Radioactive material transfer system and transfer method

Abstract

The present application relates to a radioactive material transfer system and transfer method. The radioactive material transfer system includes: a first radiation shielding device at least configured to accommodate a radioactive material; a second radiation shielding device at least configured to store the radioactive material; and a transfer device configured to transfer the radioactive material located in the first radiation shielding device into the second radiation shielding device. By transferring the radioactive material from the first radiation shielding device to the second radiation shielding device by the transfer device for storage, the personnel are protected from radiation contamination, thereby improving the safety of transfer operations.

Description

Technical Field

[0001] The present invention relates to the technical field of operations in radioactive sites, and particularly to a radioactive material transfer system and transfer method.Background

[0002] Common radioactive sites, such as those in medical, industrial, agricultural, and scientific research fields including neutron therapy, petroleum exploration, field prospecting, instrument measurement, neutron radiography, nuclear facilities, and radiation breeding, often contain radioactive materials and inevitably emit large amounts of radiation. Due to the radioactive hazards of radioactive materials in the radioactive sites, during the replacement, handling, transfer and storage of the radioactive materials for transportation or other purposes, operators who manually replace the radioactive materials in a close range without adequate protective or isolation measures will suffer health damage. In an exemplary radioactive site, such as a neutron capture therapy system in radiotherapy therapy, a neutron generation unit irradiated by a high-energy accelerated charged particle beam will reach the end of its service life after a certain period of use. To stably generate neutrons, the old neutron generation unit needs to be recovered, transferred, and stored at a designated location-for example, transferred from a temporary storage device to a safer storage device for designated storage, with centralized monitoring, maintenance, and management. As a radioactive material with high radioactivity, the old neutron generation unit exposes operators to a high radiation dose rate during recovery, transfer, and designated storage. Special consideration must be given to external exposure protection and special treatment to minimize the dose received by the operators.

[0003] In order to reduce the transfer difficulty of the radioactive material and personnel exposure, improve the safety of transfer of the radioactive material, and control the radiation dose level of on-site operators, it is necessary to design a compact, highly automated, easy, quick, and high-safety radioactive material transfer system and transfer method.Summary

[0004] In view of this, it is necessary to provide a radioactive material transfer system and transfer method targeting the radiation safety hazards existing during the transfer of a radioactive material in a radioactive site.

[0005] In a first aspect, the present application discloses a radioactive material transfer system. The radioactive material transfer system includes: a first radiation shielding device at least configured to accommodate a radioactive material; a second radiation shielding device at least configured to store the radioactive material; and a transfer device configured to transfer the radioactive material loin the first radiation shielding device into the second radiation shielding device.

[0006] The radioactive material located in the first radiation shielding device is transferred into the second radiation shielding device by the transfer device for the transfer and storage of the radioactive material.

[0007] In one embodiment, the radioactive material transfer system is used in a neutron capture therapy system, the neutron capture therapy system including: an accelerator configured to generate a charged particle beam; a transmission device configured to transmit the charged particle beam generated by the accelerator, the transmission device including at least a first transmission portion and a second transmission portion, where the first transmission portion is detachably connected to the second transmission portion; a neutron generation unit disposed at the first transmission portion and movable together with the first transmission portion, the neutron generation unit being configured to react with the charged particle beam to generate a neutron beam; and a beam shaping assembly configured to adjust an energy spectrum of the neutron beam; where the first radiation shielding device is at least configured to accommodate the neutron generation unit, and the transfer device is configured to transfer the neutron generation unit in the first radiation shielding device into the second radiation shielding device.

[0008] In one embodiment, the transfer device include a base and a moving member, the moving member being operatively movable relative to the base. The moving member is controlled to move relative to the base such that the moving member can reach a position of the first radiation shielding device and a position of the second radiation shielding device to transfer the radioactive material.

[0009] In one embodiment, the transfer device further includes a first actuator, where the first actuator is movably disposed on the moving member and is configured to obtain or release the radioactive material, and at least in a first direction, the first actuator can be moved relative to the base together with the moving member, the first actuator can move together with the moving member to a respective position of the first radiation shielding device and a respective position of the second radiation shielding device. The moving member moves to drive the first actuator to move between the respective position of the first radiation shielding device in which the action of picking up the radioactive material is performed and the respective position of the second radiation shielding device in which the action of releasing the radioactive material is performed, to transfer the radioactive material, where the respective positions refer to positions such as above and diagonally above.

[0010] In one embodiment, the first actuator includes a first actuating member configured to obtain or release a radioactive material, and a first movable member connected to the moving member, where the first movable member can drive the first actuating member to move. The first movable member enables the first actuating member to pick up the radioactive material when the first movable member moves to the first radiation shielding device, and the first movable member enables the first actuating member to release the radioactive material into the second radiation shielding device when the first movable member moves to the second radiation shielding device.

[0011] In one embodiment, at least in a second direction, the first movable member can drive the first actuating member to move relative to the moving member to enable a position of the first actuating member relative to the first radiation shielding device and / or the second radiation shielding device to be adjusted to transfer the radioactive material from the first radiation shielding device to the second radiation shielding device. In the second direction, the first movable member drives the first actuating member to move such that the first actuating member moves toward or away from the first radiation shielding device and the second radiation shielding device, to enable the first actuating member to obtain or release the radioactive material.

[0012] In one embodiment, the radioactive material transfer system further includes a radiation isolator and a second actuator, where the second actuator is movably disposed on the moving member and is configured to obtain or release the radiation isolator, and at least in the first direction, the second actuator can be moved together with the moving member to a respective position of the radiation isolator and a respective position of the second radiation shielding device. In this configuration, the second actuator picks up the radiation isolator and then moves to the second radiation shielding device in the first direction to transfer the radiation isolator to the second radiation shielding device for isolation of the radioactive material.

[0013] In one embodiment, the second actuator includes a second actuating member and a second movable member, where the second actuating member can obtain or release the radiation isolator, the second movable member is disposed on the moving member, and the second movable member can drive the second actuating member to move. In this configuration, the second movable member can drive the second actuating member to move, the second actuating member picks up the radiation isolator and can then transfer the radiation isolator into the second radiation shielding device for isolation of the radioactive material.

[0014] In one embodiment, at least in the second direction, the second movable member can drive the second actuating member to move relative to the moving member to enable a position of the second actuating member relative to the second radiation shielding device and / or the radiation isolator to be adjusted to transfer the radiation isolator to the second radiation shielding device. The second movable member drives the second actuating member to move in the second direction such that the second actuating member can move toward or away from the radiation isolator and the second radiation shielding device to transfer the radiation isolator into the second radiation shielding device.

[0015] In one embodiment, the radiation isolator include a support structure configured to form a protective space to protect a surface of the radioactive material, facilitating the protection and positioning of a protruding structure on the surface of the radioactive material.

[0016] In one embodiment, the radiation isolator has a greater structural thickness near the radioactive material and a smaller structural thickness away from the radioactive material.

[0017] In one embodiment, the radiation isolator includes a plurality of gradient thicknesses.

[0018] In one embodiment, the first radiation shielding device includes a first accommodating cavity that can accommodate the radioactive material / neutron generation unit, the second radiation shielding device includes a second accommodating cavity that can accommodate the radioactive material / neutron generation unit, and the radiation isolator has a greater structural thickness near an opening of the first accommodating cavity or an opening of the second accommodating cavity, and a smaller structural thickness away from the opening of the first accommodating cavity or the opening of the second accommodating cavity. In one embodiment, the second radiation shielding device includes a second openable member, and the radioactive material transfer system further includes a third actuator configured to open or close the second openable member. In this configuration, the third actuator can be moved together with the moving member to the respective position of the second radiation shielding device and then performs the action of opening or closing the second openable member.

[0019] In one embodiment, the third actuator includes a third actuating member configured to open or close the second openable member, and a third movable member movably disposed on the moving member, where at least in the first direction, the third movable member can drive the third actuating member to move together with the moving member to the respective position of the second radiation shielding device. The third movable member, when moving together with the moving member, can drive the third actuating member to move to the second radiation shielding device to open or close the second openable member.

[0020] In one embodiment, at least in the second direction, the third movable member can drive the third actuating member to move relative to the moving member to enable a distance between the third actuating member and the second radiation shielding device to be adjusted to open or close the second openable member. When the third movable member drives the third actuating member to move in the second direction, the third actuating member can move toward or away from the second radiation shielding device. When moving toward the second radiation shielding device, i.e., moving toward the second openable member, the third actuating member can open or close the second openable member.

[0021] In one embodiment, the first radiation shielding device, the second radiation shielding device and the radiation isolator are disposed in sequence, and the first actuator, the third actuator and the second actuator are disposed in sequence, such that when the moving member is in a third position of the base, a position of the first actuator corresponds to the position of the first radiation shielding device, a position of the third actuator corresponds to the position of the second radiation shielding device, and a position of the second actuator corresponds to the position of the radiation isolator. In this configuration, in a start position, the position of the first actuator corresponds to the position of the first radiation shielding device, the position of the third actuator corresponds to the position of the second radiation shielding device, and the position of the second actuator corresponds to the position of the radiation isolator, such that direct performance is possible without positional adjustments, reducing the operating steps and operating time for individually adjusting and aligning each component, realizing synchronous adjustment and alignment operations of the plurality of actuators, and significantly improving the efficiency.

[0022] In one embodiment, the first radiation shielding device is provided with a first openable member, such that a closed shielding space is created when the first openable member is closed. When the first openable member is opened, the radioactive material can pass through the first openable member. When the first openable member is closed, the first radiation shielding device is closed to isolate the radiation of the radioactive material from the outside. When it is necessary to transfer the radioactive material, the first openable member only needs to be opened.

[0023] In one embodiment, the radioactive material transfer system further includes an openable member control device. The openable member control device can remotely control the opening and closing of the first openable member by means of a wired or wireless connection. In this configuration, an operator can remotely open or close the first openable member to avoid radiation exposure and health hazards during close-range operation.

[0024] In one embodiment, at least one of the first radiation shielding device and the second radiation shielding device is provided with a movable portion. The movable portion is configured such that at least one of the first radiation shielding device and the second radiation shielding device can move between a start position and an end position. When the movable portion is provided, at least one of the first radiation shielding device and the second radiation shielding device can move between the start position and the end position, thereby adjusting the distance between the two, so as to facilitate the transfer of the radioactive material and the first transmission portion by the transfer device. In one embodiment, the radioactive material transfer system further includes a positioning system for positioning the first radiation shielding device and the second radiation shielding device relative to the transfer device. After the positions of the first radiation shielding device and the second radiation shielding device are determined, the transfer device is facilitated in transferring the first transmission portion. In addition, an execution program of the transfer device may be preset based on positions. The program of the transfer device can be executed after the first radiation shielding device and the second radiation shielding device move to preset positions to transfer the first transmission portion.

[0025] In one embodiment, at least one of the first radiation shielding device and the second radiation shielding device is provided with a buffer. After the radioactive material comes into contact with the buffer, the buffer deforms elastically and exerts an opposing force in a direction of movement of the radioactive material. In this configuration, the radioactive material is subject to a buffering force when entering the first radiation shielding device or the second radiation shielding device to avoid direct collision damage.

[0026] In one embodiment, the first radiation shielding device and the second radiation shielding device are made of a radiation shielding material. The first radiation shielding device and the second radiation shielding device made of the radiation shielding material can effectively prevent radiation leakage to avoid radiation contamination, improving the safety.

[0027] In one embodiment, a third guide is provided in a box of the first radiation shielding device, a fourth guide is provided in a box of the second radiation shielding device, and the transfer device removes the radioactive material from the first radiation shielding device by the third guide, and then moves the radioactive material into the second radiation shielding device by the fourth guide. The third guide in the first radiation shielding device and the fourth guide in the second radiation shielding device can reliably fix the radioactive material, improving the safety of transfer of the radioactive material.

