Neutron-capture therapy system

Abstract

To provide a neutron-capture therapy system having a compact structure and a reasonable layout.SOLUTION: A neutron-capture therapy system includes a charged particle beam generation unit, a beam transmission unit, and a neutron beam generation unit. The charged particle beam generation unit includes an ion source, and an accelerator that accelerates charged particles generated by the ion source so as to obtain a charged particle beam having desired energy. The neutron beam generation unit includes a target, a beam shaping body, and a collimator. The charged particle beam generated by the accelerator irradiates onto the target through the beam transmission unit and acts with the target to generate neutrons. The generated neutrons sequentially pass through the beam shaping body and the collimator to form a neutron beam for therapy. The neutron-capture therapy system is integrally accommodated inside a building constructed by concrete and includes an irradiation chamber, an accelerator chamber, and a beam transmission chamber. The neutron beam generation unit is at least partially accommodated inside a partition wall between the irradiation chamber and the beam transmission chamber.SELECTED DRAWING: Figure 1

Description

[Technical Field]

[0001] The present invention relates to a radiation delivery system, and more particularly to a neutron capture therapy system. [Background technology]

[0002] With the development of atomic science, radiation therapy such as cobalt-60, linear accelerator, and electron beam , which has already become one of the main means of cancer treatment. However, conventional photon or electron therapy, The physical conditions of the radiation itself limit tumor cell death, while the number of cells in the beam path It damages normal tissue and tumor cells have different degrees of sensitivity to radiation. Conventional radiation therapy is effective against highly radioresistant malignant tumors (e.g., glioblastoma multiforme (GLIOB)). Treatment for melanoma (melanoma multiforme) It's not very effective.

[0003] To reduce radiation damage to the normal tissue surrounding the tumor, chemotherapy is used. The concept of targeted therapy in radiation therapy has been applied to radiation therapy, and highly radiation-resistant Currently, there are several biological treatments for tumor cells, such as proton therapy, heavy particle therapy, and neutron capture therapy. Relative biological effectiveness (RB) E) high radiation sources are being actively developed. Of these, neutron capture therapy is For example, in boron neutron capture therapy, boron-containing drugs This technology allows neutrons to specifically collect in tumor cells, and by combining this with highly precise control of the neutron beam, it is possible to achieve a level of efficacy that is superior to conventional radiation. It offers a better cancer treatment option compared to radiation.

[0004] Conventional neutron capture therapy systems are often based on nuclear reactors, which themselves are expensive. It is expensive, its use is limited, there are unsafe factors, the facilities are complicated, and it is difficult to use it for medical purposes. Therefore, it is necessary to provide a new technical means to solve the above problems. Summary of the Invention

[0005] In order to solve the above problem, a neutron capture therapy system according to one aspect of the present invention is a neutron capture therapy system using charged particles. a beam transfer section and a neutron beam generation section, The generating unit includes an ion source that generates charged particles, and a device that applies the charged particles generated by the ion source. and an accelerator for accelerating the neutron beam to obtain a charged particle beam having a desired energy. The beam generating unit includes a target, a beam shaper, and a collimator. The beam transfer unit is disposed between the beam transfer unit and the beam shaping unit, and the load generated by the accelerator is The electron beam is irradiated onto the target by the beam transfer unit, and the target The generated neutrons are then passed through the beam shaper and collimator in order. The neutron capture therapy system passes through a filter to form a therapeutic neutron beam. It is entirely housed in a single-structure building and includes an irradiation room, accelerator room and beam transfer room. The subject injected with the agent is treated by irradiation with the therapeutic neutron beam in the irradiation chamber. The accelerator chamber at least partially accommodates the charged particle beam generating unit, and The beam transfer chamber at least partially accommodates the beam transfer section and the neutron beam generating section. is at least partially contained within a partition wall between the irradiation chamber and the beam transfer chamber. Electron capture therapy systems are based on accelerators, which are safer, more reliable, and more cost-effective. It has a compact structure and rational layout, and can be applied to medical treatment places such as hospitals.

[0006] Preferably, the neutron capture therapy system is connected to a drug control room and to the irradiated subject during irradiation treatment. and a drug injection device for injecting a drug into the body, the drug injection device comprising a drug passage assembly. a drug containment mechanism and a drug control mechanism, and the drug containing mechanism and the drug control mechanism are installed between the drug control chamber and the drug storage chamber. a drug control room for controlling drug injection to the subject; This avoids operation inside the irradiation chamber, improving safety and reliability, and It is possible to prevent neutron radiation from affecting the drug-containing mechanism and drug-control mechanism. do.

[0007] Furthermore, the drug passage assembly includes a drug passage member for injecting a drug; and a receiving member for at least partially receiving the storage member, the receiving member being disposed within the partition wall. and the drug passage member defines a passageway through the partition wall.

[0008] Preferably, the neutron capture therapy system comprises a treatment couch, a treatment couch positioning device and a treatment device for the treatment couch. The treatment table positioning device further includes a shielding device. The shielding device of the treatment table positioning device is a neutron capture device. Exposure to treatment couch positioning equipment of neutrons and other radiation generated by capture therapy systems Wire damage can be reduced or avoided, extending service life.

[0009] Further, the treatment couch positioning device supports and positions the treatment couch and includes at least one and the shielding device is a robot arm that encases the arm. Includes arm protection covers.

[0010] Furthermore, the robot arm protective cover is provided with a collision prevention protection mechanism, or , the treatment table positioning device further includes a linear axis, and the robot arm is and the treatment table, and the linear axis is connected to a slide rail fixed in the building. and a support table connected to the robot arm, the support table being configured to support the treatment table and The robot arm is driven to slide along the slide rail, and the shielding device The slide rail cover member is a cover member for covering the slide rail. The radiation leakage caused when sliding along the rail can be reduced.

[0011] Preferably, a neutron shielded space is formed in the building, and the neutron shielded space is The concrete is formed in the beam transfer chamber or the irradiation chamber, and contains boron and barite. or the concrete has a neutron shielding layer on the surface to form the neutron shielding space. During the neutron capture therapy process, a large amount of radiation is emitted, especially near the neutron beam generator. In order to generate a large amount of neutrons, a neutron shielding space is installed to prevent neutron leakage or and to avoid or reduce as much as possible radiation damage and contamination to other equipment within the system.

[0012] Preferably, within the building, there are cables for the operation of the neutron capture therapy system, or Tubular members for the passage of gases and liquids, or rod-shaped members for fixing and mounting within said structures, or A support device for supporting the cable or tubular member is provided, and the support device, the tubular member, 90% (by weight) or more of the material of the bar or rod-shaped member is C, H, O, N, Si, Al At least one element selected from the group consisting of Mg, Li, B, Mn, Cu, Zn, S, Ca, and Ti The tubular member, the fixed rod and the cable, the support device of the tubular member are installed, and the neutron By selecting materials that generate less secondary radiation after irradiation, radiation damage can be reduced. and radiation contamination of the cable, tubular member or rod-shaped member can be reduced. An annular shielding device is provided on the outer periphery, and the annular shielding device comprises an inner sleeve, an outer sleeve, and and a shielding material disposed between the inner sleeve and the outer sleeve, and an annular shielding device is provided. By installing a neutron capture therapy system in the building, Reduce radiation damage and contamination to installed cables, tubular members and fixation rods. can be done.

[0013] Preferably, the neutron capture therapy system is located in the accelerator room or the beam transfer chamber. At least partially installed, cooling equipment, or insulating gas charging and recovery equipment, or compressed air and auxiliary equipment including an air compressor to provide a vacuum environment or a vacuum pump to provide a vacuum environment. .

[0014] Furthermore, the cooling medium of the cooling device has a hardness of less than 60 mg / L, and By cooling the assemblies of the neutron capture therapy system that need to be cooled, the service life of the device can be extended. The cooling medium of the cooling device is soft water, so that the water pipes are not affected by the cooling process. Scale formation is unlikely to affect heat exchange efficiency.

