radiation amount is relatively large, so the material selection of the guide device should also be careful, and in order to avoid rapid loss due to serious activation, the material is generally made of an element with a small neutron action cross section or a short half-life (less than one year) of the radioisotope generated after activation by neutrons, for example, 90% (weight percent) or more of the material of the guide device in the part with large radiation is made 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 the guide material is selected as an aluminum alloy, the half-life of aluminum is short after being activated by neutrons, only 2.2 minutes, while elements such as iron, cobalt, and nickel, which are abundant in conventional steel materials, are long after being activated by neutrons, for example, the half-life of cobalt-60 is 5.27 years. If an aluminum alloy is used, the radioactivity induced by the activation of neutrons is greatly reduced within a limited time, and in addition to rationally suppressing the dose due to secondary radiation, it is more favorable for future dismantling of the device. The material of the guide device may further be an aluminum-magnesium alloy, a carbon fiber composite material, a 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 and closing the openable shielding plate 51, a moving member 53, and a buffer device 54 located therein. The radiation shielding device 50 is made of a radiation shielding material, including, but not limited to, a radiation shielding device made of lead (Pb). The bottom of the radiation shielding device 50 has a wheel-type moving member 53, and the top is covered with an openable shielding plate 51 made of a shielding material as an openable member. The openable shielding plate can be opened and closed by, but is not limited to, rotating, sliding, and other opening methods. When replacing the neutron generating unit, the worker controls the radiation shielding device 50 to move from the external space to the first space R1, be positioned at a preset position, and be aligned and connected to the lower end of the second rail 42. In this embodiment, a positioning member 55 that can stop and position the radiation shielding device 50 is further provided on the ground in advance. In alternative embodiments, the moving member may be a pre-installed rail or cart, the positioning member may be one or more marks, stoppers or recessed structures, the driving device may be in the form of a hook, rope or cylinder, a linear motor, a chain-type transmission structure or the like controlled at a certain distance, and may be controlled by a wired or wireless signal at the same time, and the radiation shielding device 50 may be in the form of, but is not limited to, a cube, a sphere, etc.