[0028] In a second aspect, the present application further provides a radioactive material transfer method for use in a radioactive material transfer system, the radioactive material transfer system including a first radiation shielding device, a second radiation shielding device, and a transfer device. The radioactive material transfer method includes: operatively transferring a radioactive material from the first radiation shielding device into the second radiation shielding device by the transfer device. The radioactive material is transferred into the second radiation shielding device by the transfer device to facilitate the storage of the radioactive material.

[0029] In one embodiment, the radioactive material transfer system further includes a positioning system, and the radioactive material transfer method further includes: positioning the first radiation shielding device and / or the second radiation shielding device relative to the transfer device by the positioning system. After the positions of the first radiation shielding device and the second radiation shielding device are determined, the transfer device is facilitated in transferring the first transmission portion. In addition, an execution program of the transfer device may be preset based on positions. The program of the transfer device can be executed after the first radiation shielding device and the second radiation shielding device move to preset positions to transfer the first transmission portion. In one embodiment, the transfer device includes a base and a moving member, and the radioactive material transfer method includes: controlling the moving member to move on the base from a respective position of the first radiation shielding device to a respective position of the second radiation shielding device.

[0030] In one embodiment, the transfer device includes a first actuator movably disposed on the moving member, where the first actuator can be moved relative to the base together with the moving member; and the radioactive material transfer method includes: controlling the moving member to drive the first actuator to move relative to the base to the respective position of the first radiation shielding device, and controlling the first actuator to obtain the radioactive material located in the first radiation shielding device; and controlling the moving member to drive the first actuator to move relative to the base so as to drive the radioactive material to move to the respective position of the second radiation shielding device, and controlling the first actuator to release the radioactive material to the second radiation shielding device. The moving member moves to drive the first actuator to move between the respective position of the first radiation shielding device in which the action of picking up the radioactive material is performed and the respective position of the second radiation shielding device in which the action of releasing the radioactive material is performed, to transfer the radioactive material, where the respective positions refer to positions such as above and diagonally above.

[0031] In one embodiment, the radioactive material transfer system further includes a radiation isolator and a second actuator movably disposed on the moving member. The radioactive material transfer method further includes: controlling the moving member to drive the second actuator to move relative to the base to the respective position of the radiation isolator to obtain the radiation isolator; and controlling the moving member to drive the second actuator to move relative to the base so as to drive the radiation isolator to move to the respective position of the second radiation shielding device, and releasing the radiation isolator to the second radiation shielding device. The radiation isolator is disposed in the second radiation shielding device to cover the radioactive material, so as to isolate the radioactive material.

[0032] In one embodiment, the radioactive material transfer system further includes a third actuator movably disposed on the moving member, and the second radiation shielding device has a second openable member. The radioactive material transfer method further includes: controlling the moving member to drive the third actuator to move relative to the base to the respective position of the second radiation shielding device, and closing the second openable member by the third actuator. Upon closing the second openable member, the radioactive material is further sealed to shield the radiation of the radioactive material from the outside.

[0033] In one embodiment, the first radiation shielding device is provided with a first openable member. The first radiation shielding device, the second radiation shielding device and the radiation isolator are disposed in sequence, and the first actuator, the third actuator and the second actuator are disposed in sequence. The radioactive material transfer method includes: opening the first openable member of the first radiation shielding device; controlling the moving member to move to the third position of the base such that the position of the first actuator corresponds to the position of the first radiation shielding device, the position of the third actuator corresponds to the position of the second radiation shielding device, and the position of the second actuator corresponds to the position of the radiation isolator; controlling the first actuator to obtain the radioactive material located in the first radiation shielding device; controlling the third actuator to open the second openable member of the second radiation shielding device for covering; controlling the second actuator to obtain the radiation isolator; controlling the moving member to move to the fourth position of the base such that the position of the first actuator corresponds to the position of the second radiation shielding device; controlling the first actuator to release the radioactive material to the second radiation shielding device; controlling the moving member to move to the fifth position of the base such that the position of the second actuator corresponds to the position of the second radiation shielding device; controlling the second actuator to release the radiation isolator to the second radiation shielding device; controlling the moving member to move to the third position of the base; and controlling the third actuator to close the second openable member. The moving member is provided with a plurality of positions relative to the base. The positions of the first actuator, the second actuator and the third actuator can be adjusted by controlling the movement of the moving member between the plurality of positions, such that the radiation isolator is placed on the radioactive material while the radioactive material is transferred, and the second openable member is closed without the need to provide three independent control units for the actuators.

[0034] In a third aspect, the present application further discloses a neutron capture therapy system including a transfer device. The boron neutron capture therapy system include: an accelerator configured to generate a charged particle beam; a transmission device configured to transmit the charged particle beam generated by the accelerator, the transmission device including at least a first transmission portion and a second transmission portion, where the first transmission portion is detachably connected to the second transmission portion; a neutron generation unit disposed at the first transmission portion and movable together with the first transmission portion, the neutron generation unit being configured to react with the charged particle beam to generate a neutron beam; a beam shaping assembly configured to adjust an energy spectrum of the neutron beam; a first radiation shielding device configured to accommodate the first transmission portion and the neutron generation unit; a second radiation shielding device configured to store the first transmission portion and the neutron generation unit; and a transfer device configured to transfer the first transmission portion and the neutron generation unit in the first radiation shielding device into the second radiation shielding device.

[0035] The first transmission portion and the neutron generation unit enter the first radiation shielding device for storage for a first preset period of time. The first transmission portion and the neutron generation unit are transferred into the second radiation shielding device by the transfer device for the transfer and storage of the neutron generation unit for a second preset period of time. The second preset period of time is significantly longer than the first preset period of time, and the second preset period of time is particularly suitable for long-term storage of the neutron generation unit. The second radiation shielding device is more suitable for long-term storage of the neutron generation unit than the first radiation shielding device, until the radioactive material in the neutron generation unit complies with the safety requirements, thereby achieving effective protection against radiation.

[0036] In one embodiment, the neutron capture therapy system further includes a guiding device that can guide the first transmission portion and the neutron generation unit to move from a first position to a second position, where when the first transmission portion is in the first position in the neutron capture therapy system, the neutron generation unit is accommodated in the beam shaping assembly to be able to react with a charged particle beam to generate neutrons; and when the first transmission portion is in the second position in the neutron capture therapy system, the neutron generation unit is separated from the beam shaping assembly. When the first transmission portion is in the first position, the neutron generation unit is located in the beam shaping assembly to be able to react with the charged particle beam to generate a neutron beam. When it is necessary to replace the neutron generation unit, the neutron generation unit and the first transmission portion are guided by the guiding device to the second position so as to enter the first radiation shielding device, and then the neutron generation unit and the first transmission portion are transferred into the second radiation shielding device by the transfer device. By means of cooperation of the first transmission portion, the guiding device and the transfer device, the neutron generation unit that needs to be replaced is finally accommodated in the second radiation shielding device.

[0037] In one embodiment, the guiding device includes a first guide, a second guide, and a third guide, where the first guide and the second guide have different guiding directions, the second guide is connected to the third guide, and the third guide is disposed in the first radiation shielding device, such that the first transmission portion and the neutron generation unit can be guided into the first radiation shielding device. The neutron generation unit and the first transmission portion are guided to move by the first guide, the second guide and the third guide in sequence, where when the first guide and the second guide have different guiding directions, a movement path of the neutron generation unit can be changed, and when the second guide is connected to the third guide disposed in the first radiation shielding device, the neutron generation unit and the first transmission portion can be guided together into the first radiation shielding device.Brief Description of the Drawings

[0038] FIG. 1 is a front view of a radioactive material / neutron generation unit transfer system according to one embodiment. FIG. 2 is a schematic structural diagram of a neutron capture therapy system according to one embodiment. FIG. 3 is a view of a shielding facility that is opened according to one embodiment. FIG. 4 is a view showing that a first transmission portion with a neutron generation unit at an end is replaced according to one embodiment. FIG. 5 is a schematic structural diagram of a first guide and a second guide that are connected according to one embodiment. FIG. 6 is a schematic structural diagram of a driving mechanism according to one embodiment. FIG. 7 is a schematic diagram of an openable member control device controlling an openable member according to one embodiment. FIG. 8 is a schematic diagram of a movable portion control device controlling a movable portion according to one embodiment. FIG. 9 is a side view of a radioactive material / neutron generation unit transfer system according to one embodiment. FIG. 10 is a bottom view of a radioactive material / neutron generation unit transfer system according to one embodiment. FIG. 11 is a schematic view of a first actuating member of a first actuator gripping a radioactive material / neutron generation unit or a radiation isolator according to one embodiment. FIG. 12 is a schematic structural diagram of a second radiation shielding device and a third actuator according to one embodiment. FIG. 13a is a schematic diagram of a positioning structure for aligning the radiation isolator on a mobile carrier according to one embodiment. FIG. 13b is a schematic diagram of placing the radiation isolator on the mobile carrier by the positioning structure according to one embodiment. FIG. 14a is a schematic inner structural diagram of the radiation isolator according to one embodiment. FIG. 14b is a schematic diagram of aligning the radiation isolator to the radioactive material / neutron generation unit according to one embodiment. FIG. 14c is a schematic diagram of placing the radiation isolator on the radioactive material / neutron generation unit according to one embodiment. FIG. 15 is a schematic flowchart of a radioactive material / neutron generation unit transfer method according to one embodiment. FIG. 16 is a schematic flowchart of a radioactive material / neutron generation unit transfer method according to another embodiment. FIG. 17 is a structural block diagram of a master control device according to one embodiment. FIG. 18 is a schematic position diagram of a moving member in a third position relative to a base according to one embodiment. FIG. 19 is a schematic position diagram of the moving member in a fourth position relative to the base according to one embodiment. FIG. 20 is a schematic position diagram of the moving member in a fifth position relative to the base according to one embodiment.

[0039] List of reference signs: 600 - First radiation shielding device; 700 - Second radiation shielding device; 800 - Transfer device; 100 - Accelerator; 200 - Transmission device; 210 - First transmission portion; 220 - Second transmission portion; 230 / 240 - Support device; 300 - Radioactive material / neutron generation unit; 310 - Cooling device; 320 - Measurement device; 400 - Beam shaping assembly; 500 - Guiding device; L1 - First position; L2 - Second position; 510 - First guide; 520 - Second guide; 530 - Third guide; 531 - Fourth guide; 540 - Connecting portion; 550 - Driving mechanism; 551 - Power structure; 552 - Driving carriage; 610 - Openable member; 610' - First openable member; 611 - Opening mechanism; 612 - First unit; 613 - Second unit; 620 - Openable member control device; 630 - Movable portion; 631 - Positioning member; 640 - Movable portion control device; 641 - First alignment mechanism; 642 - Second alignment mechanism; 650 - Buffer; 660 - First radiation shielding device handle; 710 - Radiation isolator; 711 - Mobile carrier; 712 - Carrier handle; 713 - Isolator handle; 714 - Positioning structure; 715 - Support structure; 720 - Second openable member; 721 - Second openable member handle; 730 - Second radiation shielding device handle; 810 - Bearing assembly; 811 - Pick-up assembly; 812 - Support; 813 - Extendable mechanism; 820 - Moving member; 821 - Guide rail; 830 - Base; 831 - Longitudinal rod; 832 - Transverse rod; 833 - Barrier; 834 - Inclined rod; 840 - First actuator; 841 - First movable member; 842 - First actuating member; 842a - Separable member; 842b - Bearing member; 842c - Catch; 843 - First drag chain; 850 - Second actuator; 851 - Second movable member; 852 - Second actuating member; 853 - Second drag chain; 860 - Third actuator; 861 - Third movable member; 862 - Third actuating member; 863 - Third drag chain; 864 - Third power member; 870 - Display device; 900 - Shielding facility; 901 - Opening; 902 / 903 - Shielding door; 1500 - Master control device; 1502 - Opening module; 1504 - Moving member control module; 1506 - First execution module; 1508 - Second execution module; 1510 - Third execution module; 1512 - Movement module; R1 - First space; R2 - Second space; R3 - Third space; P - Charged particle beam; N - Neutron beam.Detailed Description of Preferred Embodiments

[0040] In order to make the above objectives, features and advantages of the present invention more clearly understood, the particular embodiments of the present invention will be described in detail below with reference to the accompanying drawings. In the following description, many specific details are set forth in order to provide a thorough understanding of the present invention. However, the present invention can be implemented in numerous other ways that are different from those described herein, a person skilled in the art can make similar improvements without departing from the connotation of the present invention, and therefore the present invention is not limited to the particular embodiments disclosed below.