[0015] Furthermore, the cooling device is used to cool the ion source, accelerator, or target. The hardness of the cooling medium is less than 17 mg / L, or the cooling medium is deionized water, The conductivity of the deionized water is 0.5 to 1.5 μS / cm, or the cooling device is an external a circulation device, an internal circulation device, and a heat exchanger, and the internal circulation device supplies a cooling medium to the neutral The assembly is transported to the assembly to be cooled in the electron capture therapy system, where it absorbs heat, and then the temperature rises after the absorption of heat. The cooling medium is transported to the heat exchanger from the external circulation device. The cooling medium is then cooled by heat exchange with the incoming cold water, and the cooled cooling medium is transported to the assembly to be cooled. The external circulation device continuously supplies the cold water to the heat exchanger, and after absorbing heat, The heated cold water can be recovered.

[0016] The accelerator further includes an accelerator high voltage power supply that provides acceleration energy, The provision of insulating gas inside the high voltage power supply may destroy electronic components inside the accelerator high voltage power supply. The insulating gas filling and recovery device supplies the insulating gas to the accelerator high voltage power supply to avoid this. providing or recovering said insulating gas from said accelerator high voltage power supply, maintaining and Since the insulating gas can be recovered when inspecting the insulation gas, the utilization rate of the insulating gas is improved.

[0017] Furthermore, the insulating gas filling and recovery device includes a gas source, and a gas supply device for supplying and recovering insulating gas to and from the accelerator high pressure. and a storage container connected to a piezoelectric power source, the gas source containing the insulating gas. This includes containers that have been

[0018] A neutron capture therapy system according to a second aspect of the present invention includes a charged particle beam generator and a beam a transfer unit and a neutron beam generating unit, the charged particle beam generating unit generating a charged particle beam and the beam transfer unit transfers the charged particle beam to the neutron beam generation unit. The neutron beam generating unit generates a therapeutic neutron beam and controls the neutron capture therapy system. The stem is entirely housed within a concrete structure, and the neutral A cable for operating a child capture therapy system, or a tubular member for passing gases and liquids, or A rod-shaped member for fixing and mounting inside the building is installed, and the cable, tubular member or rod-shaped member An annular shielding device is installed on the outer periphery of the component. By installing the annular shielding device, neutron capture Cables, tubular components and solid objects installed in buildings for the detection of neutrons generated by capture therapy systems Radiation damage and contamination to the fixed rod can be reduced.

[0019] Preferably, the annular shielding device comprises an inner sleeve, an outer sleeve, and a sleeve for supporting the inner sleeve. The shielding material is disposed between the shaft and the outer sleeve.

[0020] Furthermore, 90% (weight percent) or more of the material of the inner sleeve or outer sleeve C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, Ca, Ti It consists of at least one of these elements.

[0021] Furthermore, the material of the inner sleeve or the outer sleeve is PVC.

[0022] Furthermore, the outer sleeve is a neutron moderator, and the neutrons after moderation are shielded by a shielding material. can be absorbed better.

[0023] Furthermore, the shielding material is made of a neutron shielding material.

[0024] Furthermore, the shielding material is a boron-containing resin.

[0025] Preferably, the tubular member is a ventilation pipe or a fire pipe, and the rod-shaped member is a support rod. It is a rod or screw.

[0026] Preferably, the charged particle beam generating unit includes an accelerator, and the neutron beam generating unit The section includes a target, a beam shaper, and a collimator, and the target A charged particle beam generated by the accelerator is provided between the transfer unit and the beam shaper. The beam is irradiated onto the target by the beam transfer unit and interacts with the target to form a central beam. The generated neutrons pass through the beam shaper and collimator in order. to form a therapeutic neutron beam.

[0027] Furthermore, the beam shaper may include a reflector, a moderator, a thermal neutron absorber, a radiation shield, and a beam a beam outlet, the moderator converting neutrons generated in the target into epithermal neutron energy The reflector surrounds the moderator and directs the escaping neutrons away from the moderator. The thermal neutron absorber absorbs the thermal neutrons and returns them to the original state to improve the intensity of the epithermal neutron beam. This prevents excessive doses from being given to superficial normal tissue during treatment, and A body is placed behind the reflector surrounding the beam exit to block escaped neutrons and photons. The collimator shields the beam to reduce the dose to normal tissue in the non-irradiated area. It is installed at the rear of the exit and focuses the neutron beam.

[0028] A neutron capture therapy system according to a third aspect of the present invention includes a charged particle beam generator and a beam a transfer unit and a neutron beam generating unit, the charged particle beam generating unit generating a charged particle beam and the beam transfer unit transfers the charged particle beam to the neutron beam generation unit. The neutron beam generating unit generates a therapeutic neutron beam and controls the neutron capture therapy system. The system is entirely housed within a concrete structure building, including an irradiation room and a drug control room. The subject injected with the drug is then treated by neutron beam irradiation in the irradiation chamber. The irradiation room has a partition wall separating it from the drug control room, and the neutron capture therapy system The drug injection system includes a drug passage assembly disposed between the drug control chamber and the irradiation chamber. The drug passage assembly further includes a drug passage member for injecting a drug, and a drug passage member. and a housing member that at least partially houses the partition wall. The drug passage member is disposed within the partition wall, and forms a passageway through the partition wall. The irradiation device injects the drug into the subject in the irradiation chamber through a drug passage assembly that passes through the partition wall. To avoid manipulation inside the irradiation chamber, improve safety and reliability, and install the storage member. This allows for easy passage of the chemical-passing member, while preventing dust and other substances from penetrating the chemicals through the concrete wall. This prevents contamination of the passing member.

[0029] Preferably, the drug injection device injects a drug into the subject during radiation treatment.

[0030] Preferably, the drug injection device further includes a drug containing mechanism and a drug control mechanism, The drug containing mechanism and the drug control mechanism are installed in the drug control room, and By controlling the injection of the drug into the subject, the neutron radiation in the irradiation chamber is It is possible to avoid affecting the drug-containing mechanism and drug-control mechanism. The drug passage member is connected to the drug containing mechanism and allows the drug to pass through the drug control mechanism. Inject into the irradiated body.

[0031] Preferably, the housing member is installed in a through hole in the thickness direction of the partition wall. .

[0032] Furthermore, the central axis of the through hole is perpendicular to the ground along the thickness direction of the partition wall. It can cross both perpendicular planes to reduce radiation leakage.

[0033] Furthermore, from the center of the through hole in the first side wall of the partition wall facing the drug control chamber The distance from the through hole to the ground is greater than the distance from the center to the ground.

[0034] Furthermore, the number of the through holes is two or more, and one of the through holes may be blocked or have other problems. If a problem occurs, there is a backup.

[0035] Preferably, the material of the container is PVC, and the generated after irradiation by neutrons The article is non-radioactive or has very low radioactivity, reducing the secondary radiation generated.

[0036] Preferably, the drug passage member is at least partially made of a neutron shielding material and is irradiated. It is possible to reduce the effect of neutron radiation in the irradiation chamber on the boron-containing agent in the agent-passing member. can.

[0037] A neutron capture therapy system according to a fourth aspect of the present invention includes a charged particle beam generator and a beam a transfer unit and a neutron beam generating unit, the charged particle beam generating unit generating a charged particle beam and the beam transfer unit transfers the charged particle beam to the neutron beam generation unit. The neutron beam generating unit generates a therapeutic neutron beam and controls the neutron capture therapy system. The stem is entirely contained within a concrete structure building, and the concrete structure building A neutron shielding space is formed within the structure. In the neutron capture therapy process, the neutron beam Since a large amount of neutrons is generated near the generating part, a neutron shielding space is installed to Avoid as much as possible the leakage of protons or radiation damage and contamination to other equipment in the room. Reduce.

[0038] Preferably, the neutron capture therapy system includes an irradiation chamber and a beam transfer chamber, The beam transfer chamber at least partially accommodates the beam transfer section and the neutron beam generating section. is at least partially accommodated within a partition wall between the irradiation chamber and the beam transfer chamber, A neutron shielding space is formed in the beam transfer chamber or the irradiation chamber.

[0039] Preferably, a neutron shielding space is formed on the surface of the concrete. A sub-shield is installed.

[0040] Furthermore, the neutron shielding plate is installed on the surface of the concrete by a support assembly. The support assembly has one side connected to the concrete and the other side connected to the neutron shield. is connected to the plate.

[0041] Furthermore, the neutron shielding plate is a boron-containing PE plate. The material is aluminum alloy, and the support assembly is made of two L-shaped It is a plate-like member.