[0056] The embodiment of FIG. 3 shows a state in which replacement work is performed on the first transport unit 11 having the neutron generating unit 20 at its end, and the shielding device 300 is opened, and the shielding door 301 and / or the shielding door 302 are opened, and in this case, the first space R1 and the second space R2 are communicated. The worker manually or automatically opens the openable shielding plate 51 of the radiation shielding device 50, inspects the connection and positional status of the first rail 41, the second rail 42 and the radiation shielding device 50, and performs the replacement work. As shown in FIG. 1, the transport device 10 further includes a third transport unit 13, and the first transport unit 11 and the second transport unit 12 are disassembled, and the second transport unit 12 and the third transport unit 13 are disassembled, and the second transport unit 12 is removed to change the length of the entire transport device 10, and thus reserves an evacuation space for removing the first transport unit 11 having the neutron generating unit 20 at its end along the rail. During the disassembly process, the third transport section may preferably maintain a vacuum state. In an alternative embodiment, the second transport section 12 may be fixedly connected to one end of the third transport section 13 and designed as a structure (not shown) such as a corrugated pipe or a telescopic pipe to reserve the operation space for replacement. The power from the driving device 70 (see FIG. 7) separates the first transport section 11 having the neutron generating section 20 at its end from the beam shaper 30, and the first transport section 11 moves to the second rail 42 by passing through the opening formed by opening the shielding door 301 and the shielding door 302 along the first direction of the transport device 10 arrangement on the first rail 41, and continues to move along the direction of the second rail 42 under the action of gravity or rail power, and the first transport section 11 enters the receiving opening 52 formed by opening the openable shielding plate 51, in this case the first transport section 11 is in the second position L2. The interior of the radiation shielding device 50 includes at least one buffer device 54 that can provide a buffering effect for the first transporting section 11 and the neutron generating section 20 sliding downward. After the first transporting section 11 enters the cavity of the radiation shielding device 50 and comes into contact with the buffer device 54, the buffer device elastically deforms, so that the first transporting section 11 and the neutron generating section 20 are stopped and accommodated within the radiation shielding device 50, thereby avoiding damage caused by rapid collision between the first transporting section and the neutron generating section and the radiation shielding device.In an alternative embodiment, when the length of the second rail 42 of the neutron capture therapy system 100 is short, it may further include a third rail 44, one end of which may be connected to the second rail 42 by a connecting part 43 as well, and the other end is attached to the inside of the radiation shielding device 50, and in a more preferred solution, a flexibly rotating rail 422 structure is hinged to the second rail 42, which serves to interlock and align with the third rail 44 inside the radiation shielding device 50, and does not need to be rigidly connected to the connecting part 43, thus eliminating the installation step. A buffer cylinder 54 is provided near the bottom of the third rail 44, which can act to stop and protect the first transport part 11 and the radiation shielding device 50 by generating deformation in the moving direction of the first transport part 11 and the neutron generating part 20 and applying an opposite acting force, and the first transport part 11 and the neutron generating part 20 stay safely inside the radiation shielding device 50 due to the action of the buffer cylinder 54. In alternative embodiments, the buffer device may further be a different mechanical buffer structure, such as a spring, or an elastic material, such as a rubber pad, an airbag, etc. Note that the part where the first transport section 11 and the neutron generating section 20 preferentially enter the radiation shielding device 50 is on the opposite side to the neutron generating section 20 with the radioactive consumables, i.e., when the retrieval operation is finally completed, the neutron generating section 20 with the radioactive consumables is closer to the receiving opening 52 of the radiation shielding device 50 and remains at the distal end of the buffer device. Such a recovery direction design focuses on improving the cyclic utilization rate of the neutron generating unit 20 with radioactive consumables. The neutron generating unit 20 located in the beam shaping body 30 is made of more active lithium metal (Li) and / or beryllium metal (Be), and its own coating film is only about 100 microns thick and is easily destroyed after being hit. Therefore, the recovery direction in which the neutron generating unit 20 finally enters the accommodation opening and remains at the distal end of the buffer device is safer than other recovery directions and is less likely to damage the neutron generating unit, greatly improving the overlapping utilization rate of the neutron generating unit with radioactive consumables and avoiding unnecessary radiation leakage after being hit. At the same time, there is no need to switch the direction of the neutron generating unit 20, and no complicated direction switching structure is required, further saving space and avoiding radiation leakage caused by failure of the switching structure.The inside of the radiation shielding device 50 can further be made into a vacuum environment or filled with an inert gas, thereby realizing a physical isolation function from the outside air, thereby improving the safety and reliability of transporting and storing the first transport section 11, the neutron generating section 20, and other highly reactive elements.

[0057] 5 and 6 show a guide device 40' according to another embodiment of the present invention, the guide device 40' includes a first rail 41' and a second rail 42', the first rail 41' extends basically along the first direction of the transport device arrangement, one end of the second rail 42' is connected to the first rail 41' by a connecting part 43', and the second rail 42' defines a second direction extending upward. The top of the first space R1 includes an operable moving mechanical structure 53', the moving mechanical structure 53' supports the radiation shielding device 50' to realize spatial positioning by three-dimensional calculation or artificial adjustment, moves to a preset three-dimensional positioning mark, and is connected to the second rail 42', the bottom of the radiation shielding device 50' includes an openable and closable shielding plate 51' that can be operably opened to form a receiving opening 52', and the inside of the radiation shielding device 50' includes a third rail 44' that can be operably aligned and connected to the other end of the second rail 42' by a connecting part 43'. The driving device 70 (see FIG. 7) transports the power by the rail, and removes the first transporting section 11 and the neutron generating section 20 from the first position L1, transports them along the first rail 41' through the second rail 42' to the third rail 44' in the radiation shielding device 50, and stops and fixes them until they reach the second position (not shown). The second rail 42' and the connection part 43' at the third rail 44' are operably disengaged, and the openable shielding plate 51' is operably closed to complete the recovery operation of the first transporting section 11 and the neutron generating section 20. In alternative embodiments, the moving mechanical structure 53' may be at a different position, such as the side wall of the first space R1, and the second rail may be arranged in any other direction different from the extending direction of the first rail (i.e., the arrangement direction of the transporting device) according to the actual situation.