[0041] In the description of the present invention, it should be understood that orientation or position relationships indicated by the terms such as "center", "longitudinal", "transverse", "length", "width", "thickness", "up", "down", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", "clockwise", "counterclockwise", "axial", "radial", and "circumferential" are based on the orientation or position relationships shown in the accompanying drawings and are merely for ease of description of the present invention and simplification of the description, rather than indicating or implying that the devices or elements referred to must have a specific orientation or be constructed and operated in a specific orientation, and thus cannot be construed as limiting the present invention.

[0042] In addition, the terms "first" and "second" are used for descriptive purposes only, and cannot be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, the features defined with "first" and "second" can explicitly or implicitly include at least one of the features. In the description of the present invention, the phrase "a plurality of" means at least two, such as two, three, etc., unless otherwise specifically defined.

[0043] In the present invention, unless explicitly specified and defined otherwise, the terms such as "mount", "connect", "connected" and "fix" should be interpreted in a broad sense, for example, may be a fixed connection, a detachable connection, or integration; or may be a mechanical connection or an electrical connection; or may be a direct connection or an indirect connection via an intermediate medium, or may be communication between interiors of two elements or interaction between the two elements, unless otherwise specifically defined. For those of ordinary skill in the art, the specific meaning of the terms mentioned above in the present invention should be construed according to specific circumstances.

[0044] In the present invention, unless otherwise explicitly specified and defined, the expression of a first feature being "on" or "under" a second feature may be the case that the first feature is in direct contact with the second feature, or the first feature is in indirect contact with the second feature via an intermediate medium. Moreover, the expression the first feature being "over", "above" and "on top of" the second feature may be the case that the first feature is directly above or obliquely above the second feature, or only means that the level of the first feature is higher than that of the second feature. The expression of the first feature being "underneath", "below" and "beneath" the second feature may be the case that the first feature is directly below or obliquely below the second feature, or only means that the level of the first feature is lower than that of the second feature.

[0045] It should be noted that when an element is referred to as being "fixed to" or "arranged on" a further element, it may be directly on the further element, or there may be an intermediate element. When one element is considered to be "connected" to another element, the element may be directly connected to another element or an intermediate element may exist simultaneously. The terms "vertical", "horizontal", "upper", "lower", "left", "right" and similar expressions used herein are merely for the purpose of illustration and do not represent any unique implementation.

[0046] The embodiments of the present application provides a radioactive material transfer system for transferring a radioactive material in a radioactive site. Referring to FIG. 1, the radioactive material transfer system includes a transfer device 800 and further includes at least a first radiation shielding device 600 and a second radiation shielding device 700. The transfer device 800 is operated to transfer a radioactive material (not shown) between at least the first and second radiation shielding devices. The transfer device 800 may further include a base 830 and a moving member 820 (described below). The base 830 provides a stable operating frame and structure for the transfer device, defines a safe operating area, and further provides a positioning structure, a guiding structure, a display structure, etc., to ensure the stability, precision and reliability of the transfer of the radioactive material. The moving member 820 can operatively move relative to the base 830. The radioactive material transfer system according to the present application is stable in structure and has a small footprint, which facilitates safe transfer with low risk of exposure of personnel to a radioactive material in a compact building. The radioactive material is stored in the first radiation shielding device 600 for a first preset period of time. After being transferred from the first radiation shielding device 600 to the second radiation shielding device 700 by the transfer device 800, the radioactive material is stored in the second radiation shielding device 700 for a second preset period of time that is significantly longer than the first preset period of time.

[0047] In one embodiment, as shown in FIG. 1, the radioactive material transfer system includes at least a first radiation shielding device 600, a second radiation shielding device 700, and a transfer device 800. The first radiation shielding device 600 is configured to accommodate a radioactive material, and the second radiation shielding device 700 is configured to store the radioactive material. The transfer device 800 is configured to transfer the radioactive material / neutron generation unit in the first radiation shielding device 600 into the second radiation shielding device 700.

[0048] Illustratively, the first radiation shielding device 600 and / or the second radiation shielding device 700 are made of a radiation shielding material which is 90% or more (by weight) composed of at least one of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, Ca and Ti, and which may further be aluminum-magnesium alloy, or a carbon-fiber composite, a glass-fiber composite, or a combination thereof. In such a way, the first radiation shielding device 600 or second radiation shielding device 700 with the radioactive material accommodated therein can function to isolate the radiation of the radioactive material to external environment. In some embodiments, external materials of the first radiation shielding device 600 and the second radiation shielding device 700 are selected as anti-activation materials, such as aluminum. Internal materials are selected as materials with shielding properties, such as lead. In other embodiments, the first shielding device 600 may be provided with different materials at different box portions depending on the position of the accommodated radioactive material.

[0049] In one embodiment of the present application, the radioactive material transfer system is used in a radiotherapy system. Radiotherapy as an effective means of treating cancers has been increasing in recent years, in particular for the research and development of neutron capture therapy that is effective in reducing radiation damage to normal tissues surrounding a tumor. Boron neutron capture therapy is the most common, and neutrons supplying boron neutron capture therapy can be supplied by a nuclear reactor or an accelerator. In one embodiment of the present application, in an example of a neutron capture therapy system, such as an accelerator boron neutron capture therapy system, basic components of which typically include an accelerator for accelerating charged particles such as protons and deuterons, a radioactive consumable neutron generation unit, a heat removal system, and a beam shaping assembly. The accelerated charged particles interact with the metallic neutron generation unit to generate neutrons. A suitable nuclear reaction is selected based on a required neutron yield and energy, accelerated charged particle energy and current that can be provided, and the properties of the metallic neutron generation unit such as physical and chemical properties. The nuclear reactions usually discussed are 7< Li(p,n) 7< Be and 9< Be(p,n) 9< B, both of which are endothermic reactions, and the energy thresholds for the two nuclear reactions are 1.881 MeV and 2.055 MeV, respectively. Since an ideal neutron source for the boron neutron capture therapy provides epithermal neutrons in the keV energy range, theoretically, if a metallic lithium neutron generation unit is bombarded by protons having an energy only slightly above the thresholds, neutrons with relatively low energy can be produced and can be used clinically without requiring extensive moderation. However, the cross-sections for the interaction of both lithium (Li) and beryllium (Be) neutron generation units with protons at threshold energy are not high. In order to create a sufficiently large neutron flux, protons with high energy are typically selected to induce the nuclear reactions.

[0050] The requirements for the heat removal system then vary depending on the selected nuclear reaction. For example, due to the low melting point and poor thermal conductivity of the metallic neutron generation unit (lithium), the 7< Li(p,n) 7< Be reaction has higher requirements for the heat removal system than the 9< Be(p,n) 9< B reaction. The 7< Li(p,n) 7< Be nuclear reaction is used in the embodiments of the present application. It can be seen therefrom that the temperature of the neutron generation unit irradiated by a high-energy accelerated charged particle beam will inevitably rise significantly, which affects the service life of the neutron generation unit. The used neutron generation unit as a radioactive material has a large amount of radioactive rays. Therefore, when the neutron generation unit is replaced in a close range, unless there are sufficient protective or isolation measures, a radioactive material transfer system is considered to be used in the neutron capture therapy system described above, so as to reduce radiation safety hazards.

[0051] Referring to FIG. 2, FIG. 2 shows a schematic structural diagram of a neutron capture therapy system according to one embodiment of the present invention in which a radioactive material transfer system may be used. One embodiment of the present invention provides a neutron capture therapy system, including an accelerator 100, a transmission device 200, a neutron generation unit (a radioactive material) 300, and a beam shaping assembly 400. When the radioactive material transfer system is used in the neutron capture therapy system, the neutron generation unit 300 of the neutron capture therapy system is a radioactive material, which is the object to be transferred by the transfer device 800. When it is necessary to replace the neutron generation unit 300, the neutron generation unit 300 is guided into the first radiation shielding device 600, and the neutron generation unit 300 is transferred from the first radiation shielding device 600 to the second radiation shielding device 700 by the transfer device 800. It should be noted that the first radiation shielding device 600, the second radiation shielding device 700 and the transfer device 800 may be located in the same space as the accelerator 100, the transmission device 200, the neutron generation unit 300 and the beam shaping assembly 400, for example, in the same room, or the first radiation shielding device 600, the second radiation shielding device 700 and the transfer device 800 may be located in another space, for example, in two separate rooms.

[0052] With continued reference to FIG. 2, in one possible implementation, the transfer device 800 includes a bearing assembly 810 (equivalent to a first actuator 840 below) and a support 812 (equivalent to a base 830), where the support 812 serves to support the bearing assembly 810. The bearing assembly 810 includes a pick-up assembly 811 and an extendable mechanism 813 (corresponding to a first movable member 841 below), where the pick-up assembly 811 is configured for picking up a radioactive material / neutron generation unit 300 and is equivalent to the first actuating member 842, and / or a second actuating member 852 and / or a third actuating member 862 below. The bearing assembly 810 is movable relative to the support 812 (equivalent to the first actuator 840 or the second actuating member 852 or the third actuating member 862 moving relative to the base 830 by the moving member 820 below).

[0053] In the neutron capture therapy system, the accelerator 100 is configured to generate and accelerate a charged particle beam P, the transmission device 200 is configured to transmit the charged particle beam P to the neutron generation unit 300 such that the neutron generation unit 300 can react with the charged particle beam P to generate and emit a neutron beam N, and the beam shaping assembly 400 is disposed in a path of the neutron beam N and is configured to adjust the beam quality of the neutron beam N. The first radiation shielding device 600 is configured to accommodate the neutron generation unit 300, the second radiation shielding device is configured to store the neutron generation unit 300, and the transfer device 800 is configured to transfer the neutron generation unit 300 from the first radiation shielding device 600 into the second radiation shielding device 700. Illustratively, the second radiation shielding device 700 has a stronger radiation shielding capability than the first radiation shielding device 600, and preferably the second radiation shielding device 700 can be designed with a more simple and compact structure compared to the first radiation shielding device 600. Therefore, the dimension and volume of the second radiation shielding device 700 can be designed to be relatively small. It will be easily understand that the first radiation shielding device 600 is only suitable for short-time (a first period of time) temporary storage, and the second radiation shielding device is suitable for prolonged (a second period of time) storage, to meet the centralized storage of a plurality of neutron generation units for a prolonged period of time.

[0054] The neutron capture therapy system can be divided into at least a first space R1 and a second space R2. The accelerator 100, a part of the transmission device 200, supporting equipment for supporting the transmission device and associated measurement equipment are disposed in the first space R1. The second space R2 is usually the core reaction space of the entire system and has relatively high radiation. A part of the transmission device 200, the neutron generation unit 300 and the beam shaping assembly 400 are disposed in the second space R2. The second space R2 can be physically isolated from the first space R1 by a shielding facility 900 to shield harmful radiation as much as possible. As a result, the radiations from the first space R1 and other spaces in communication with the first space R1 can be controlled to be at a relatively safe level. Further, the transmission device 200 passes through the first space R1 and the second space R2, and the shielding facility 900 includes at least one opening 901 for the transmission device 200 to pass through the shielding facility 900 in a closed state.

[0055] The accelerator 100 is configured to accelerate the charged particles P to have energy sufficient to overcome the nuclear force of a target. A direction of transmission of the charged particle beam P is consistent with a direction of arrangement of the transmission device 200, such that a 7< Li(p,n) 7< Be nuclear reaction occurs between the charged particle beam P and the neutron generation unit 300 to generate neutrons to create and emit a neutron beam N.