[0042] Preferably, the neutron capture therapy system further includes an auxiliary device, A neutron shielding plate is installed around the device to form the neutron shielding space, and the neutron capture therapy process is performed. This reduces radiation damage and contamination to auxiliary equipment from neutrons during the process.

[0043] Furthermore, the charged particle beam generating unit includes an ion source that generates charged particles, and a Accelerating the charged particles generated by the source to obtain a charged particle beam with a desired energy and an accelerator, the neutron capture therapy system further including an accelerator room and a beam transfer room. The accelerator chamber at least partially accommodates the charged particle beam generating unit, and the beam a beam transfer chamber at least partially housing the beam transfer section, and the auxiliary device The beam transfer chamber is at least partially located within the chamber.

[0044] Furthermore, an auxiliary device housing chamber is provided to house or surround the auxiliary device, The chamber is at least partially comprised of a support assembly and a front end secured to the support assembly. It is composed of the above neutron shielding plate.

[0045] Furthermore, the auxiliary device housing chamber includes a door and a movement mechanism therefor, and the movement mechanism includes: The operator opens the door to enter the auxiliary equipment chamber and easily inspect the equipment. It is possible.

[0046] Furthermore, the movement mechanism includes a guide rail and a slide rod, and the door is The slide rod allows the rod to slide horizontally along the guide rail. Cut.

[0047] Furthermore, the moving mechanism further includes a lifting assembly and a pulley, The door lifting assembly moves the pulley to the door by lifting the door vertically. The door can be placed at the bottom of the pulley, so that the door can slide horizontally. This makes it possible to save more labor.

[0048] A neutron capture therapy system according to a fifth aspect of the present invention includes a charged particle beam generator and a beam a transfer unit, a neutron beam generating unit, a treatment table, and a treatment table positioning device, The child beam generating unit generates a charged particle beam, and the beam transferring unit transfers the charged particle beam. the neutron beam generator to generate a therapeutic neutron beam. and the treatment table positioning device is a robotic arm that supports and positions the treatment table. the neutron capture therapy system further includes a shielding device for the treatment couch positioning device. the robot arm includes at least one arm portion, and the shielding device includes The robot arm protection cover is included. The shielding device of the treatment table positioning device is for treatment couch positioning devices for neutrons and other radiation generated by neutron capture therapy systems This reduces radiation damage and extends the service life of the device.

[0049] Preferably, the material of the robot arm protective cover is at least partially neutron shielding. The arm and the metal components and electronic devices in the mechanism installed on the arm are materials. It prevents the robot from being activated by neutrons and breaking down or being damaged. The material of the protective cover of the arm is at least partially a boron-containing glass fiber resin composite. The glass fiber composite material has a certain strength and is not easily activated by neutrons. Boron is capable of absorbing neutrons.

[0050] Preferably, the treatment table positioning device further includes a linear axis, and the robot arm The treatment table is connected to the linear shaft. and can move parallel along the linear axis together with the robot arm. The neutron capture therapy system includes an irradiation chamber and a preparation chamber, and the linear axis is a slide rail fixed in the chamber or preparation chamber, and a support base connected to the robot arm; The support base slides along the slide rail, and the shielding device is A slide rail moves together with the support base and always covers the exposed portion of the slide rail. Includes a roller cover member.

[0051] Preferably, the robot arm protective cover is integrally and fixedly connected to the arm portion. Furthermore, the first case and the second case are made of a material is a boron-containing glass fiber resin composite material, and the glass fiber composite material has a certain strength. The boron absorbs neutrons and is difficult to activate by neutrons. Metallic components and electronic devices installed in the mechanism of the building are activated by neutrons and break down. This can prevent the device from being damaged or destroyed.

[0052] Preferably, the robot arm protective cover is integrally and fixedly connected to the arm portion. and a first case and a second case which are fixedly connected together. and a third case and a fourth case that enclose the first case. and the third case and / or the second case and the fourth case. The device further includes a collision prevention protection mechanism.

[0053] Furthermore, the material of the first case and the second case is a boron-containing glass fiber resin composite material. The material of the third case and the fourth case is a glass fiber resin composite material, The case of the sensor is made of an aluminum alloy, or the third case and the fourth case are made of aluminum alloy. The material is a boron-containing glass fiber resin composite material, and the glass fiber composite material has a certain The boron has strength and is difficult to be activated by neutrons. The boron absorbs neutrons and The metal parts and electronic devices in the mechanism installed in the arm are activated by neutrons. It can be prevented from breaking down or being damaged.

[0054] Furthermore, a power supply and a power source for the sensor are provided at a position corresponding to the sensor in the third or fourth case. Through-holes will be installed for communication cables to pass through.

[0055] Furthermore, the first case and the second case are provided with a housing cavity for housing the sensor. The sensor is installed in the receiving cavity, and the first case and the third case and / or between the second case and the fourth case by means of an interference fit.

[0056] Furthermore, between the first case and the third case and / or between the second case and the fourth case a gap through which the sensor is attached or through which the power supply and communication cables of the sensor pass; It will be installed.

[0057] Furthermore, the collision prevention protection mechanism includes a sensor control assembly and a human-machine interface. the sensor is a pressure sensor, and the third case or the fourth case further includes a surface. The pressure received by the pressure sensor is converted into a pressure signal and transmitted to the sensor control assembly. providing a numerical display on a human-machine interface of the pressure signal received by said sensor; If the pressure signal exceeds a predetermined value, the pressure signal exceeding the predetermined value is preferentially transmitted to the sensor control assembly. and provides a warning indication on the human machine interface.

[0058] Preferably, the treatment table positioning device is installed on the robot arm protection cover. or a sensor installed between the robot arm protective cover and the arm portion. The device further includes a collision prevention protection mechanism.

[0059] Furthermore, the collision prevention protection mechanism includes a sensor control assembly and a human-machine interface. and a sensor control assembly for transmitting a signal transmitted from the sensor to the sensor control assembly. and displaying the sensor control assembly on the human machine interface. , and performs corresponding control based on the received signal.

[0060] Furthermore, the treatment table positioning device further includes a drive mechanism, The robot system is connected to the drive mechanism and controls the drive mechanism to move the robot. a treatment table control device for controlling the movement of the arm, The received signal is transferred to the treatment table control device to perform the corresponding control.

[0061] A neutron capture therapy system according to a sixth aspect of the present invention includes a charged particle beam generator and a beam a transfer unit, a neutron beam generating unit, a treatment table, and a treatment table positioning device, The child beam generating unit generates a charged particle beam, and the beam transferring unit transfers the charged particle beam. the neutron beam generator to generate a therapeutic neutron beam. and the neutron capture therapy system is entirely contained within a concrete building. the treatment table positioning device includes a linear axis and a robotic arm, The arm is installed between the linear shaft and the treatment table to support and position the treatment table. The linear axis is connected to a slide rail fixed in the building and the robot arm. and a support table mounted on the treatment table, the support table being configured to support the treatment table and the robot arm together. The neutron capture therapy system is driven to slide along a rail, and the treatment table position The locking device further includes a shielding device for the locking device, the shielding device including a slide rail cover member. The shielding device of the treatment table positioning device is designed to protect against neutrons generated by the neutron capture therapy system and other Reduce or avoid radiation damage to radiation treatment couch positioning devices and extend their useful life. The slide rail cover member can be attached to the support base when the support base slides along the slide rail. This can reduce radiation leakage caused by the

[0062] Preferably, the material of the slide rail cover member includes a neutron shielding material.

[0063] Preferably, the neutron capture therapy system includes an irradiation chamber, and the object to be irradiated is The patient is treated by irradiating the neutron beam in the irradiation chamber, and the slide rail is The device is fixed to a fixed surface within the device.

[0064] Furthermore, the slide rail cover member moves together with the support base and Always cover exposed areas of the drain.

[0065] Preferably, a neutron shielding plate is provided on the fixed surface, and the slide rail cover member is installed between the support base and the neutron shielding plate.

[0066] Preferably, the slide rail cover members each include a flat plate connected in sequence. It includes a first part and a second part.

[0067] Furthermore, each of the flat plates is connected to the other in a slidable or pivotable manner.

[0068] Furthermore, the slide rail cover member is a support member for the slide rail cover member. The first and second parts are supported by the support base along the sliding direction of the support base. One adjacent end is fixedly connected to the support base and the other end is fixedly connected to the support member.