[0058] 7 shows a schematic diagram of the first transport section 11 of the transport device 10, and the neutron capture therapy system 100 includes a drive structure 70, and further includes a cooling device 80 for cooling the neutron generating section 20 and a detection device 90. The drive structure 70 has a power and further includes a drive frame 72 for carrying the first transport section 11 and the neutron generating section 20, and a power structure 71, and the power structure 71 includes, but is not limited to, electronic or pneumatic connecting rods, robots and their structures, robot arms, etc., as shown in FIG. 1 and FIG. 2, the purpose of the present invention is that after the neutron generating section 20 and the beam shaping body 30 are separated, when the environmental radiation dose in the second space R2 is high, the operator leaves the radiation exposure space R2 to enter an unmanned operation situation, and the operator remotely controls the drive of the related power structure by operating the overall control panel 400 in the radiation-free safety area R. The operator operates the overall control panel 400 in the radiation-free safety area R to realize remote operation, and the power structure 71 of the drive device 70 drives the drive frame 72 carrying the first transporter 11 and the neutron generator 20 to move, and the drive frame 72 drives the first transporter 11 and the neutron generator 20 to separate from the beam shaper 30 and move along the guide device, and when the first transporter 11 and the neutron generator 20 move to the radiation shielding device 50, the overall control panel 400 drives the pneumatic lever of the buffer device 54 to realize safe recovery, and further operates the overall control panel 400 to realize the closing of the openable shielding plate 51 of the radiation shielding device 50, thereby completing the recovery operation. As shown in FIG. 3, in an alternative embodiment, the shielding device 300 and the auxiliary door on the shielding device can also be remotely controlled by wire or wirelessly through the overall control panel 400. The cooling device 80 includes a pipe located at the end of the transportation device 10 and in contact with the plane of the neutron generating unit 20, and two cooling pipes arranged vertically along the arrangement direction of the transportation device, and the two cooling pipes arranged vertically may be partially provided in the moderator, and the cooling pipes have a U-shaped structure and are connected to an external cooling system. The neutron generating unit 20 is subjected to high-energy level accelerated irradiation, causing its temperature to rise and generate heat, and the cooling medium flows through the cooling pipes to efficiently cool the neutron generating unit 20.In the illustrated embodiment, the detection device 90 may be a temperature sensor, and includes a detection circuit disposed along the transport device 10 and connected to the control end to detect the real-time temperature of the cooling device. In an alternative embodiment, the detection device may be a charged particle sensor to detect the status of the charged particle beam before the reaction between the first transport section 11 and the neutron generating section 20 occurs, a vacuum pressure sensor to detect the vacuum status of the first transport section 11, or a neutron detector to detect the status of the neutrons generated after the nuclear reaction occurs. The detection device 90 includes, but is not limited to, an electronic sensor, a proximity sensor, a capacitance sensor, a transducer, or other types of sensors. When the first transport section 11 is in the first position L1, the cooling line and the line of the external cooling system are in communication with each other, and cooling can be realized, and the detection circuit and the line of the control end are in a connected state, and real-time monitoring and data transmission and feedback can be realized. When the first transport section 11 is in the second position L2, the cooling line and the cooling line of the external cooling system are disconnected, and the connection line of the detection circuit and the control end are disconnected. The cooling device and the partially blocked pipeline, and the partially blocked line of the detection device are all provided in the first transport section and moved together with the first transport section 11 to the second position to be retrieved and replaced.