[0056] The transmission device 200 includes at least a first transmission portion 210 and a second transmission portion 220 detachably connected to the first transmission portion 210, where preferably the first transmission portion 210 is located in the second space R2. The first transmission portion 210 and the second transmission portion 220 may be in the form of a hollow tube, with their cross-sectional shapes including, but not limited to, circular, oval, diamond, square, irregular shapes. The at least one opening 901 of the shielding facility 900 may be shaped to match the shape of the transmission device 200 or the like passing through the opening, including, but not limited to, circular, oval, diamond, square, irregular shapes. During the replacement of a radioactive consumable and the disassembly of the transmission device 200, the first transmission portion 210 and the second transmission portion 220 of the transmission device are preferably remain in a vacuum state.

[0057] The neutron generation unit 300 is configured to generate the neutron beam N, which may be act as a target, such as a target containing Li, and which undergoes the 7< Li(p,n) 7< Be nuclear reaction with the charged particle beam P to produce neutrons. The neutron generation unit 300 is fixedly or movably connected to the first transmission portion 210, or is limited by the first transmission portion 210, such that the neutron generation unit 300 can move together with the first transmission portion 210. The end of the first transmission portion 210 at which the neutron generation unit 300 is provided is received in the beam shaping assembly 400.

[0058] The beam shaping assembly 400 generally has a large size and is not suitable for movement, and may be fixedly embedded inside a wall, and includes a moderator, a thermal neutron absorber, a radiation shield, etc. (none of which are shown in the figures). The moderator is made of a mixture of aluminum fluoride (typically as main material) and optionally one or more of lithium fluoride, aluminum, lead fluoride, aluminium oxide, calcium fluoride or magnesium fluoride. The moderator moderates the neutrons generated by the neutron generation unit 300 down to an epithermal neutron energy range, and the deviated neutrons are reflected back to the moderator by a reflector to increase the intensity of an epithermal neutron beam. Thermal neutron absorber absorbs thermal neutrons to avoid unnecessary damages to superficial normal tissues due to excess dose during treatment. The radiation shield is configured to shield leaked neutrons and photons to reduce the dose in normal tissues in non-irradiated areas. The neutron capture therapy system further includes a third space R3 as an irradiation chamber, and a qualified neutron beam N can exit a beam exit and enter the irradiation chamber for use.

[0059] Each of the first radiation shielding device 600 and the second radiation shielding device 700 may be a box having a cavity, which may have a square, spherical or other special shapes. The first radiation shielding device 600 is configured to accommodate the first transmission portion 210 and the neutron generation unit 300, and can serve the function of temporary storage, and the second radiation shielding device 700 is configured to store the first transmission portion 210 and the neutron generation unit 300 or to store only the neutron generation unit 300, and can serve the function of prolonged storage. In some embodiments, the first radiation shielding device 600 and the second radiation shielding device 700 are made of a radiation shielding material, including, but not limited to, a radiation shield made of plumbum (Pb).

[0060] The transfer device 800 is configured to transfer the first transmission portion 210 and the neutron generation unit 300 in the first radiation shielding device 600 into the second radiation shielding device 700. When the first radiation shielding device 600, the second radiation shielding device 700 and the transfer device 800 are located in the same space as the accelerator 100, the transmission device 200, the neutron generation unit 300 and the beam shaping assembly 400, the first transmission portion 210 enters the first radiation shielding device 600 together with the neutron generation unit 300, and the neutron generation unit 300 in the first radiation shielding device 600 is transferred directly by the transfer device 800 to the second radiation shielding device 700. In addition, in other embodiments, the transfer device 800 may also be in another space, and in this case the second radiation shielding device 700 and the transfer device 800 are located together in this space more suitable for prolonged centralized storage and recovery of the neutron generation unit. After the first transmission portion 210 enters the first radiation shielding device 600 together with the neutron generation unit 300, the first radiation shielding device 600 moves into the separate space where the second radiation shielding device 700 and the transfer device 800 are located, and the neutron generation unit 300 is thus transferred by the transfer device 800 from the first radiation shielding device 600 to the second radiation shielding device 700.

[0061] In one possible implementation, the neutron capture therapy system further includes a guiding device 500. The guiding device 500 is configured to guide the neutron generation unit 300 into the first radiation shielding device 600 when it is required to replace the neutron generation unit 300. The transfer device 800 is configured to transfer the neutron generation unit 300 from the first radiation shielding device 600 into the second radiation shielding device 700.

[0062] The guiding device 500 is configured to guide the first transmission portion 210 to move, thereby causing the neutron generation unit 300 to move together. Preferably, the guiding device 500 includes at least two positions, i.e., a first position L1 and a second position L2. The first position L1 may be a position in which the first transmission portion 210 is close to the beam shaping assembly 400, and in this case, the neutron generation unit 300 is accommodated in the beam shaping assembly 400 and can react with the charged particle beam P to generate the neutron beam N. The second position L2 may be a position in which the first transmission portion 210 is remote from the beam shaping assembly 400, and in this case, the neutron generation unit 300 is separated from the beam shaping assembly 400. Further, the second position L2 may also refer to a position in the first radiation shielding device 600.

[0063] Referring to FIG. 3, FIG. 3 shows that the shielding facility 900 is opened according to one embodiment, with the second radiation shielding device 700 and the transfer device 800 not shown. The shielding facility 900 includes at least one shielding door 902 and / or 903. When the shielding door 902 and / or the shielding door 903 are opened, the first space R1 communicates with the second space R2. With respect to FIG. 2, the neutron capture therapy system may further include a support device 230 and / or 240 for stably supporting the transmission device 200 in a direction in which the transmission device 200 is arranged. The support device 230 may be disposed under the second transmission portion 220, and the support device 240 may be disposed under the first transmission portion 210. In an alternative embodiment, the support device 240 may also be disposed in a different location, such as above or beside the first transmission portion 210 for support.

[0064] Referring to FIG. 4, FIG. 4 shows the first transmission portion 210 with the neutron generation unit 300 at an end being replaced according to some embodiments. In this case, the shielding facility 900 is opened and the first space R1 is in communication with the second space R2. The first transmission portion 210 is separated from the second transmission portion 220. The removal of the second transmission portion 220 causes the overall length of the transmission device 200 to change, which leave room for the first transmission portion 210 with the neutron generation unit 300 at the end to move out along the guiding device 500. In some embodiments, the second transmission portion 220 includes two sections that can be separated again, or is designed as a structure (not shown) such as a bellows or extendable tube, to leave a space for replacement operation. The guiding device 500 guides the first transmission portion 210 with the neutron generation unit 300 at the end that has been separated from the beam shaping assembly 400 into the first radiation shielding device 600.

[0065] With continued reference to FIG. 2, in some embodiments, the guiding device 500 includes a first guide 510, a second guide 520 connected to the first guide 510, and a third guide 530 connected to the second guide 520. The first guide 510, the second guide 520 and the third guide 530 may each be a bar-shaped rail or a bar-shaped groove, and the guiding device 500 may be provided with a driving mechanism 550 (which is described below) for driving the neutron generation unit 300 and the first transmission portion 210. Preferably, the first guide 510 is substantially along the direction of extension of the transmission device 200, the direction of extension of the transmission device 200 is substantially opposite or the same as the direction of movement of the charged particle beam P, a first end of the second guide 520 is connected to the first guide 510 by a connecting portion 540, and a second end thereof extends and is detachably connected to the third guide 530, for example, by the connecting portion 540. As shown in FIG. 5, FIG. 5 shows a schematic diagram of the first guide 510 and the second guide 520 that are connected according to some embodiments, where the connecting portion 540 may be a connecting rod, a latch, a male and female buckle or other structures that can firmly engage the first guide 510 with the second guide 520, such that the first transmission portion 210 moves smoothly from the first guide 510 to the second guide 520. A projection of a line connecting the first end and the second end of the second guide 520 forms a first angle with the first guide 510, such as 10° to 150°, preferably 30° to 90°. Preferably, in a plane perpendicular to the ground in which the first guide 510 is located, the projection of the line connecting the first end and the second end of the second guide 520 forms a second angle with the first guide 510. 90% or more (by weight) of the material of the part of the guiding device 500 that is exposed to high radiation is composed of at least one of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, Ca, Ti, may further be aluminum-magnesium alloy, or a carbon-fiber composite, a glass-fiber composite, or a combination thereof.

[0066] Preferably, the guiding directions of the first guide 510 and the second guide 510 of the guiding device 500 are different, that is, the guiding device 500 has at least two guiding directions. This configuration is advantageous for use in a compact building, enabling steering when the neutron generation unit 300 and the first transmission portion 210 are guided, and avoiding the limitation of the compact building on a guiding distance. Preferably, the third guide 530 is disposed in the first radiation shielding device 600 such that the guiding device 500 can guide the neutron generation unit 300 and the first transmission portion 210 into the first radiation shielding device 600. Referring to Fig. 4 for the guidance process, in one embodiment, the first transmission portion 210 moves through the opening 901 formed by opening the shielding door 902 and the shielding door 903 on the first guide 510 in the direction of extension of the transmission device 200 to the second guide 520, and then moves in the direction of the second guide 520 under the action of gravity or a rail power, approaches the first radiation shielding device 600 and moves in a direction of the third guide 530 disposed in the first radiation shielding device 600, so as to enter the first radiation shielding device 600 and be positioned. Preferably, a protective pad (not shown) for preventing activation may further be provided at the bottom of the first radiation shielding device 600 for bearing the radioactive material / neutron generation unit.

[0067] The sections of the first transmission portion 210 and the neutron generation unit 300 that first enter the radiation shielding device 600 are sides that are opposite the neutron generation unit 300 containing the radioactive consumable. That is, when the recovery operation is finally completed, it is the neutron generation unit 300 containing the radioactive consumable that is closer to a receiving opening of the first radiation shielding device 600. The design of this recovery direction focuses on improving the recycling rate of the neutron generation unit 300 containing the radioactive consumable. Since the neutron generation unit 300 located in the beam shaping assembly 400 is made of relatively active lithium (Li) and / or beryllium (Be), with a coating thickness of only about 100 microns, the neutron generation unit is prone to damage after being impacted. Therefore, compared with other recovery directions, the recovery direction in which the neutron generation unit 300 finally enters the receiving opening and stays at a distal end of a buffer device is safer and makes it less likely to damage the neutron generation unit, thereby significantly improving the reuse rate of the neutron generation unit 300 containing the radioactive consumable and preventing unwanted radiation leakage after collision. Moreover, the direction of movement of the neutron generation unit 300 does not need to be switched, and there is no need for a complicated direction switching structure, etc., which saves more space and also prevents radiation leakage due to a failure in the switching structure or the like.

[0068] Referring to FIG. 6, FIG. 6 shows a schematic structural diagram of a driving mechanism according to some embodiments. The guiding device 500 may include a driving mechanism 550. The driving mechanism 550 may include a power structure 551 and / or a driving carriage 552 carrying the first transmission portion 210 and the neutron generation unit 300. The power structure 551 includes, but is not limited to, an electronic or pneumatic link, a robot and structures thereof, a robotic arm, or the like. The driving carriage 552 may include a set of rollers disposed on two sides of the first guide 510 and / or the second guide 520. Accordingly, rolling grooves may be provided on the two sides of the first guide 510 and / or the second guide 520, such that the rollers can slide within the rolling grooves to enable the driving mechanism 550 to drive the first transmission portion 210 and the neutron generation unit 300 to move on the first guide 510 and / or the second guide 520.