[0069] Furthermore, the material of the support member is such that the product after irradiation with neutrons is radioactive. or the radioactivity of the product after irradiation with neutrons is very low, or The neutron shield is a material in which the half-life of the radioisotope produced after irradiation is short, and , covering the support member, or the material of the support member includes a neutron shielding material, The neutron shielding plate is fitted to the support member.

[0070] A neutron capture therapy system according to a seventh aspect of the present invention includes a charged particle beam generator and a beam a transfer unit and a neutron beam generating unit, the charged particle beam generating unit generating a charged particle beam and the beam transfer unit transfers the charged particle beam to the neutron beam generation unit. The neutron beam generating unit generates a therapeutic neutron beam and controls the neutron capture therapy system. The stem is entirely housed within a concrete structure, and the neutral A cable for operating a child capture therapy system, or a tubular member for passing gases and liquids, or Rods for fixing and mounting within buildings or for supporting said cables or tubular members A support device is provided for supporting the tubular or rod-shaped member. The support device is made of 90% (parts by weight) of the material of the tubular or rod-shaped member. (cent) or more are C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, The tubular member, the fixing rod and the case are made of at least one element selected from the group consisting of S, Ca and Ti. Secondary radiation generated after the support device for the tubular member was installed and irradiated by neutrons. By selecting materials with low radiation damage and contamination, radiation damage and contamination can be reduced. .

[0071] Preferably, the material of the support device, tubular member or rod-shaped member is an aluminum alloy or a plastic. It is plastic or rubber.

[0072] Preferably, the support device includes a conduit for passing and supporting the cable. The conduit extends along the extending direction of the cable and is The nozzle is at least partially sealed in the circumferential direction around the nozzle.

[0073] Furthermore, the cross section of the conduit perpendicular to the extending direction of the cable may be circular, polygonal, or the like. , V-shaped, horizontal V-shaped, U-shaped or horizontal U-shaped.

[0074] Furthermore, the conduit is fixed to a wall, floor board, or ceiling board in the building by a connecting member. can be.

[0075] Furthermore, the neutron capture therapy system includes an irradiation room, an accelerator room, and a control room, The body is treated by irradiation with the neutron beam in the irradiation chamber, and the accelerator chamber is The control room at least partially houses a charged particle beam generator, and the control room controls the neutron beam. The radiation treatment is controlled, and the electrical conduit is located in the radiation room, accelerator room, or control room. do.

[0076] Preferably, the support device includes a support frame, the support frame supporting the pipe. The device is used to place and guide components or cables.

[0077] Furthermore, the support frame has a support surface for supporting the tubular member or cable, The support frame is configured such that the placement surface is parallel to the ground or perpendicular to the ground. Furthermore, the support frame is fixed in a manner such that there is a predetermined gap between the side plates. and a plurality of horizontal plates connected at intervals, the horizontal plates forming the placing surface.

[0078] The neutron capture therapy system further includes an accelerator room and a beam transfer room, a chamber at least partially accommodating the charged particle beam generating unit, and the beam transfer chamber the beam transfer section is at least partially housed in the accelerator chamber or It is installed inside the beam transfer chamber.

[0079] Preferably, the charged particle beam generating unit includes an accelerator, and the neutron beam generating unit The section includes a target, a beam shaper, and a collimator, and the target A charged particle beam generated by the accelerator is provided between the transfer unit and the beam shaper. The beam is irradiated onto the target by the beam transfer unit and interacts with the target to form a central beam. The generated neutrons pass through the beam shaper and collimator in order. to form a therapeutic neutron beam.

[0080] Furthermore, the beam shaper may include a reflector, a moderator, a thermal neutron absorber, a radiation shield, and a beam a beam outlet, the moderator converting neutrons generated in the target into epithermal neutron energy The reflector surrounds the moderator and directs the escaping neutrons away from the moderator. The thermal neutron absorber absorbs the thermal neutrons and returns them to the original state to improve the intensity of the epithermal neutron beam. This prevents excessive doses from being given to superficial normal tissue during treatment, and A body is placed behind the reflector surrounding the beam exit to block escaped neutrons and photons. The collimator shields the beam to reduce the dose to normal tissue in the non-irradiated area. It is installed at the rear of the exit and focuses the neutron beam.

[0081] A neutron capture therapy system according to an eighth aspect of the present invention includes a charged particle beam generator and a beam a transfer unit and a neutron beam generating unit, the charged particle beam generating unit generating a charged particle beam and the beam transfer unit transfers the charged particle beam to the neutron beam generation unit. The neutron beam generating unit generates a therapeutic neutron beam and controls the neutron capture therapy system. The system further includes a cooling device, and the cooling medium of the cooling device has a hardness of more than 60 mg / L. The cooling device is used to cool the assemblies to be cooled in the neutron capture therapy system. This extends the service life of the equipment, and by using soft water as the cooling medium for the cooling equipment, During the cooling process, scale formation on the water pipes is unlikely to affect heat exchange efficiency.

[0082] Preferably, the charged particle beam generating unit includes an ion source for generating charged particles, and Charged particles generated by the ion source are accelerated to generate a charged particle beam with a desired energy. and an accelerator capable of generating a ion source, wherein the cooling device cools the ion source or the accelerator.

[0083] Preferably, the neutron beam generating unit includes a target, and the charged particle beam interacts with the target to generate the neutron beam, and the cooling device Cooling the target extends its useful life.

[0084] Furthermore, the cooling medium of the cooling device has a hardness of less than 17 mg / L, especially in the heat exchange part. However, when copper pipes are used, scale forms on the water pipes during the cooling process, which affects the heat exchange efficiency. or the cooling medium of the cooling device has a conductivity of less than 10 μS / cm; Meets the requirements for use under high voltage conditions, and is resistant to leakage currents in high voltage environments and neutron beams. This can prevent interference with the generation of

[0085] Furthermore, the cooling device is configured such that the cooling medium is deionized water, and the conductivity of the deionized water is 0 0.5~1.5μS / cm.

[0086] Preferably, the cooling device includes an external circulation device, an internal circulation device, and a heat exchanger, An internal circulation device transports a cooling medium to an assembly to be cooled in the neutron capture therapy system. The cooling medium, which has been heated after absorbing heat, is transported to the heat exchanger, and the external circulation The cooling medium is cooled by heat exchange with the cold water transported from the cooling device to the heat exchanger. The external circulation device transports the cold water to the assembly to be cooled to absorb heat, and the external circulation device transports the cold water to the heat exchanger. The cold water can be continuously supplied to the exchanger and recovered after absorbing heat and raising the temperature.

[0087] Furthermore, the external circulation device includes a cold heat source unit, a first pump, and a and a first control device that controls the first pump, and the external circulation device includes the heat exchanger The cold water from the container, which has been heated after absorbing heat, is transported to the cold heat source unit and cooled. The cold water is pumped to the heat exchanger by the first pump, and the first control device Control the transport of

[0088] Further, the internal circulation device includes a filter, a second pump, and a pump for circulating the filter and the second pump. a second control device for controlling the pump, one end of which is connected to the assembly to be cooled; The other end is connected to the heat exchanger, and the cooling medium absorbs heat from the assembly to be cooled. After collecting the cooled water, the cooled water is pumped by the second pump to the heat exchanger to exchange heat with the cooled water, After being cooled and cooled, the cooling medium is filtered by the filter and then passed through the filter. The cooling medium is transported into the assembly and heat exchange is performed, and the second control device controls the transport of the cooling medium. Control.

[0089] Furthermore, the internal circulation device includes a pressure stabilization circuit or a cooling medium replenishment circuit, and the pressure The stabilization circuit and the cooling medium replenishment circuit are controlled by the second control device, and the external circulation The circulation device includes a chilled water replenishment circuit controlled by the first control device.

[0090] A neutron capture therapy system according to a ninth aspect of the present invention includes a charged particle beam generator and a beam a transfer unit and a neutron beam generating unit, the charged particle beam generating unit generating a charged particle beam and the beam transfer unit transfers the charged particle beam to the neutron beam generation unit. The neutron beam generating unit generates a therapeutic neutron beam, and the charged particle beam generating unit generates a The generating unit includes an ion source that generates charged particles, and a device that accelerates the charged particles generated by the ion source. and an accelerator for obtaining a charged particle beam having a desired energy, the accelerator comprising: The accelerator high voltage power supply provides acceleration energy, and an insulating gas is provided in the accelerator high voltage power supply. By providing insulating gas inside the accelerator high voltage power supply, the power To prevent child parts from being destroyed.