[0059] Fig. 8 shows that the drive frame 72 of the drive structure 70 includes at least one set of rollers, and in a preferred embodiment, includes at least two sets of rollers 73, 74. As shown in Figs. 1, 4, 6 and 8, the guide device 40 further includes a rail base 46 and multiple stages of rails, and preferably, the first rail and the second rail 41, 42 are laid on the rail base 46. The rolling planes of the two sets of rollers 73 and 74 on the drive frame 72 are different, and preferably, their rolling directions are also different, while the rolling directions of the rollers in a single set are all maintained to be consistent. The roller group 73 and the rail section above the base are a combination of rollers and convex rails, and the roller group 74 and the rail base 46 are a combination of rollers and concave rails, and the different combination modes of the two roll on different planes and roll directions perpendicular to each other, which can reliably guarantee the high stability of the entire guiding work in two dimensions, greatly contributing to the consistency and adaptability of the rails when switching the subsequent rails, and even the flexibility of arbitrarily selecting one or two sets of rollers. In a preferred embodiment, the flexibly rotatable rail 422 structure of the second rail 42 is only provided with the rail base 46, so that when switching to the rail 422 section, only the roller group 74 engages with the guide of the concave rail base 46 of the rail 422 section, and the roller group 73 disengages from the guide of the convex rail of the rail 422 section, so that the third rail 44 enters the already aligned inside the radiation shielding device 50, and the third rail 44 engages with the concave rail base 46 of the rail 422 section to align it. Considering that the first transport section 11 and the neutron generating section 20 are heavy, and when the rollers in this embodiment are guided and transported using the method of engaging with concave or convex rails, in addition to considering metals that are not easily activated by neutrons and have a short half-life, it is necessary to comprehensively consider the load-bearing capacity and wear-resisting capacity of the guide device, so that a material selected solely from aluminum alloy or aluminum magnesium alloy may not be able to withstand the heavy weight of the first transport section 11 and the neutron generating section 20 and the wear of the rollers against the guide rail.Therefore, the guide device is designed to select a wear-resistant material with higher rigidity and to coat its surface with a coating that can prevent neutron activation and resist roller wear, thereby reducing the probability of activation and extending the service life of the rail. As can be seen by performing cross-sectional stress analysis on multiple parts of the guide rail, the load and deformation experienced by the rail cross section in the curved part are much larger than those of the straight rail, and the parts of the first rail 41 and the second rail 42 are straight rails, while the remaining part of the second rail 42 needs to form a curved part due to the change in the guide direction, so there is a high requirement for the rigidity and wear resistance of the material. According to the above research and analysis, in an alternative embodiment, the straight guide portion located in the core reaction space R2 and close to the beam shaper 30 is considered to select aluminum alloy, magnesium aluminum alloy and / or a material coated with a wear-resistant coating on its surface, and the curved guide portion is considered to select a material with high rigidity such as stainless steel, and is considered to be coated with a coating that can prevent neutron activation and can withstand roller wear on its surface; or, as shown in Figs. 9a and 9b, a radiation protection cover 47 with a shape-matching guide structure is manufactured using a radiation protection material such as a neutron or photon shielding material such as boron-containing PE and / or boron-containing resin, and during the operation of the radioactive irradiation system, the radiation protection cover 47 is always kept covered on the surface of the material that is easily activated in the guide device, and when replacing radioactive consumables, in this case, when the operation of the radioactive irradiation system is stopped, the radiation protection cover 47 can be removed and the guide rail can be used normally. By selecting a number of different materials for the rail of the guide device in stages according to demand, the service life of the guide device can be greatly extended and the reliability of its use can be improved.