[0069] The neutron capture therapy system may further include a cooling device 310 for cooling the neutron generation unit 300 and a measurement device 320. The cooling device 310 may include a pipe at an end of the transmission device 200 in planar contact with the neutron generation unit 300, at least two cooling pipes arranged one on the other in the direction of arrangement of the transmission device, where the two cooling pipes arranged one on the other may be partially disposed in the moderator, the cooling pipes are in the form of a "U"-shaped structure and in communication with an external cooling system. The neutron generation unit 300 heats up due to exposure to high-energy accelerated irradiation, and the neutron generation unit 300 is efficiently cooled by a cooling medium flowing through the cooling pipes. In the embodiment shown, the measurement device 320 may be a temperature sensor including a measurement line arranged along the transmission device 200 and connected to a control end to measure the real-time temperature of the cooling device 310. In an alternative embodiment, the measurement device 320 may also be a charged particle sensor to measure the condition of the charged particle beam before the first transmission portion 210 reacts with the neutron generation unit 300, or a vacuum pressure sensor to measure a vacuum condition of the first transmission portion 210, or a neutron detector to detect neutrons generated by a nuclear reaction. The measurement device 320 include, but is not limited to, an electronic sensor, a proximity sensor, a capacitive sensor, a transducer, or other forms of sensors. When the first transmission portion 210 is in the first position L1, the cooling pipes are connected to pipes of the external cooling system and are in a cooling state. The measurement line is connected to a line of the control end to enable real-time monitoring and data transmission and feedback. When the first transmission portion 210 is in the second position L2, the cooling pipes are disconnected from the cooling pipes of the external cooling system, and a connection between the measurement line and the control end is disconnected. The cooling device 310 and its partially disconnected pipes as well as the measurement device 320 and its partially disconnected lines are all disposed in the first transmission portion 210, and together with the first transmission portion 210, move to the second position L2 and are recovered and replaced.

[0070] In some embodiments, at least one of the first radiation shielding device 600 and the second radiation shielding device 700 is provided with an openable member 610, such that a closed shielding space is created when the openable member 610 is closed, and the radioactive material / neutron generation unit 300 can pass through the openable member 610 when the openable member 610 is opened. Illustratively, the first radiation shielding device 600 has an openable member 610. The first radiation shielding device 600 forms a closed shielding space when the openable member 610 is closed, to shield the radioactive material / neutron generation unit 300 in the first radiation shielding device 600. When the openable member 610 is opened, the radioactive material / neutron generation unit 300 can pass through the receiving opening formed by the openable member 610, such that the transfer device 800 can take out the radioactive material / neutron generation unit 300.

[0071] The openable member 610 may be made of a material having a shielding effect, such as a Pb-containing material, and the opening and closing actions of the openable member 610 includes, but is not limited to, rotation, sliding, etc. Referring to FIG. 7, in some embodiments, an openable member control device 620 is provided, and the openable member 610 is provided with a signal receiver communicatively connected to the openable member control device 620 by means of a wired or wireless connection, where the wireless connection may be a Bluetooth connection or a WIFI connection, such that the opening and closing of the openable member 610 can be remotely controlled by the openable member control device 620. During an replacement operation, the opening and closing of the openable member 610 can be controlled remotely outdoors, reducing the radiation contamination of an operator.

[0072] In some embodiments, a movable portion 630 is further provided at the bottom of the first radiation shielding device 600 and / or the second radiation shielding device 700. Illustratively, the movable portion 630 may be wheels such that the first radiation shielding device 600 and / or the second radiation shielding device 700 can move between two determined positions. For example, provisions are made that a start position is in a first room in which the beam shaping assembly is located, and an end position is in a second room for storing the radioactive material / neutron generation unit, the transfer device and the second radiation shielding device are disposed in the second room, and the first transmission portion enters the first radiation shielding device and then moves into the second room and is transferred from the first radiation shielding device to the second radiation shielding device by the transfer device. It will be easily understood that the start position and the end position may be defined according to actual use scenarios, and are not absolute position, and there may also be a plurality of start positions and / or a plurality of end positions during transfer.

[0073] For the first radiation shielding device 600 moving between a preset start position and a preset end position, the start position may also be a storage position when not in use, and the end position may also be a position when the radioactive material / neutron generation unit is transferred.

[0074] Further, the radioactive material / neutron generation unit transfer system further includes a positioning system for positioning the first radiation shielding device and the second radiation shielding device relative to the transfer device. Illustratively, the positioning system includes a movable portion control device 640. Referring to FIG. 8, the movable portion 630 may be provided with a signal receiver, the movable portion control device 640 is connected to the movable portion 630, for example, by means of a wired or wireless connection, including a WIFI connection, an infrared connection or a Bluetooth connection, etc., such that the movable portion control device 640 can control the first radiation shielding device 600 and / or the second radiation shielding device 700 to move to a preset position and be positioned.

[0075] Illustratively, the positioning system includes a first alignment mechanism 641 and a second alignment mechanism 642 (see FIG. 1), where the first alignment mechanism 641 is configured to detect whether the first radiation shielding device 600 moves to the preset position, and the second alignment mechanism 642 is configured to detect whether the second radiation shielding device moves to the preset position. In one possible implementation, a detection point is provided on the first radiation shielding device 600 and / or the second radiation shielding device 700, and a detection probe, such as a infrared or ultrasonic detection probe, is provided on the transfer device 800. The position of the detection point is determined by the detection probe to determine the position of the first radiation shielding device 600 and / or the second radiation shielding device 700.

[0076] Optionally, when the preset end position of the first radiation shielding device 600 is set as a guiding position for the guiding device 500, the first radiation shielding device 600 when being moved to the end position, can receive the radioactive material / neutron generation unit 300 guided by the guiding device 500 to facilitates transfer operations by the transfer device 800. When the guiding device 500 includes a first guide 510, a second guide 520, and a third guide 530, since the third guide 530 is disposed in the first radiation shielding device 600, the end position in which the first radiation shielding device 600 moves is set to be a guiding position for the second guide 520, such that the second guide 520 is operatively connected to the third guide 530 position when the first radiation shielding device 600 moves to the end position, and the radioactive material / neutron generation unit 300 and the first transmission portion 210 can be transferred by the second guide 520 to the third guide 530 and thus into the first radiation shielding device 600.

[0077] In some embodiments, the first radiation shielding device 600 is provided with an openable member 610 and a movable portion 630. When the radioactive material / neutron generation unit 300 is replaced, preferably, the operator can remotely control the movable portion 630 by the movable portion control device 640 to move the first radiation shielding device 600 to the guiding position for the guiding device 500 to enable the guiding device 500 to guide the radioactive material / neutron generation unit 300 and the first transmission portion 210 into the first radiation shielding device 600. In one possible implementation, the positioning system further includes a positioning member 631 for marking or stopping disposed on the ground. The positioning member 631 corresponds to the guiding position for the guiding device 500, and in this case the openable member control device 620 controls the opening of the openable member 610 to receive the first transmission portion 210 and the radioactive material / neutron generation unit 300 guided by the guiding device 500, after which the first radiation shielding device 600 can be controlled manually or by the movable portion control device 640 to move toward the second radiation shielding device 700. In one embodiment, the first radiation shielding device 600 moves from an outer space into the first space R1, is positioned at the preset end position, and interfaces with a lower end of the second guide 520. In some possible implementations, the positioning member 631 may be one or more marks, stop blocks, recessed structures, or the like.

[0078] In some embodiments, a buffer 650 may further be provided in an inner accommodating cavity of the first radiation shielding device 600 and / or the second radiation shielding device 700 for buffering the first transmission portion 210 and the neutron generation unit 300 against damage due to collisions with an inner wall. After the first transmission portion 210 and the neutron generation unit 300 come into contact with the buffer 650, the buffer 650 elastically deforms and exerts an opposing force in a direction of movement of the first transmission portion 210 to reduce the speed of the first transmission portion 210, such that the first transmission portion 210 and the neutron generation unit 300 can be stationarily received in either the first radiation shielding device 600 or the second radiation shielding device 700. In some possible implementations, the buffer 650 may be a different mechanical buffer structure, such as a spring, or a resilient material, such as a rubber cushion and a balloon.

[0079] In some embodiments, only the radioactive material, such as only the neutron generation unit 300, is transferred. Other structures associated with the radioactive material may also be transferred, such as the neutron generation unit 300 and the first transmission portion 210.

[0080] In another possible implementation, referring to FIGS. 1, 9 and 10, FIGS. 9 and 10 show further schematic structural views of the transfer device 800 according to some embodiments. The first radiation shielding device 600 is provided with a first accommodating cavity capable of accommodating the radioactive material / neutron generation unit 300 and a first openable member 610' for covering the first accommodating cavity, the second radiation shielding device 700 is provided with a second accommodating cavity capable of accommodating the radioactive material / neutron generation unit 300, and the transfer device 800 is configured to transfer the radioactive material / neutron generation unit 300 between the first accommodating cavity and the second accommodating cavity. Further, the first radiation shielding device 600 may further be provided with a first radiation shielding device handle 660 to facilitate the gripping and movement by the operator.

[0081] Referring to FIG. 9, the first openable member 610' can be hinged to a box of the first radiation shielding device 600, driven by an opening mechanism 611, and can be opened with one side of the top of the box of the first radiation shielding device 600 as a central line of rotation to expose the first accommodating cavity. Illustratively, the opening mechanism 611 is communicatively connected to the openable member control device 620, and the opening mechanism 611 can be controlled by the openable member control device 620 to open the first openable member 610'. In actual use, when the opening mechanism 611 extends, the first openable member 610' is driven to rotates and open. The first openable member 610' may include a first unit 612 and a second unit 613 rotatably connected to the first unit 612, where the first unit 612 is also rotatably connected to the box of the first radiation shielding device 600. Further, the opening mechanism 611 is connected to the first unit 612. In this configuration, when the opening mechanism 611 extends, the first unit 612 can be driven to rotate, and in this case the second unit 613 moves together with the first unit 612 and moves toward the first unit 612, as shown in FIG. 9, to realize folding, to expose the first accommodating cavity.

[0082] Further, the base 830 may include a frame structure that achieves basic support, such as a plurality of longitudinal rods 831 and a plurality of transverse rods 832 connected to each other, where the plurality of longitudinal rods 831 and the plurality of transverse rods 832 combine to form a bearing frame. In particular, the length of each of the longitudinal rods 831 is greater than the heights of the first radiation shielding device 600 and the second radiation shielding device 700 to ensure that the opening of the first openable member 610' is not blocked, and an area between adjacent longitudinal rods 831 may be used to place the first radiation shielding device 600 or the second radiation shielding device 700, allowing for no obstacles in front and behind to facilitate movement. Further, a control device may be provided, such as on the longitudinal rods 831, to facilitate electrical connection with an adjacent controlled mechanism to control the controlled mechanism. A remote control may also provided separately from the base 830. In one embodiment, the base 830 is provided with a barrier 833 at the top. In one embodiment, the base 830 may further be provided with a plurality of inclined rods 834, where the inclined rods 834 are connected to middle portions of some of the longitudinal rods 831 and middle portions of the transverse rods 832 for supporting purposes, to improve the stability of support of the frame of the base 830.

[0083] In some embodiments, the transfer device 800 includes a first actuator 840 movably connected to the moving member 820, where the first actuator 840 can pick up or release the radioactive material / neutron generation unit, and remove the radioactive material / neutron generation unit from the first radiation shielding device 600 by the third guide 530 to transfer the radioactive material / neutron generation unit. As the moving member 820 moves in a first direction relative to the base 830, the first actuator 840 can move together with the moving member 820. The first direction may be a direction of movement from an opening of the first accommodating cavity of the first radiation shielding device 600 to an opening of the second accommodating cavity of the second radiation shielding device 700. The first direction may also be a preset direction in which the moving member 820 moves along the base 830, for example, a horizontal direction parallel to the base 830. The first actuator 840 can operatively reach respective positions of the first radiation shielding device 600 and the second radiation shielding device 700, for example, directly above or diagonally above them. Illustratively, the first actuator 840 moves on the base 830 above the first radiation shielding device 600, picks up the radioactive material / neutron generation unit located in the first accommodating cavity and then moves above the second radiation shielding device 700, then moves the radioactive material / neutron generation unit into the second radiation shielding device 700 by a fourth guide 531, and releases the radioactive material / neutron generation unit to the second accommodating cavity to transfer the radioactive material / neutron generation unit.