[0091] Preferably, the neutron capture therapy system includes an auxiliary device including an insulating gas filling and recovery device. the insulating gas filling and recovery device provides the insulating gas to the accelerator high voltage power supply. To provide or recover the insulating gas from the accelerator high voltage power supply, and to maintain and inspect related equipment. Since the insulating gas can be recovered when the insulating gas is used, the utilization rate of the insulating gas is improved.

[0092] Preferably, the insulating gas filling and recovering device includes a gas source, a gas source and a gas recovery device for the accelerator height. and a storage container connected to a piezoelectric power source, the gas source containing the insulating gas. This includes containers that have been

[0093] Furthermore, the insulating gas filling and recovering device further includes a vacuum pump, and before filling, Start the pump to evacuate the storage container, piping, parts, etc. of the insulating gas filling and recovery device. to vent the air inside the device.

[0094] Furthermore, the insulating gas filling and recovery device provides power for the filling and recovery (return) process. It further includes a compressor.

[0095] Furthermore, the insulating gas filling and recovery device is provided between the storage container and the accelerator high voltage power supply. Remove most of the water molecules in the installed and recovered insulating gas to keep the gas in a relatively dry state. The method further includes a drying device for maintaining the temperature.

[0096] Furthermore, the insulating gas filling and recovery device is provided between the storage container and the accelerator high voltage power supply. The purity of the insulating gas is improved by removing oil and coarse particle impurities from the installed and collected insulating gas. The filter further comprises a filter device for maintaining the

[0097] Furthermore, the insulating gas filling and recovery device is a device for connecting the gas source container and the accelerator high voltage power supply. The insulating gas is supplied to the accelerator high voltage power supply. When the insulating gas is returned from the gas source container to the refrigeration device, the insulating gas is converted into a liquid state. The compressor compresses the insulating gas in a gaseous or liquid state, thereby increasing the volume of the gas source. Inject into the vessel.

[0098] Preferably, the neutron beam generating unit includes a target, a beam shaper, and a collimator. the target is disposed between the beam transfer unit and the beam shaper; The charged particle beam generated by the accelerator is irradiated onto the target by the beam transfer unit. and interacts with the target to generate neutrons, and the generated neutrons are The neutrons pass through a beam shaper and collimator to form a therapeutic neutron beam.

[0099] Furthermore, the beam shaper may include a reflector, a moderator, a thermal neutron absorber, a radiation shield, and a beam a beam outlet, the moderator converting neutrons generated in the target into epithermal neutron energy The reflector surrounds the moderator and directs the escaping neutrons away from the moderator. The thermal neutron absorber absorbs the thermal neutrons and returns them to the original state to improve the intensity of the epithermal neutron beam. This prevents excessive doses from being given to superficial normal tissue during treatment, and A body is placed behind the reflector surrounding the beam exit to block escaped neutrons and photons. The collimator shields the beam to reduce the dose to normal tissue in the non-irradiated area. It is installed at the rear of the exit and focuses the neutron beam.

[0100] The neutron capture therapy system of the present invention is based on an accelerator, which makes its operation safer and more reliable; It also has a more compact structure and rational layout, making it suitable for use in hospitals and other treatment facilities. can be done. [Brief explanation of the drawings]

[0101] [Figure 1] 1 is a schematic configuration diagram of a neutron capture therapy system according to an embodiment of the present invention. [Figure 2] 1 is a block diagram of a cooling device of a neutron capture therapy system according to an embodiment of the present invention. [Figure 3] FIG. 3 is a block diagram of an external circulation device in FIG. 2. [Figure 4] FIG. 3 is a block diagram of the internal circulation device in FIG. 2. [Figure 5] 1 is a block diagram of an insulating gas filling and recovery device of a neutron capture therapy system according to an embodiment of the present invention. [Figure 6] 1 is a plan layout diagram of a neutron capture therapy system according to an embodiment of the present invention. [Figure 7] FIG. 7 is a schematic diagram of a partition wall between the control room and the irradiation room in FIG. 6. [Figure 8a] 8A and 8B are layout diagrams of neutron shielding plates and support assemblies installed on the side of the partition wall between the irradiation chamber and the beam transfer chamber of a neutron capture therapy system according to an embodiment of the present invention, where FIG. 8A is a layout diagram of the neutron shielding plates and FIG. 8B is a layout diagram of the support assemblies. [Figure 8b] 8A and 8B are layout diagrams of neutron shielding plates and support assemblies installed on the side of the partition wall between the irradiation chamber and the beam transfer chamber of a neutron capture therapy system according to an embodiment of the present invention, where FIG. 8A is a layout diagram of the neutron shielding plates and FIG. 8B is a layout diagram of the support assemblies. [Figure 9] 8a-8b are schematic diagrams of the fixing method of the neutron shield and the support assembly. [Figure 10] 1 is a schematic diagram of an auxiliary device housing chamber installed in a beam transfer chamber of a neutron capture therapy system according to an embodiment of the present invention. [Figure 11] 1 is a schematic diagram of a treatment couch positioning device of a neutron capture therapy system according to an embodiment of the present invention. [Figure 12] FIG. 12 is a schematic view of FIG. 11 as seen from another direction. [Figure 13] 1 is a block diagram of a treatment table positioning device and its control device of a neutron capture therapy system according to an embodiment of the present invention. [Figure 14] 12 is a schematic diagram of an embodiment of a slide rail cover member of the treatment table positioning device of FIG. 11. FIG. [Figure 15] 12 is a schematic view of another embodiment of the slide rail cover member of the treatment table positioning device of FIG. 11. FIG. [Figure 16] FIG. 12 is a schematic diagram of an embodiment of a robot arm protective cover of the treatment table positioning device of FIG. [Figure 17] 1 is a layout diagram of a conduit and support frame of a neutron capture therapy system according to an embodiment of the present invention. [Figure 18] 1 is a schematic diagram of an annular shielding device of a neutron capture therapy system according to an embodiment of the present invention. DETAILED DESCRIPTION OF THE INVENTION

[0102] The present invention will be described in more detail below with reference to the accompanying drawings, so that those skilled in the art can easily understand the present invention. If so, it can be implemented by reference to the text of the specification.

[0103] As shown in FIG. 1, the neutron capture therapy system in this embodiment preferably includes a boron The neutron capture therapy system 100 is a boron neutron capture therapy system. This is a device that uses neutron capture therapy to treat cancer. Boron neutron capture therapy is a (B-10) is injected into the irradiated subject 200, and the neutron beam N is irradiated to treat cancer. The subject 200 is then given a boron (B-10)-containing drug or injected with it. The boron-containing drug is selectively collected in tumor cells M, and then the boron (B-10)-containing drug is thermally activated. Taking advantage of its high neutron capture cross section, 10 B(n,α) 7 Li middle Due to neutron capture and fission reactions, 4 He and 7 It generates two types of heavy charged particles called Li The two types of charged particles have an average energy of about 2.33 MeV and a high linear energy Linear Energy Transfer (LET) and short range The linear energy and range of the alpha particles are 150 keV / μm and 8 μm, respectively. can be, 7 The linear energy deposition and range of Li heavy charged particles are 175 keV / μm and 5 μm. The total range of the two types of particles is equivalent to the size of one cell, so radiation damage to the living body is minimal. On the premise that the damage is limited to the cellular level and does not cause too much damage to normal tissue, tumor cells The purpose of localized killing can be achieved.

[0104] The boron neutron capture therapy system 100 includes a beam generator 10 and a treatment couch 20. The beam generator 10 includes a charged particle beam generator 11, a beam transport unit 12, and a (first) neutral The charged particle beam generator 11 generates a charged particle beam such as a proton beam. The beam transfer unit 12 transfers the charged particle beam P to the neutron beam generation unit 13. The neutron beam generator 13 generates a therapeutic neutron beam N and transfers it to the treatment table 2. The object 200 on the optical axis 10 is irradiated.

[0105] The charged particle beam generating unit 11 includes an ion source 111 and an accelerator 112. 1 is H - The accelerator 112 generates charged particles such as ions, protons, and deuterons. The charged particles generated by the electron beam P are accelerated to generate a charged particle beam P having a desired energy, for example, If you do, you get a proton beam.