[0060] 10 is a schematic diagram of another embodiment of replacing the neutron generating unit, which shows the case where the shielding device 300 between the first space R1 and the second space R2 is in a closed state, and when the shielding door 301 and / or the shielding door 302 are closed, the first space R1 and the second space R2 are physically blocked, and the guide device 40 penetrates from the first space R1 through the opening 303 of the shielding device into the second space R2. Preferably, in this state, the worker is located in the first space R1 and can safely operate under the condition of less radiation to retrieve the first transport unit and the neutron generating unit. As in the same steps in the embodiment of FIG. 3, the worker performs the preparation work for the replacement work, completes the removal of the second transport unit 12, and completes the inspection of the connection and position status of the first rail 41, the second rail 42 and the radiation shielding device 50. In this embodiment, preferably, the worker penetrates only the opening 303 with his hand or other object to dismantle and cut the piping corresponding to the cooling device 80 and the detection device 90 (see Figure 7) on the first transport section 11, and preferably, after the piping of other pneumatic devices (not shown) which may be present on the first transport section 11 is similarly dismantled and cut, the first transport section 11 with the neutron generating unit is moved to a third position (not shown) close to the opening 303 of the shielding device 300, and the one end where the neutron generating unit is provided is always maintained to be positioned within the second space R2. The power from the driving device 70 (see Figure 7) or the pulling force from the operator is applied to the first transport unit 11 as the first power, and the first transport unit 11 with the neutron generating unit generates a first movement with a small stroke, and separates and leaves the beam shaping body 30. In this case, due to the exposure of the neutron generating unit, the radiation value in the second space R2 is much higher than the radiation value in the first space R1. It should be noted that when the neutron generating unit is separated by artificial means, the operator should take appropriate protective measures and quickly evacuate to the safety area R.The power from the driving device 70 (see FIG. 7) or the pulling force from the operator is applied again as the second power, so that the first transport section 11 makes a second movement with a relatively large stroke along the first direction of the transport device 10 arrangement on the first rail 41 under the action of the second power, moves to the second rail 42 located in the first space R1 by completely passing through the opening 303 on the shielding device 300 maintained in the closed state without any hindrance, and continues to move to the second position L2 along the direction of the second rail 42 under the action of gravity or rail power. The shape of the opening 303 of the shielding device 300 may be circular, rectangular, or even irregular, etc., and preferably has a shape that is compatible with the cross section of the first transport section 11 with the neutron generator and the guide device, so that after the hydroelectric auxiliary piping of the first transport section 11 with the neutron generator is cut off, it can smoothly pass through the shielding device 303 and continue to move to the recovery position while ensuring the maximum reduction of radiation leakage. A shielding cover plate (not shown) made of a radiation shielding material may be further provided at the opening 303 of the shielding device 300, and when operating normally, the shielding cover plate does not shield the opening 303. When replacing the neutron generating unit in the above step, the worker dismantles and blocks the auxiliary piping, removes the first transport unit 11 with the neutron generating unit, and then uses the movable shielding cover plate to shield the opening 303 to the maximum extent, thereby further reducing the leakage of radiation from the second space R2 to the first space R1.

[0061] 11a-11e, the shielding device 300 between the first space R1 and the second space R2 is in a closed state, and when the shielding door 301 and / or the shielding door 302 are closed, the first space R1 and the second space R2 are physically blocked, and the guide device 40 penetrates from the first space R1 through the opening 303 of the shielding device into the second space R2. Referring to FIG. 10, preferably, an auxiliary door 304 is provided in the opening 303 of the shielding device 300, which is similar to the above-mentioned movable shielding cover plate, and the auxiliary door 304 includes a fixed member 305 and a movable member 306, and the movable member 306 is divided into two parts, left and right, and is located on the fixed member 305 fixed to the shielding doors 301 and 302 respectively, and has at least one opening 303' in the middle when the movable member 306 is closed. In this embodiment, the shape of at least one opening 303' of the auxiliary door 304 is generally adapted to the shape of the first transporter 11, the guide device 40, and the associated pipe line structure, vacuum valve, etc., provided in the opening 303', so as to reduce radiation leakage from the opening 303' when the shielding device 300 and the auxiliary door 304 are closed to perform neutron radiation therapy, and the shape includes, but is not limited to, an ellipse, a rhombus, a square, and even an irregular shape (FIGS. 11a to 11e). When performing the recovery work of the first transporter and the neutron generator, only the auxiliary door 304 is opened, the shielding device 300 is kept closed, and after replacing the new first transporter and the neutron generator, the auxiliary door 304 is closed, or when performing the recovery work of the first transporter and the neutron generator, the shielding device 300 is opened, and after replacing the new first transporter and the neutron generator, the shielding device 300 and the auxiliary door 304 are closed. The above-mentioned auxiliary door 304 is made of a material with high shielding performance, and its movable member 306 can open or close along a preset path of the fixed member 305 when the shielding doors 301 and 302 are kept closed. Such a flexible, compact and shape-matching auxiliary door design helps to further reduce the radiation dose when performing neutron beam radiation therapy; at the same time, when shape or structural adjustments appear in the first transport part or the guiding device, there is no need to consume manpower and material force to modify the heavy and large shielding door, but only needs to adjust or customize the auxiliary door, and also saves the energy of moving the large shielding door.