[0084] In one possible implementation, the first actuator 840 includes a first actuating member 842 (see FIG. 11). Further, the first actuator 840 further includes a first movable member 841 which is extendable. The first movable member 841 can extend or retract in a second direction different from the first direction, and the first actuating member 842 is disposed at an extendable end of the first movable member 841. Illustratively, the second direction may be a direction close to or away from the first radiation shielding device 600 and / or the second radiation shielding device 700, for example, a vertical direction above the first radiation shielding device 600 and / or the second radiation shielding device 700, driving the first actuating member 842 to move in the second direction relative to the moving member 820. The first actuating member 842 is configured to obtain or release the radioactive material / neutron generation unit 300. Optionally, the first actuating member 842 may be a structure such as a jaw, a support table and a fastener, the first actuating member 842 corresponds to the radioactive material / neutron generation unit in terms of shape and size, can enter the accommodating cavity of the first radiation shielding device 600 and / or the second radiation shielding device 700, and can pick up the radioactive material / neutron generation unit to a certain height.

[0085] Referring to FIG. 11, FIG. 11 shows a schematic structural diagram of the first actuating member according to one embodiment. The first actuating member 842 includes a plurality of separable members 842a, a plurality of bearing members 842b, and a plurality of catches 842c. Preferably, the plurality of catches 842c are spaced apart so as to be capable of catching preset portions of the radioactive material / neutron generation unit 300, and the plurality of catches 842c are connected to two oppositely disposed separable members 842a by the bearing members 842b that can move toward or away from each other, respectively, such that when the two separable members 842a move toward each other, the plurality of catches 842c follow to move toward one another, so as to reduce spacings for gripping. When the two separable members 842c move away from each other, the plurality of catches 842c move away from one another, so as to increase the spacings for release. In particular, the two separable members 842a can move away from and toward each other by means of a cylinder, a telescopic rod, a manipulator, etc. In this configuration, when it is desired to pick up the radioactive material / neutron generation unit 300, the two separable members 842a are first moved away from each other and toward the radioactive material / neutron generation unit 300, and when reaching the preset positions, the two separable members 842a move toward each other to cause the plurality of catches 842c move toward one another so as to be caught in the preset positions of the radioactive material / neutron generation unit 300, such as a vacant portions under a flange of the radioactive material / neutron generation unit 300, to grip and fix the radioactive material / neutron generation unit 300. It will be easily understood that similar structures may be used to transfer a radiation isolator 710 in other embodiments.

[0086] In addition, in an embodiment of the neutron capture system, the catches 842c can also catch a clearance portion of the first transmission portion 210 when the first transmission portion 210 moves with the neutron generation unit (equivalent to the radioactive material) 300. Preferably, when the first transmission portion 210 is provided with the cooling device 310 or other structures, the catches 842c can catch a clearance portion of the neutron generation unit 300 with no contact with the cooling device 310 or other structures, to avoid damage caused by improper gripping.

[0087] A first end of the first movable member 841 is movably connected to the moving member 820 by means of sliding connection, for example. A second end of the first movable member 841 is connected to the first actuating member 842 such that when the first movable member 841 moves to the preset position, the first actuating member 842 can be carried to the preset position, which can be the respective positions of the first radiation shielding device 600 and the second radiation shielding device 700, such as in the first accommodating cavity of the first radiation shielding device 600 and in the second accommodating cavity of the second radiation shielding device 700. Optionally, after the first movable member 841 moves to the preset position, the first movable member 841 is controlled to extend or retract such that the first actuating member 842 can reach the first accommodating cavity and the second accommodating cavity. In one embodiment, the first movable member 841 is driven by a first power member (not shown) to extend and retract, and extends to move toward the first radiation shielding device 600 or the second radiation shielding device 700, and conversely retracts to move away from the first radiation shielding device 600 or the second radiation shielding device 700. Further, the first actuating member 842 can be electrically connected to the driving mechanism by a first drag chain 843, the first power member can be in the form of a cylinder, air pipes and cables used in the cylinder can extend into the first drag chain 843 for protection in order to avoid the entanglement of a plurality of cables or air pipes. It will be easily understood that the first movable member 841 may be in other forms that would readily occur to those skilled in the art to drive the first actuating member 842 to move.

[0088] With continued reference to FIG. 1, in some embodiments, the radioactive material / neutron generation unit transfer system further includes a radiation isolator 710. The radiation isolator 710 can be disposed in the second accommodating cavity together with the radioactive material / neutron generation unit 300 to isolate the radioactive material / neutron generation unit 300 and reduce its radiation contamination to the outside. It will be easily understood that the radiation isolator 710 may be sized to match the opening of the second accommodating cavity such that after the radioactive material / neutron generation unit 300 is placed in the second accommodating cavity, the radiation isolator 710 is placed over the radioactive material / neutron generation unit 300, which can ensure that the second accommodating cavity is sealed. In particular, the radiation isolator 710 may be configured on a mobile carrier 711, and the mobile carrier 711 may be provided with a carrier handle 712 to facilitate the operator holding the carrier handle 712 to place the mobile carrier 711 in a preset position. In other embodiments, referring to FIGS. 13a and 13b, the mobile carrier 711 further includes a positioning structure 714 for maintaining the radiation isolator 710 in alignment for transfer, which is advantageous for the radiation isolator 710 to maintain at a predetermined angle during transfer to achieve further shielding of the radioactive material / neutron generation unit. In some embodiments, the radiation isolator 710 is made of a radiation shielding material, including, but not limited to, plumbum (Pb), or is a composite structure made of mental coated with plumbum. In some embodiments, referring to FIGS. 14a to 14c, the radiation isolator 710 includes a support structure 715 on an inner surface. When the radioactive material / neutron generation unit has a protruding structure at one end, for example, the neutron generation unit may have a structure such as a protruding cooling water pipe at a target end, the material of the support structure 715 may be selected to be a more rigid material than the bulk shielding material, and the support structure 715 directly bears a load by its own rigid structure on a plane in which the target end is located and on the inner surface of the radiation isolator 710, such that a protective space S is created to serves the functions of supporting and protecting the cooling water pipe or other structures from being crushed by the heavy radiation isolator 710. In some embodiments, the radiation isolator 710 has a greater structural thickness near the radioactive material and a smaller structural thickness away from the radioactive material, and the radiation isolator 710 includes a plurality of thicknesses and / or a gradient thickness, which is conductive to reducing its own weight and creating targeted shielding protection. In some embodiments, the radiation isolator 710 has a greater structural thickness near the opening of the first accommodating cavity or the opening of the second accommodating cavity, and a smaller structural thickness away from the opening of the first accommodating cavity or the opening of the second accommodating cavity.

[0089] The transfer device 800 further includes a second actuator 850 movably connected to the moving member 820, such that in the first direction, the second actuator 850 can move relative to the base 830 to the respective position of the radiation isolator 710 and the respective position of the second radiation shielding device 700. The second actuator 850 can pick up or release the radiation isolator 710 such that the radiation isolator 710 can be picked up when the second actuator 850 is transferred to the respective position of the radiation isolator 710. After the radioactive material / neutron generation unit is placed in the second accommodating cavity of the second radiation shielding device 700, the second actuator 850 transfers the radiation isolator 710 to the respective position of the second radiation shielding device 700 and further places the radiation isolator 710 into the second accommodating cavity. It will be easily understood that the second actuator 850 may be operatively movable in the first direction by means of the fit between a sliding block and a sliding groove, the fit between guide wheels and guide rails, or other methods.

[0090] In one embodiment, the second actuator 850 includes a second actuating member 852. Further, the second actuator 850 further includes a second movable member 851 which is extendable. The second movable member 851 can extend and retract in the second direction different from the first direction. A fixed end of the second movable member 851 is movably connected to the moving member 820, and an extendable end of the second movable member 851 is connected to the second actuating member 852, such that the second actuating member 852 can change its position as the second movable member 851 extends or retracts. The second actuating member 852 may be a jaw, a support table, a fastener, or other structures capable of picking up the radiation isolator 710. In one possible implementation, the radiation isolator 710 may be provided with an isolator handle 713 at the top, and the second actuating member 852 has a gripping structure. After the second movable member 851 is located in the respective position of the radiation isolator 710, the second movable member 851 extends, and the gripping structure can extend into the isolator handle 713 for locking fit. The second movable member 851, after rising, can carry the radiation isolator 710 to rise together in the second direction, and can carry the radiation isolator 710 to descend after moving to the respective position of the second radiation shielding device 700, such that the radiation isolator 710 enters the second radiation shielding device 700, and then the gripping structure releases. In particular, the second movable member 851 may be driven to extend and retract by a second power member (not shown) in the form of a cylinder or the like, and the second actuator 852 may be electrically connected to the driving mechanism by a second drag chain 853. It will be easily understood that the second movable member 851 may also be in other forms that would readily occur to those skilled in the art to drive the second actuating member 852 to move.

[0091] Referring to FIG. 12, FIG. 12 shows a schematic structural diagram of the second radiation shielding device 700 and the third actuator 860 according to one embodiment. The fourth guide 531 may be disposed within the box of the second radiation shielding device, the second radiation shielding device 700 may be provided with a second openable member 720 that can be opened or closed. The second openable member 720 is used to cover the second accommodating cavity of the second radiation shielding device 700. The transfer device 800 may further include a third actuator 860 movably connected to the moving member 820. The third actuator 860 can open or close the second openable member 720, and the third actuator 860 can be moved together with the moving member 820 in the first direction. The second openable member 720 may be a cover disposed over the second radiation shielding device 700, the second openable member 720 can be rotationally hinged to or separated from the second radiation shielding device 700 to be opened and closed. When the third actuator 860 moves to the position of the second radiation shielding device 700, the second openable member 720 can be opened. In one possible implementation, the second openable member 720, when being opened, can be separated from the second radiation shielding device 700, and in this case the third actuator 860 can pick up the second openable member 720 and carry the second openable member for movement after the second openable member 720 is opened. The second radiation shielding device 700 may further be provided with a second radiation shielding device handle 730 to facilitate movement of the second radiation shielding device by the operator.

[0092] In some embodiments, the third actuator 860 includes a third actuating member 862 that can open or close the second openable member 720. Further, the third actuator 860 further includes an extendable third movable member 861 which is extendable. It will be easily understood that with reference to the form of the first and second actuators, the third movable member 861 can extend and retract in the second direction, and a fixed end of the third movable member 861 is movably connected to the moving member 820 by means of sliding connection or rotational connection. A movable end of the third movable member 861 is connected to the third actuating member 862. In the second direction, when the third movable member 861 moves to the preset position relative to the base 830, the third actuating member 862 can reach the second openable member 720 and opens or closes the second openable member 720. In one possible implementation, the third actuating member 862 is controlled by a third power member 864 to open and close the second openable member 720, for example, by means of a cylinder. Illustratively, an electrical connection can be achieved by a third drag chain 863. The provision of the third drag chain 863 allows to ensure that the cables are not damaged during movement, to extend the service life, and the air pipes of the cylinder can also be protected by the third drag chain 863. In one embodiment, the second openable member 720 is provided with a second openable member handle 721. In this case, the third actuating member 862 is a gripping structure that can grip the second openable member handle 721, such as an expandable or contractible manipulator. After the manipulator grips the second openable member handle 721, the third movable member 861 is retracted to open the second openable member 720, and the third movable member 861 extends to close the second openable member 720.