[0106] The neutron beam generating unit 13 includes a target T, a beam shaper 131, and a collimator 132. The charged particle beam P generated by the accelerator 112 is turned on by the beam transfer unit 12. Irradiating the get T and interacting with the target T to generate neutrons, the generated neutrons are The neutrons pass through a beam shaper 131 and a collimator 132 in order to form a therapeutic neutron beam N. The target T is preferably a metal target. The required neutron yield and energy, the available energy and The appropriate nuclear reaction is selected depending on the magnitude of the current, the physical and chemical properties of the metal target, etc. The nuclear reactions that are generally considered are: 7 Li(p,n) 7 Be and 9 Be(p,n) 9 B, and these two types of reactions are both endothermic. The reaction has energy thresholds of 1.881 MeV and 2.055 MeV, respectively, and Since the ideal neutron source for neutron capture therapy is epithermal neutrons at the keV energy level, Theoretically, protons with energies slightly above the threshold are bombarded into a metallic lithium target. By doing so, it is possible to generate neutrons with relatively low energy, and there is no need for too much moderation. It can be used clinically without the need for treatment, but metallic lithium (Li) and metallic beryllium The cross section of interaction between the two types of targets of lithium (Be) and the threshold energy protons is not high, To generate a sufficient neutron flux, protons with relatively high energy are generally used. An ideal target would have a high neutron yield and the energy of the generated neutrons would be The energy distribution is close to the epithermal neutron energy region (described in detail below), and has strong penetrating properties. It does not emit much radiation, is safe, inexpensive, easy to operate, and has high temperature resistance. However, in practice it is impossible to find a nuclear reaction that satisfies all the requirements. As is known to those skilled in the art, the target T may be made of metal materials other than Li and Be. For example, it is made of Ta or W and alloys thereof. It may be a cyclotron, a synchrotron, or a synchrocyclotron.

[0107] The beam shaper 131 is a neutron beam shaper that is generated when the charged particle beam P interacts with the target T. The beam quality of the neutron beam N can be adjusted, and the collimator 132 focuses the neutron beam N. This allows the neutron beam N to have high targeting during the treatment process. 131 includes a reflector 1311, a moderator 1312, a thermal neutron absorber 1313, and a radiation shield 1 314 and a beam outlet 1315, through which the charged particle beam P interacts with the target T. The energy spectrum of the neutrons generated by this method is wide, so the amount of epithermal neutrons that can meet the therapeutic needs is In addition, the content of other types of neutrons and photons should be reduced as much as possible to prevent the operator or the irradiated body from being exposed to the radiation. Neutrons leaving the target T must be slowed down to avoid causing damage. The energy of fast neutrons (>40 keV) passes through the body 1312 and enters the epithermal neutron energy region. It is adjusted to the range (0.5 eV to 40 keV) and can absorb epithermal neutrons (<0.5 eV) as much as possible. The moderator 1312 has a large cross section for fast neutrons and is suitable for epithermal heating. The decelerator 1312 is made of a material with a small cross section that interacts with the electrons. In this embodiment, the decelerator 1312 is D2 O, AlF3, Fluental, CaF2, Li2CO3, MgF2 and Al2O3 The reflector 1311 is made of at least one of the above materials, and the reflector 1311 surrounds the decelerator 1312 and decelerates the decelerator. The neutrons that pass through the body 1312 and diffuse into the surrounding area are reflected back into the neutron beam N to improve the neutron utilization rate. In this embodiment, the reflector 1311 is made of a material with high neutron reflectivity. The decelerator 1312 is made of at least one of Pb and Ni, and the decelerator 1312 has a thermal neutral The neutron absorber 1313 is made of a material with a large cross section for interacting with thermal neutrons. The thermal neutron absorber 1313 is made of Li-6 and absorbs the thermal neutrons that have passed through the moderator 1312. It absorbs neutrons to reduce the thermal neutron content in the neutron beam N, and maintains normal tissue in the superficial layer during treatment. To avoid excessive doses to tissues, thermal neutron absorbers are , may be integral with the moderator, the material of the moderator containing Li-6, and the radiation shielding 131 4 shields neutrons and photons leaking from the portion other than the beam exit 1315, and provides radiation shielding. The material of the body 1314 includes at least one of a photon-shielding material and a neutron-shielding material. In an embodiment, the radiation shielding material 1314 is made of lead (Pb) for photon shielding and lead (Pb) for neutron shielding. As can be seen, the beam shaper 131 further comprises a shielding material, polyethylene (PE). The collimator 1 may have any other structure as long as it can obtain the epithermal neutron beam required for treatment. 32 is installed behind the beam exit 1315 and is used to collimate the epithermal neutron beam emitted from the collimator 132. The beam is irradiated to the irradiated body 200, passes through the superficial normal tissue, and then is slowed down to thermal neutrons, which are then injected into the tumor. As can be seen, the collimator 132 may be removed and other configurations may be used. The neutron beam may be emitted from the beam outlet 1315 directly onto the object 200. In this embodiment, a beam is inserted between the object to be irradiated 200 and the beam exit 1315. A radiation shielding element is provided to block radiation from the beam exit 1315 to normal tissue of the subject. The radiation shielding device 30 is installed, and as can be understood, the radiation shielding device 30 may not be installed. The target T is installed between the beam transfer section 12 and the beam shaper 131. The transfer section 12 has a transfer tube C for accelerating or transferring the charged particle beam P. In this embodiment, The transfer tube C extends into the beam shaping body 131 along the direction of the charged particle beam P, and The target T penetrates the reflector 1311 and the decelerator 1312. and located at the end of the transfer tube C to obtain a high quality neutron beam. The target may use other mounting methods, further facilitating target replacement. or an accelerator or beam shaper to make the charged particle beam act uniformly on the target. It may be movable relative to

[0108] The boron neutron capture therapy system 100 further includes an auxiliary device 14, which includes , before the operation of the charged particle beam generating unit 11, the beam transferring unit 12, and the neutron beam generating unit 13. In one embodiment, auxiliary device 14 includes: Cooling device 141, air compressor for providing compressed air, insulating gas filling and recovery device 142, The present invention does not specifically limit the scope of the present invention to the above.

[0109] The cooling device 141 is used to cool the charged particle beam generator 11, the target T, and other auxiliary devices 14. It is used to cool the assembly CP, which should be cooled, and can extend the service life of the equipment. The cooling medium of the cooling device 141 may be soft water, and the heat exchange part in particular uses copper pipes. In this case, scale formation on the water pipes during the cooling process is unlikely to affect the heat exchange efficiency. For example, the hardness is less than 60 mg / L, and the charged particle beam generating unit 11 and the target T are cooled. When using a capacitor, it must meet the requirements for use under high voltage conditions and must not cause leakage current in a high voltage environment. To prevent interference with the generation of the neutron beam, the cooling medium has a very low electrical conductivity. For example, the conductivity of the cooling medium must be less than 10 μS / cm. Two cooling devices are installed, one of which uses soft water with a hardness of less than 17 mg / L, The other is to use deionized water with a conductivity of 0.5 to 1.5 μS / cm, as can be seen. However, other types of cooling media may also be used.

[0110] As shown in FIG. 2, the cooling device 141 includes an external circulation device 1411, an internal circulation device 1412, and a and a heat exchanger 1413, and the internal circulation device 1412 is a cooling medium (e.g., soft water or desiccant). The ionized water is transported to the assembly CP to be cooled to absorb heat, and then the cooled medium is heated after absorbing heat. The body is transported to the heat exchanger 1413 and then transported from the external circulation device 1411 to the heat exchanger 1413. The cooled cooling medium is transported to the assembly CP to be cooled and absorbs heat. By repeating this process, the external circulation device 1411 continuously supplies cold water to the heat exchanger 1413. The external circulation device 1411 can provide the cold water and recover the cold water that has been heated after absorbing heat. The boron neutron capture therapy system 100 is installed outdoors, i.e., in a manner that allows the heat to be exhausted to the atmosphere. It is installed outside the building that contains it (described in more detail below), and in this example, The internal circulation device 1412 and the heat exchanger 1413 are installed on the roof of the building. In order to absorb the heat of the CP, the boron neutron capture therapy system 100 It is installed inside the building that houses the equipment, and as can be understood, it may be installed in other places, e.g. For example, the heat exchanger is placed outdoors.