[0062] In one embodiment, the method for recovering the neutron generating portion specifically includes the following steps: Step S1 of moving the radiation shielding device to a second space; A step S2 of dismantling the second transport section between the first transport section and the third transport section while maintaining the vacuum in the first transport section; Step S3 of dismantling auxiliary pipes related to water and electricity, such as cooling pipes and detection circuits; Step S4 of pushing the radiation shielding device to the position of the ground positioning member, stopping and locking it, and fixing the radiation shielding device, and in this case, opening the opening and closing member of the radiation shielding device; Step S5: removing the radiation prevention protective cover on the guide device, and connecting and aligning the second guide part with the third guide part in the radiation shielding device; Step S6 in which the worker exits from the second space to a safety area; Step S7: triggering a switch of the driving device on the overall control panel, and pushing out the driving frame to which the first transport unit and the neutron generating unit are attached by the driving power structure, and moving it along the guide device into the inside of the radiation shielding device; Step S8: triggering a control switch of the opening / closing member of the radiation shielding device on the overall control panel to close the opening / closing member and prevent radiation leakage; Step S9 of covering the guide device with an anti-radiation protective cover; Step S10 of unlocking the ground positioning member and pushing the radiation shielding device out of the second space; Step S11 of installing a new neutron generating unit and completing the connection of the first, second and third transport units; and step S12 of connecting water / electricity related auxiliary piping such as cooling lines, detection circuits, etc., and debugging the transport device.

[0063] The neutron capture therapy system disclosed in the present application is not limited to the contents described in the above embodiments and the structures shown in the drawings. For example, the embodiments in Fig. 5 and Fig. 6 are both applied to the operation step of replacing the neutron generating unit when the shielding device is open or closed, and the structure for detachably connecting the transport device may be a structure fixed by a high-speed clamp structure or a structure fixed by bolts and nuts, and some of the transport devices are provided with an expandable corrugated tube, a folding tube, a telescopic tube, etc. In addition, the first transport unit is driven to move away from the beam shaping body, and the radiation shielding device is controlled to move to a predetermined position, and the manner of opening and closing, rail butting and separation of the openable and closable shielding member is not limited to manual or gravity movement, and may be remote or close-range operation by an operator and automatic control. Any obvious changes, substitutions or modifications to the material, shape and position of the components based on the present application are included in the scope of the claims of the present application.

Claims

1. An accelerator that generates a charged particle beam; a transport device for transporting the charged particle beam; a neutron generating unit that reacts with the charged particle beam to generate a neutron beam; A beam shaper for adjusting the energy spectrum of the neutron beam; A guide device; Including, the transport device includes at least a first transport section and a second transport section, the first transport section and the second transport section are detachably connected, the neutron generating section is provided on the first transport section, and the first transport section includes a first position and a second position, the guide device can guide the first transport section to move from the first position to the second position, when the first transport section is in the first position, the neutron generating section is accommodated in the beam shaper and can generate neutrons by reacting with a charged particle beam, and when the first transport section is in the second position, the neutron generating section and the beam shaper are separated from each other, The guide device includes a first guide portion and a second guide portion, The first guide portion extends along a first direction, a first end of the second guide portion is connected to the first guide portion; The second end of the second guide portion extends along a second direction, The second direction is different from the first direction, A neutron capture therapy system, characterized in that the guide device is capable of guiding the first transport section to move along the first direction and the second direction.

2. A neutron capture therapy system as described in claim 1, characterized in that the first direction is along the direction of movement of the charged particle beam.

3. A neutron capture therapy system as described in claim 2, characterized in that a line projected along the first direction onto a plane parallel to the ground forms a first angle with a line projected along the line connecting the first end and the second end of the second guide portion onto the plane parallel to the ground, and a line projected along the first direction onto a plane perpendicular to the ground forms a second angle with a line projected along the line connecting the first end and the second end of the second guide portion onto the plane perpendicular to the ground.