[0093] In some embodiments, the first radiation shielding device 600, the second radiation shielding device 700 and the radiation isolator 710 are disposed in sequence. Correspondingly, the first actuator 840, the third actuator 860 and the second actuator 850 are disposed in sequence. In particular, when the moving member 820 moves relative to the base 830 to a third position of the base (see FIG. 18), the position of the first radiation shielding device 600 corresponds to the position of the first actuator 840, the position of the third actuator 860 corresponds to the position of the second radiation shielding device 700, and the position of the second actuator 850 corresponds to the position of the radiation isolator 710, such that at this time the first actuator 840 can pick up the radioactive material / neutron generation unit in the first accommodating cavity of the first radiation shielding device 600, and preferably, the third actuator 860 can open the second openable member 720 and the second actuator 850 can pick up the radiation isolator 710 at the same time. In this configuration, a plurality of tasks can be performed concurrently within the same period of time, and the plurality of actuators perform synchronous adjustment and alignment operations directly without positional adjustments, reducing individual operating steps and operating time for individually adjusting and aligning each component, significantly shortening the operating time, improving the operating efficiency, contributing to reducing radiation exposure, and enhancing environmental safety indicators.

[0094] When the first radiation shielding device 600, the second radiation shielding device 700 and the radiation isolator 710 are disposed in sequence and the first actuator 840, the third actuator 860 and the second actuator 850 are also disposed in sequence, the positions of the moving member 820 relative to the base 830 includes a third position, a fourth position, and a fifth position (see FIGS. 18-20, where FIG. 18 is a schematic diagram of the moving member 820 in the third position, FIG. 19 is a schematic diagram of the moving member 820 in the fourth position, and FIG. 20 is a schematic diagram of the moving member 820 in the fifth position, with the components shown for illustrative purposes only).

[0095] When the moving member 820 is located in the third position in the base 830 (which is a fixing member and not shown in FIGS. 18-20), the position of the first actuator 840 corresponds to the position of the first radiation shielding device 600, the position of the third actuator 860 corresponds to the position of the second radiation shielding device 700, and the position of the second actuator 850 corresponds to the position of the radiation isolator 710. When the moving member 820 moves from the third position to the fourth position in the first direction, the position of the first actuator 840 corresponds to the position of the second radiation shielding device 700. When the moving member 820 moves from the fourth position to the fifth position in the first direction, the position of the second actuator 850 corresponds to the position of the second radiation shielding device 700.

[0096] In some embodiments, referring to FIG. 10 together, the moving member 820, when being driven, may be slidably connected to base 830. Illustratively, the base 830 may further be provided with guide rails 821 on which the moving member 820 can slide, such that the moving member 820 is slidably connected to the base 830. The moving member 820 can operatively move relative to the base 830 to the respective positions of the first radiation shielding device 600 and the second radiation shielding device 700.

[0097] On the basis of the same inventive concept, the embodiments of the present application further provide a radioactive material transfer method for the radioactive material transfer system described above. The solution provided by this transfer method to solve the problem is similar to that cited in the above radioactive material transfer system. Therefore, for specific definitions in one or more radioactive material transfer methods provided below, reference may be made to the above definitions of the radioactive material transfer system, which are not repeated herein.

[0098] The present application further discloses a radioactive material transfer method for use in a radioactive material transfer system. The radioactive material transfer system includes a first radiation shielding device 600, a second radiation shielding device 700, and a transfer device 800. The radioactive material transfer method includes: operatively transferring a radioactive material 300 from the first radiation shielding device 600 into the second radiation shielding device 700 by the transfer device 800. The present application further discloses a radioactive material transfer system for use in a neutron capture system. In the radioactive material transfer system, the radioactive material that needs to be transferred is a neutron generation unit, where the transfer method for the neutron generation unit further includes: operatively transferring the neutron generation unit 300 from the first radiation shielding device 600 into the second radiation shielding device 700 by the transfer device 800.

[0099] In one embodiment, the neutron generation unit transfer system further includes a positioning system, and the neutron generation unit transfer method further includes: positioning the first radiation shielding device 600 and / or the second radiation shielding device 700 relative to the transfer device 800 by the positioning system.

[0100] When the transfer device 800 has a large size or mass and is difficult to move, the positions of the first radiation shielding device 600 and the second radiation shielding device 700 are the preset positions relative to the transfer device 800 in order to transfer the neutron generation unit 300. The transfer device 800 has a fixed dimension and can transfer the neutron generation unit only when the first radiation shielding device 600 and the second radiation shielding device 700 move to the preset positions. The first radiation shielding device 600 and / or the second radiation shielding device 700 move to the preset positions and are positioned by the positioning system, and then the neutron generation unit 300 is transferred by the transfer device 800. In one possible implementation, the first radiation shielding device 600 and / or the second radiation shielding device 700 have a movable portion 630, and a movable portion control device 640 controls the movable portion 630 to move.

[0101] In one embodiment, the transfer device includes a base 630 and a moving member 620, and the neutron generation unit transfer method includes: controlling the moving member 620 to move on the base 630 from a respective position of the first radiation shielding device 600 to a respective position of the second radiation shielding device 700.

[0102] The moving member 620, when being driven, can operatively move relative to the base 630, and can move to the respective positions of the first radiation shielding device 600 and the second radiation shielding device 700 to transfer the neutron generation unit 300. Illustratively, the moving member 820 is slidably connected to the base 830.

[0103] In one embodiment, the transfer device 800 includes a first actuator 840. The first actuator 840 movably disposed on the moving member 820. The first actuator 840 can be moved relative to the base 830 together with the moving member 820. The neutron generation unit transfer method includes: controlling the moving member 820 to drive the first actuator 840 to move relative to the base 830 to the respective position of the first radiation shielding device 600, and controlling the first actuator 840 to obtain the neutron generation unit 300 in the first radiation shielding device 600; and controlling the moving member 820 to drive the first actuator 840 to move relative to the base 830 so as to drive the neutron generation unit 300 to move to the respective position of the second radiation shielding device 700, and controlling the first actuator 840 to release the neutron generation unit 300 to the second radiation shielding device 700.

[0104] The first actuator 840 can pick up or release the neutron generation unit 300 to transfer the neutron generation unit 300. As the moving member 820 moves in the first direction relative to the base 830, the first actuator 840 can be moved together with the moving member 820. The first direction may be a direction of movement from an opening of the first accommodating cavity of the first radiation shielding device 600 to an opening of the second accommodating cavity of the second radiation shielding device 700. The first direction may be a preset direction in which the moving member 820 moves along the base 830, for example, in a horizontal direction parallel to the base 830, such that the first actuator 840 can reach the respective position of the first radiation shielding device 600 and the respective position of the second radiation shielding device 700, for example, directly above or diagonally above them. Illustratively, the first actuator 840 moves on the base 830 above the first radiation shielding device 600, picks up the neutron generation unit 300 located in the first accommodating cavity and then moves above the second radiation shielding device 700 to release the neutron generation unit to the second accommodating cavity to transfer the neutron generation unit 300.

[0105] In one embodiment, the neutron generation unit transfer system further includes a radiation isolator 710 and a second actuator 850. The second actuator 850 is movably disposed on the moving member 820. The neutron generation unit transfer method further includes: controlling the moving member 820 to drive the second actuator 850 to move relative to the base 830 to the respective position of the radiation isolator 710 to obtain the radiation isolator 710; and controlling the moving member 820 to drive the second actuator 850 to move relative to the base 830 so as to drive the radiation isolator 710 to move to the respective position of the second radiation shielding device 700, and releasing the radiation isolator 710 to the second radiation shielding device 700.

[0106] The radiation isolator 710 can be disposed in the second accommodating cavity together with the neutron generation unit 300 to isolate the neutron generation unit 300 and reduce its radiation contamination to the outside. In the first direction, the second actuator 850 can move relative to the base 830 to the respective position of the radiation isolator 710 and the respective position of the second radiation shielding device 700. The second actuator 850 can pick up or release the radiation isolator 710 such that the radiation isolator 710 can be picked up when the second actuator 850 is transferred to the respective position of the radiation isolator 710. After the neutron generation unit is placed in the second accommodating cavity of the second radiation shielding device 700, the second actuator 850 is transferred to the respective position of the second radiation shielding device 700 and then places the radiation isolator 710 into the second accommodating cavity.

[0107] In one embodiment, the neutron generation unit transfer system further includes a third actuator 860. The third actuator 860 is movably disposed on the moving member 820. The second radiation shielding device 700 has a second openable member 720. The neutron generation unit transfer method further includes: controlling the moving member 820 to drive the third actuator 860 to move relative to the base 830 to the respective position of the second radiation shielding device 700, and closing the second openable member 720 by the third actuator 860.

[0108] The neutron generation unit transfer system further includes a second openable member 720 for covering the second accommodating cavity of the second radiation shielding device 700, and the second openable member 720 can be opened or closed. The transfer device 800 further includes a third actuator 860 movably connected to the moving member 820. The third actuator 860 can open or close the second openable member 720, and the third actuator 860 can be moved together with the moving member 820 in the first direction. The second openable member 720 may be a cover disposed over the second radiation shielding device 700, the second openable member 720 can be rotationally hinged to or separated from the second radiation shielding device 700. When the third actuator 860 moves to the position of the second radiation shielding device 700, the second openable member 720 can be opened. In one possible implementation, the second openable member 720, when being opened, can be separated from the second radiation shielding device 700, and in this case the third actuator 860 can pick up the second openable member 720 and carry the second openable member for movement after the second openable member 720 is opened.

[0109] Referring to FIG. 15, FIG. 15 shows a radioactive material / neutron generation unit transfer method according to one embodiment, the method including: step S1302, positioning the first radiation shielding device 600 and / or the second radiation shielding device 700 relative to the transfer device 800 by the positioning system; step S1304, controlling the moving member 820 to drive the first actuator 840 to move relative to the base 830 to the respective position of the first radiation shielding device 600, and controlling the first actuator 840 to obtain the radioactive material / neutron generation unit 300 in the first radiation shielding device 600; step S1306, controlling the moving member 820 to drive the first actuator 840 to move relative to the base 830 so as to drive the radioactive material / neutron generation unit 300 to move to the respective position of the second radiation shielding device 700, and controlling the first actuator 840 to release the radioactive material / neutron generation unit 300 to the second radiation shielding device 700; step S1308, controlling the moving member 820 to drive the second actuator to move relative to the base 830 to the respective position of the radiation isolator 710 to obtain the radiation isolator 710; step S1310, controlling the moving member 820 to drive the second actuator to move relative to the base 830 so as to drive the radiation isolator 710 to move to the respective position of the second radiation shielding device 700, and releasing the radiation isolator 710 to the second radiation shielding device 700; and step S1312, controlling the moving member 820 to drive the third actuator to move relative to the base 830 to the respective position of the second radiation shielding device 700, and closing the second openable member 720 by the third actuator 860.

[0110] In this embodiment, the first radiation shielding device 600 and the second radiation shielding device 700 are first moved to the preset positions of the transfer device 800 by the positioning system, the moving member 820 is then controlled to move to the respective position of the first radiation shielding device 600, and the radioactive material / neutron generation unit 300 in the first radiation shielding device 600 is picked up by the first actuator 840. Then, the moving member 820 is controlled to drive the first actuator 840 to move to the respective position of the second radiation shielding device 700, to release the radioactive material / neutron generation unit 300 into the second radiation shielding device 700 by the first actuator 840. The moving member 820 is then controlled to move to the respective position of the radiation isolator 710, and after the radiation isolator 710 is picked up by the second actuator 850, the moving member 820 is controlled to move into the second radiation shielding device 700, to release the radiation isolator 710 into the second radiation shielding device 700 so as to shield the radioactive material / neutron generation unit 300. Finally, the moving member 820 is controlled to drive the third actuator 860 to close the second openable member 720 of the second radiation shielding device 700, to enclose the radioactive material / neutron generation unit 300. By the above method, the radioactive material / neutron generation unit 300 is safely transferred from the first radiation shielding device 600 into the second radiation shielding device 700.