[0111] As shown in FIG. 3, the external circulation device 1411 includes a cold heat source unit 1411a, a first pump 1411b, a first control device for controlling the cooling heat source unit 1411a and the first pump 1411b; The cooling device 1411c may include a cooling device 1411d, which cools the cold water from the heat exchanger 1413 whose temperature has increased after absorbing heat. The cooled water is transported to the heat source unit 1411a and cooled, and then pumped by the first pump 1411b. The cold water is pumped to the heat exchanger 1413, and the first control device 1411c controls the transport of the cold water. As shown, the internal circulation device 1412 includes a filter 1412a, a second pump 1412b, a filter 1412c, a filter 1412d, a filter 1412e, a filter 1412f ... The second control device 1412c controls the filter 1412a and the second pump 1412b. One end is connected to the assembly CP to be cooled and the other end is connected to the heat exchanger 1413. The cooling medium absorbs the heat of the assembly CP to be cooled at the end and then flows into the second pump. The water is pumped to the heat exchanger 1413 by the pump 1412b and exchanges heat with the cold water. After cooling and lowering the temperature, The cooling medium is filtered by the filter 1412a and then passed through the assembly CP to be cooled. The cooling medium is transported to the cooling section 1412c, where heat exchange occurs, and the second control device 1412c controls the transport of the cooling medium. When using deionized water as a cooling medium, the circulation process is affected by various factors. This allows the conductivity to be continuously improved, and the filter ensures that the conductivity of the cooling medium meets the requirements. To ensure that the temperature is maintained and meets requirements, a conductivity sensor (not shown) must be installed. The conductivity of the cooling medium at the outlet of the filter 1412a may be detected by the The heat exchanger 1413 is also controlled by the first controller 1411c, and as can be seen, The second controller 1412c may have a controller of the first type and may be controlled by the second controller 1412c.

[0112] The internal circulation device 1412 includes a pressure stabilization circuit 1412d and is connected to the second control device 141. 2c. In one embodiment, the pressure stabilization circuit 1412d may be controlled by a buffer. The nitrogen gas may be supplied by the pressure sensor. Detects the pressure inside the tank and releases nitrogen gas into the buffer tank if the pressure is lower than a specified value. Refill and increase pressure, ensuring positive pressure in the system and preventing air from entering the system. The external circulation device 1411 and the internal circulation device 1412 are respectively connected to the cold water replenishment circuit 141. 1d, and a cooling medium replenishment circuit 1412e, and respectively include a first control device 1411c, a second control device 1411d, and a cooling medium replenishment circuit 1412e. It may be controlled by the control device 1412c, and an alarm notification may be issued if there is insufficient cold water / cooling medium. The cooling medium is supplied by the cooling water supply circuit 1411d / cooling medium supply circuit 1412e. The external circulation device 1411 and the internal circulation device 1412 are equipped with a temperature sensor, a control valve, a pressure sensor, etc. and may be controlled by a first controller 1411c and a second controller 1412c. As can be readily appreciated, the cooling device 141 may have other configurations.

[0113] The accelerator 112 includes an accelerator high voltage power supply (ELV) 1121 that provides acceleration energy. In order to prevent the electronic components in the accelerator high voltage power supply 1121 from being damaged, Provide an insulating gas to the power supply 1121 (for example, provide an insulating gas in the case of the accelerator high voltage power supply 1121). The insulating gas may be SF6, and as can be seen, other insulating gases may be used. The insulating gas filling and recovery device 142 supplies the insulating gas to the accelerator high voltage power supply 1121. Provide insulating gas or recover insulating gas from the accelerator high voltage power supply 1121 and related equipment. The insulating gas can be recovered during maintenance and inspection, improving the utilization rate of the insulating gas. do.

[0114] As shown in FIG. 5, the insulating gas filling and recovery device 142 includes a gas source 1421 (e.g., SF 6) and connected to the gas source 1421 and the accelerator high voltage power supply 1121, respectively. In the initial state, the insulating gas is stored in the gas source 1421. First, insulating gas is filled into the storage container 1422 from the container of the gas source 1421, and then When insulating gas is filled into the ELV from the storage container 1422, the ELV begins to operate normally. If the ELV needs to be opened for maintenance or inspection, the insulating gas must be removed from the ELV to the reservoir 142. 2, and when maintenance and inspection are completed, the insulating gas is pumped from the storage container 1422 into the ELV. The storage container 1422, pipelines, and parts of the insulating gas filling and recovery device 142 require maintenance. When an inspection is required or when a malfunction occurs, the insulating gas is supplied from the storage container 1422 to the gas supply. Return it to the original state in the container of the source 1421, and when the maintenance and inspection are completed, refill it. Do it again.

[0115] The insulating gas filling and recovery device 142 is a filter installed between the storage container 1422 and the ELV. The insulating gas may be transferred from the ELV to the storage vessel 1423 and the drying device 1424. When collecting the insulating gas in the gas separator 22, the filter 1423 is used to filter out oil and coarse particles in the collected insulating gas. The purity of the insulating gas is maintained by removing impurities, and the drying device 1424 dries the recovered insulating gas. This removes most of the water molecules in the gas, keeping it relatively dry. A strainer may be used, and the drying device 1424 may be electrically heated. Alternatively, drying or filtering may be performed by other methods. In this embodiment, the insulating gas is First, it passes through a filtration device 1423, then through a drying device 1424, and as can be seen, first The filtration device 1423 and the drying device 1424 may be integrated. The sensor may include a moisture detection component, an oil detection component, or an impurity detection component.

[0116] The insulating gas filling and recovery device 142 is provided between the container of the gas source 1421 and the storage container 1422. The insulating gas may be stored in a storage tank that may include a refrigeration unit 1425 and a compression unit 1426. When returning the insulating gas from 1422 to the container of the gas source 1421, the refrigeration device 1425 The compressor 1426 compresses the insulating gas in the gas or liquid state to 1421, and as can be seen, the refrigeration system 1425 and the compression system 14 26 may be integrated without any restriction on the order of precedence.

[0117] The insulating gas filling and recovery device 142 may include a vacuum pump. The insulating gas is supplied to the storage container 1422, the pipeline, the components, etc. of the insulating gas filling and recovery device 142. The accelerator high voltage power supply 1121 is equipped with a vacuum pump 14. 3 may be installed to evacuate the ELV before filling and operating the ELV. The insulating gas filling and recovery device 142 is a device for filling and recovering (returning) the insulating gas. The insulating gas filling and recovery device 142 may include a compressor that provides power to the insulating gas. It may also include a valve for controlling the recovery (return) process, a vacuum detection component, a pressure detection component, etc. As can be appreciated, the insulating gas filling and recovery device 142 may have other configurations.

[0118] As shown in FIG. 6, the boron neutron capture therapy system 100 is installed in a concrete structure building. Specifically, the first irradiation chamber 101, the accelerator chamber 102, and the beam The object to be irradiated 200 on the treatment table 20 is irradiated with neutrons in the irradiation chamber 101. The accelerator room 102 receives treatment by irradiation of the beam N, and the accelerator room 102 includes a charged particle beam generator 11 (e.g., For example, the beam transfer chamber 103 at least partially houses the ion source 111 and the accelerator 112. The beam transfer section 12 is at least partially accommodated in the irradiation chamber. The auxiliary equipment is at least partially housed within a partition wall W1 between the beam transfer chamber 101 and the beam transfer chamber 103. The device 14 is at least partially located within the accelerator chamber 102 or the beam transfer chamber 103 .

[0119] The boron neutron capture therapy system 100 may include a second irradiation chamber 101′, The generator 10 further includes a second neutron beam generating section 13' corresponding to the second irradiation chamber 101'. The beam transfer unit 12 includes a beam direction switching assembly 121. The beam transfer unit 12 is connected to the assembly 121, and the charged particle beam generated by the charged particle beam generation unit 11 is transferred to the beam transfer unit 12. The charged particle beam P is selected for the first neutron beam generating unit 13 or the second neutron beam generating unit 13'. By selectively transferring the beam to the first irradiation chamber 101 or the second irradiation chamber 101', The neutron beam N irradiating the inside of the second irradiation chamber 101' is It may also be used for treatment by irradiating another subject on the treatment table 20' with the neutron beam N. , sample detection, etc., and the present invention is not limited thereto.