4. The neutron capture therapy system of claim 2 or 3, characterized in that the second guide portion includes at least a fixed rail and a movable rail, the fixed rail being removably connected to the first guide portion, and the movable rail being rotatably connected to the fixed rail.

5. The first transport unit provided with the neutron generating unit can be removed from the first position, a drive unit including a drive frame and a power structure; The neutron capture therapy system of claim 1 , wherein the drive frame carries the first transport section and the neutron generating section, and the power structure provides a drive force.

6. The neutron generating unit includes a movable radiation shielding device that houses the first transport unit and the neutron generating unit guided by the guide device. The guide device further includes a third guide portion, The neutron capture therapy system according to claim 2 or 5, characterized in that the third guide portion is fixedly accommodated within the movable radiation shielding device.

7. The second end of the second guide portion is connected to the third guide portion, The neutron capture therapy system of claim 6, wherein the movable radiation shielding device further includes a positioning system that can realize alignment and connection between the second guide portion and the third guide portion by moving and locking the movable radiation shielding device to a preset position.

8. The radiation shielding device includes an openable and closable member made of a radiation shielding material; When the openable member is opened, the radiation shielding device forms an accommodation opening, and the first transporting part of the transporting device first enters the radiation shielding device through the accommodation opening, and then the neutron generating part enters the radiation shielding device through the accommodation opening; The neutron capture therapy system according to claim 6, wherein when the openable and closable member is closed, the radiation shielding device forms a sealed shielded space to prevent radiation leakage from the neutron generating unit.

9. The movable radiation shielding device further includes a shock absorber. The neutron capture therapy system of claim 6, characterized in that the buffer device can elastically deform after the first transport section comes into contact with the buffer device to avoid damage to the first transport section and / or the radiation shielding device.

10. The neutron capture therapy system according to claim 6, further comprising a control unit capable of remotely controlling the driving device and / or the movable radiation shielding device via a wired or wireless connection.

11. 2. A method for recovering a neutron generating unit of a neutron capture therapy system according to claim 1, further comprising: an auxiliary pipe connected to the first transport unit provided with the neutron generating unit, disassembling the first transport unit and the second transport unit; Disconnecting the auxiliary pipe from the first transport section; applying a first power to the first transport section provided with the neutron generating section, thereby causing the first transport section to move away from the first position along the guide device and separate from the beam shaper; applying a second power to the first transport unit provided with the neutron generating unit, so that the first transport unit moves again along the guide device and stops until it reaches a recovery position; A method for recovering a neutron generating unit, wherein the first direction is along a direction of movement of the charged particle beam.

12. The method for recovering a neutron generating unit according to claim 11, characterized in that the neutron capture therapy system further includes a shielding device having an opening, and when the shielding device is in a closed state, the first transport section penetrates the opening.

13. The method for recovering a neutron generating portion according to claim 12, characterized in that the recovery is performed through the opening when the shielding device is in a closed state.

14. The method for recovering a neutron generating unit according to claim 12, characterized in that the shielding device is provided with an auxiliary door, which at least partially shields the opening of the shielding device when closed and has an opening that matches the outer shapes of the first transport section, the guide device, and the auxiliary piping provided at the location of the opening of the shielding device, and the method for recovering the neutron generating unit is performed through the opening when the shielding device is in a closed state and the auxiliary door is in an open state.

15. The neutron capture therapy system further includes a radiation shielding device that houses the recovered neutron generating unit, and a first space and a second space that are partitioned by the shielding device, the guide device is provided with a radiation prevention protective cover, the neutron generating unit is located in the first space, and the second transport unit is located in the second space, and a method of recovering the neutron generating unit includes the steps of: before applying a first power to the first transport section in which the neutron generating section is provided; moving the radiation shielding device into the second space and fixing it according to a preset position; Opening an opening / closing member of the radiation shielding device; removing the anti-radiation protective cover on the guide device; After applying a second power to the first transport section in which the neutron generating section is provided, moving the first transport part along the guide device into the radiation shielding device; Closing an opening / closing member of the radiation shielding device; covering the guide device with the radiation prevention protective cover; The method for recovering a neutron generating portion according to claim 12, further comprising: pushing the radiation shielding device out of the second space.

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