[0111] Referring to FIG. 16, FIG. 16 shows a flowchart of a radioactive material / neutron generation unit transfer method according to one embodiment. The first radiation shielding device 600 is provided with a first openable member 610'. The first radiation shielding device 600, the second radiation shielding device 700 and the radiation isolator 710 are disposed in sequence, and the first actuator 840, the third actuator 860 and the second actuator 850 are disposed in sequence. The radioactive material / neutron generation unit transfer method further includes: step S1402, opening the first openable member 610' of the first radiation shielding device 600, where when the opening mechanism 611 is provided, the first openable member 610' can be opened by the opening mechanism 611; step S1404, controlling the moving member 820 to move to the third position of the base 830 such that the position of the first actuator 840 corresponds to the position of the first radiation shielding device 600, the position of the third actuator 860 corresponds to the position of the second radiation shielding device 700, and the position of the second actuator 850 corresponds to the position of the radiation isolator 710; step S1406, controlling the first actuator 840 to obtain the radioactive material / neutron generation unit 300 in the first radiation shielding device 600, controlling the third actuator 860 to open the second openable member 720 of the second radiation shielding device 700 for covering, and controlling the second actuator 850 to obtain the radiation isolator 710; step S1408, controlling the moving member 820 to move to the fourth position of the base 830 such that the position of the first actuator 840 corresponds to the position of the second radiation shielding device 700, where the moving member 820 is controlled to move to the fourth position of the base 830 in the first direction. step S1410, controlling the first actuator 840 to release the radioactive material / neutron generation unit to the second radiation shielding device 700; step S1412, controlling the moving member 820 to move to the fifth position of the base 830 such that the position of the second actuator 850 corresponds to the position of the second radiation shielding device 700, and particularly, controlling the moving member 820 to move in the first direction such that the moving member can move to the fifth position of the base 830, in this case the position of the second actuator 850 corresponds to the position of the second radiation shielding device 700; step S1414, controlling the second actuator 850 to release the radiation isolator 710 to the second radiation shielding device 700; step S1416, controlling the moving member 820 to move to the third position of the base 830; and step S1418, controlling the third actuator 860 to close the second openable member 720.

[0112] In this embodiment, preferably, the moving member 820 moves to drive the first actuator 840, the third actuator 860 and the second actuator 850 to move as a whole, and the radioactive material / neutron generation unit is transferred from the first accommodating cavity of the first radiation shielding device 600 into the second accommodating cavity of the second radiation shielding device 700 only by controlling the moving member 820 with no need to separately provide a control assembly for controlling the first actuator 840, the second actuator 850 and the third actuator 860, resulting in a high degree of integration. In other embodiments, the first actuator 840, the second actuator 850 and the third actuator 860 may also be separately controlled and moved, or the three may be integrated into one component, such as a robot arm, to carry out the above transfer of the radioactive material / neutron generation unit.

[0113] FIG. 17 shows a radioactive material / neutron generation unit transfer system according to one embodiment. The system further includes a master control device 1500. The master control device 1500 includes an opening module 1502, a moving member control module 1504, a first execution module 1506, a second execution module 1508, a third execution module 1510, and a movement module 1512.

[0114] The opening module 1502 is configured to control the opening and closing of the opening mechanism 611.

[0115] The moving member control module 1504 is configured to control the moving member 820 to move relative to the base 830 to the third, fourth and fifth positions of the base 830.

[0116] The first execution module 1506 is configured to control the first actuator 840 to pick up or release the radioactive material / neutron generation unit 300.

[0117] The second execution module 1508 is configured to control the second actuator 850 to pick up or release the radiation isolator 710.

[0118] The third execution module 1510 is configured to control the third actuator 860 to open or close the second openable member 720.

[0119] The movement module 1512 is configured to control the first radiation shielding device 600, the second radiation shielding device 700 and the radiation isolator 710 to move to the preset positions. Illustratively, this can be achieved by controlling the movable portion 630 and the mobile carrier 711.

[0120] It should be understood that although the method numbers in the flowchart involved in the embodiments as described above are shown sequentially as indicated by the arrows, the method numbers are not necessarily performed in the order indicated by the arrows. Unless explicitly stated herein, the order, in which these method numbers are performed, is not strictly limited, and these method numbers may be performed in other orders. Moreover, at least some of the numbers in the flowchart involved in the embodiments as described above may include a plurality of method numbers or a plurality of stages. These method numbers or stages are not necessarily performed at the same time and instead they may be performed at different times. These method numbers or stages are not necessarily performed in a sequential order, and instead they may be performed in turn or alternately with other numbers or at least some of steps or stages of the other numbers.

[0121] Referring to FIG. 1, in some embodiments, the radioactive material / neutron generation unit transfer system further includes a display device 870. The display device 870 may be a non-touch display screen or a touch display screen. The display device 870 is electrically connected to the master control device 1500, and is provided with areas corresponding to the opening module 1502, the moving member control module 1504, the first execution module 1506, the second execution module 1508, the third execution module 1510, and the movement module 1512, respectively, such that corresponding areas can be triggered to control corresponding modules to carry out the above radioactive material / neutron generation unit transfer method. Illustratively, the display device 870 may be disposed on the transfer device 800, or may be disposed directly or detachably at other locations in the radioactive material / neutron generation unit transfer system. Particularly, the triggering operation may be a touch operation, a cursor operation, a key operation, or a voice operation. The touch operation may be a touch click operation, a touch press operation, or a touch swipe operation, and the touch operation may be a single touch operation or a multi-touch operation. The cursor operation may be an operation that controls a cursor to click or an operation that controls a cursor to press. The key operation may be a virtual key operation or a physical key operation, etc.

[0122] In a radioactive place, the radioactive material transfer system of the present application is advantageous to transfer one or more radioactive materials a plurality of times or repeatedly within a short period of time with independent operations and high safety. In an exemplary neutron capture therapy system, the transfer system for the neutron generation unit can perform an transfer operation on the neutron generation unit within a flexible time by the structure and method of the above embodiments, without being limited by the number of neutron generation units or the number of transfers.

[0123] It can be understood that the radioactive material to which the present application relates includes, but is not limited to, the neutron generation unit of the neutron capture therapy system, and may also be radioactive materials involved in proton therapy, heavy particle therapy and other particle therapy, and may include radioactive materials in other medical and / or non-medical fields. The structure of and the transfer method for the radioactive material transfer system of the present application that are related to are not limited by the neutron generation unit of the neutron capture therapy system exemplified in the above embodiments.

[0124] Any combination of the technical features of the above embodiments may be possible, and in order to simplify the descriptions, not all possible combinations of the technical features of the above embodiments are described. However, as long as there is no conflict between the combinations of these technical features, they should be considered to be within the scope of the description.

[0125] The above embodiments merely represent several implementations of the present invention, giving specifics and details thereof, but should not be understood as limiting the scope of the present patent of invention. It should be noted that various variations and improvements may also be made by those of ordinary skill in the art without departing from the spirit of the present invention and shall fall within the scope of protection of the present invention. Therefore, the scope of protection of the present patent of invention shall be subjected to the appended claims.

Claims

1. A radioactive material transfer system, <b>characterized by comprising: a first radiation shielding device at least configured to accommodate a radioactive material; a second radiation shielding device at least configured to store the radioactive material; and a transfer device configured to transfer the radioactive material located in the first radiation shielding device into the second radiation shielding device.

2. The radioactive material transfer system according to claim 1, characterized in that the radioactive material transfer system is used in a neutron capture therapy system, the neutron capture therapy system comprising: an accelerator configured to generate a charged particle beam; a transmission device configured to transmit the charged particle beam generated by the accelerator, the transmission device comprising at least a first transmission portion and a second transmission portion, wherein the first transmission portion is detachably connected to the second transmission portion; a neutron generation unit disposed at the first transmission portion and movable together with the first transmission portion, the neutron generation unit being configured to react with the charged particle beam to generate a neutron beam; and a beam shaping assembly configured to adjust an energy spectrum of the neutron beam; wherein the first radiation shielding device is at least configured to accommodate the neutron generation unit, and the transfer device is configured to transfer the neutron generation unit in the first radiation shielding device into the second radiation shielding device.

3. The radioactive material transfer system according to claim 1, characterized in that the transfer device comprises a base and a moving member, the moving member being operatively movable relative to the base.

4. The radioactive material transfer system according to claim 3, characterized in that the transfer device further comprises a first actuator, wherein the first actuator is movably disposed on the moving member and is configured to obtain or release the radioactive material, and at least in a first direction, the first actuator is capable of being moved relative to the base together with the moving member, the first actuator is capable of being moved together with the moving member to a respective position of the first radiation shielding device and a respective position of the second radiation shielding device.

5. The radioactive material transfer system according to claim 4, characterized in that the first actuator comprises a first actuating member configured to obtain or release a radioactive material, and a first movable member connected to the moving member, the first movable member being capable of driving the first actuating member to move.

6. The radioactive material transfer system according to claim 5, characterized in that at least in a second direction, the first movable member is capable of driving the first actuating member to move relative to the moving member to enable a position of the first actuating member relative to the first radiation shielding device and / or the second radiation shielding device to be adjusted to transfer the radioactive material from the first radiation shielding device to the second radiation shielding device.

7. The radioactive material transfer system according to claim 4, characterized by further comprising a radiation isolator and a second actuator, wherein the second actuator is movably disposed on the moving member and is configured to obtain or release the radiation isolator, and at least in the first direction, the second actuator is capable of being moved together with the moving member to a respective position of the radiation isolator and the respective position of the second radiation shielding device.

8. The radioactive material transfer system according to claim 7, characterized in that the second actuator comprises a second actuating member and a second movable member, the second actuating member being capable of obtaining or releasing the radiation isolator, the second movable member being disposed on the moving member, and the second movable member being capable of driving the second actuating member to move.

9. The radioactive material transfer system according to claim 8, characterized in that at least in the second direction, the second movable member is capable of driving the second actuating member to move relative to the moving member to enable a position of the second actuating member relative to the second radiation shielding device and / or the radiation isolator to be adjusted to transfer the radiation isolator to the second radiation shielding device.

10. The radioactive material transfer system according to claim 7, characterized in that the second radiation shielding device comprises a second openable member, and the radioactive material transfer system further comprises a third actuator configured to open or close the second openable member.

11. The radioactive material transfer system according to claim 10, characterized in that the third actuator comprises a third actuating member configured to open or close the second openable member, and a third movable member movably disposed on the moving member, wherein at least in the first direction, the third movable member is capable of driving the third actuating member to move together with the moving member to the respective position of the second radiation shielding device.

12. The radioactive material transfer system according to claim 11, characterized in that at least in the second direction, the third movable member is capable of driving the third actuating member to move relative to the moving member to enable a distance between the third actuating member and the second radiation shielding device to be adjusted to open or close the second openable member.

13. The radioactive material transfer system according to claim 10, characterized in that the first radiation shielding device, the second radiation shielding device and the radiation isolator are disposed in sequence, and the first actuator, the third actuator and the second actuator are disposed in sequence, such that when the moving member is in a third position of the base, a position of the first actuator corresponds to the position of the first radiation shielding device, a position of the third actuator corresponds to the position of the second radiation shielding device, and a position of the second actuator corresponds to the position of the radiation isolator.

14. A radioactive material transfer method for use in a radioactive material transfer system comprising a first radiation shielding device, a second radiation shielding device, and a transfer device, the transfer device comprising a base and a moving member, characterized in that the radioactive material transfer method comprises: controlling the moving member to move on the base from a respective position of the first radiation shielding device to a respective position of the second radiation shielding device; and operatively transferring the radioactive material from the first radiation shielding device into the second radiation shielding device by the transfer device.

15. The radioactive material transfer method according to claim 14, characterized in that the transfer device comprises a first actuator movably disposed on the moving member; the first actuator is capable of being moved relative to the base together with the moving member; and the radioactive material transfer method comprises: controlling the moving member to drive the first actuator to move relative to the base to the respective position of the first radiation shielding device, and controlling the first actuator to obtain the radioactive material located in the first radiation shielding device; and controlling the moving member to drive the first actuator to move relative to the base so as to drive the radioactive material to move to the respective position of the second radiation shielding device, and controlling the first actuator to release the radioactive material to the second radiation shielding device.

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