[0120] The beam generating device 10 may have another structure. For example, when there is a third irradiation chamber, In this case, a third neutron beam generating unit corresponding to the third irradiation chamber may be added, and the neutron beam generating The number of units corresponds to the number of irradiation chambers, and the embodiment of the present invention specifies the number of neutron beam generating units as follows: Without limitation, one charged particle beam generator is installed to generate charged particle beams and neutron beams. By transferring the data to the department, the cost of the system can be effectively reduced. As described above, the beam generating device may include a plurality of charged particle beam generating units, thereby Charged particle beams are transferred to each neutron beam generator, and multiple neutrons are simultaneously generated in multiple irradiation chambers. It is possible to generate and irradiate a beam.

[0121] In one embodiment of the present invention, the beam direction switching assembly 121 The first irradiation chamber 101 includes a deflection magnet (not shown) for deflecting the direction of the beam. When turned on, the beam is introduced into the first irradiation chamber 101, and the present invention is not specifically limited thereto. The boron neutron capture therapy system 100 collects the beam when it is not needed. or a beam collector 40 for verifying the power of the charged particle beam P before treatment. The beam direction switching assembly 121 redirects the charged particle beam P from its normal trajectory. It can be directed to a collector.

[0122] The boron neutron capture therapy system 100 includes a preparation room (not shown), a control room 104, and a treatment room. The irradiation chamber may include other spaces (not shown) to assist in the preparation of the irradiation. Before irradiation treatment, the patient is fixed to the treatment table and the patient's position is simulated. The control room 104 controls the accelerator, It controls the beam transfer unit, treatment table, etc., and manages the entire irradiation process. It is possible to simultaneously monitor multiple irradiation rooms within the same room, and the drawings only show one type of control room layout. As shown and understood, the control room may have other configurations.

[0123] During the boron neutron capture therapy process, boron neutrons must be administered continuously. The capture therapy system 100 delivers a boron (B-10)-containing drug to the subject 200 during radiation treatment. The drug injection device 50 is located in the drug control room (in this embodiment) The control room 104 and the irradiation room 101 are connected to each other via a drug passage assembly 51. The drug passage assembly 51 includes a drug passage member 5 for injecting a drug containing boron (B-10). 11 and a containing member 512 that at least partially contains the drug passage member 511, The firing chamber 101 has a partition wall W2 separating it from the drug control chamber, and the storage member 512 is The drug passage member 511 is installed in the wall W2, and forms a passage that passes through the partition wall W2; Furthermore, it can support the medicine passing member 511. In this embodiment, the containing member 51 2 is fixedly mounted within the partition wall W2, for example, by means of an interference fit, and as can be seen The containing member 512 may be installed in other ways, such as On the other hand, the concrete wall prevents the contamination of the drug passage member 511 by dust or the like. In the drawing, a boron-containing agent is injected into the subject 200 in the first irradiation chamber 101. Only the device is shown, and as can be seen, the boron-containing agent for the subject in the other irradiation chamber. The injection may be performed using a similar drug injection device 50.

[0124] The drug injection device 50 may include a drug containing mechanism 52 and a drug control mechanism 53. The container mechanism 52 and the drug control mechanism 53 are installed in a drug control room and are illuminated in the drug control room. The injection of a boron (B-10) containing agent into the projectile 200 may be controlled, and the irradiation chamber 101 Neutron radiation in the drug containing mechanism 52 and the drug control mechanism 53 is transferred to the electric field in the drug control mechanism 53. If the auxiliary components do not function properly or react with the boron-containing drug contained within drug containment mechanism 52, The medicine passing member 511 can prevent the medicine containing device from being affected by the medicine passing member 511. The device 52 is connected to the device 52, and the drug control device 53 controls the drug containing boron (B-10) to be injected into the irradiated body. The medicine containing mechanism 52 may be an infusion bag or an infusion bottle. The drug control mechanism 53 is connected to the drug passage member 511 and The flow of the boron (B-10)-containing agent is controlled by, for example, using a pump to pump the liquid (boron (B -10) The contained drug) may provide a force to flow, control the flow rate, and detect and alarm. The drug passage member 511 may have the following functions: For example, a venous needle, a protector, a tube, and The medicine passage member 511 includes a bottle needle connected to the medicine containing mechanism 52. The parts, for example, the intravenous needle and the tube part installed in the irradiation chamber 101 are made of neutron shielding material. The neutron radiation in the irradiation chamber may affect the boron-containing drug in the drug passage member 511. The impact of this can be reduced.

[0125] As shown in FIG. 7, in this embodiment, the accommodating member 512 has a thickness in the thickness direction of the partition wall W2. The central axis X of the through hole 513 is aligned with the ground and the partition wall. The through-hole 513 intersects with a plane perpendicular to the ground along the thickness direction of W2. The radiation leakage is reduced by penetrating the partition wall W2 in a manner that is inclined both in the vertical and horizontal directions. , the central axis X of the through hole 513 is a straight line, and as can be understood, the through hole 513 is For example, the central axis X of the through hole 513 may be a broken line or a curved line. The cross section of the through-hole 513 may be circular, square, etc. From the center of the through hole 513 in the first side wall S1 of the wall W2 facing the control room 104 to the ground The distance D1 is the distance between the through-hole 513 in the second side wall S2 of the partition wall W2 facing the irradiation chamber 101. The distance D2 from the center to the ground is greater than the distance D2, for example, the distance D2 is greater than the distance D2 from the control room 104 of the partition wall W2. The distance from the center of the through-hole 513 to the ground gradually decreases along the direction to the chamber 101. In this embodiment, the receiving member 512 is a tubular member installed in the through-hole 513, The outer wall of the tubular member is fitted to the inner wall of the through-hole, and the shape of the inner wall of the tubular member is not limited. In order to allow the medicine passing member 511 to pass through, the containing member 512 is a box-shaped body having a hole formed therein. There may be one or more buckles, etc.

[0126] The container 512 is made of PVC, and the product after irradiation with neutrons is radioactive. No or very low radioactivity, reducing the secondary radiation generated and, as can be seen, The product after irradiation by neutrons is not radioactive, or the product after irradiation by neutrons is not radioactive. The half-life of a radioisotope that has very low radioactivity or is produced after irradiation by neutrons Other materials with short lengths may be used. The receiving member 512 and the through-hole 513 are formed in each partition wall at least At least two may be installed, and if one of them becomes blocked or other problems occur, In that case, there is a spare one.

[0127] Regarding the process of injecting boron (B-10)-containing drugs during radiation therapy, Before the injection, a suitable medicine passage member 511 is selected, and the medicine passage member 511 and the medicine containing mechanism 5 2 and the drug control mechanism 53, and the drug passing member 511 passes through the containing member 512 and is illuminated. The irradiation chamber 101 is placed at an appropriate position, and the irradiation chamber 101 is positioned relative to the object to be irradiated 200. After completing the above and deciding on a treatment plan, the operator in the drug control room opens the drug control mechanism 53. Then, the doctor in the irradiation room 101 removes the protector and inserts the intravenous needle into the subject 200. or inserted into the irradiation subject 200 before positioning the irradiation subject 200, and the doctor After leaving the control room 104, the operator directs the neutron beam to irradiate the target object. Controlled injection of boron (B-10) containing drugs. A similar drug injection device 50 may be used to inject a drug containing boron (B-10) before treatment. The drug passage member 511 is blocked before entering the irradiation chamber 101, for example, by blocking the drug passage member 511. After the patient enters the irradiation chamber 101, the intravenous needle is removed or an indwelling needle is used, and the drug passage member 511 is inserted. The drug passage member 511 is reconnected or replaced, and boron (B- 10) Injection of boron (B-10)-containing drugs or injection of boron (B-10)-containing drugs during radiation therapy In this case, the preparation room becomes a drug control room. The drug injection device 50 may be applied to other types of neutron capture therapy systems, such as boron ( B-10) The contained drug may be replaced with another drug.

[0128] In the neutron capture therapy process, a large amount of neutrons is generated near the target T. In order to generate neutrons, it is necessary to prevent neutron leakage as much as possible. At least a part of the space (for example, the beam transfer chamber 103, the irradiation chambers 101, 101') is The concrete to be formed is concrete to which neutron shielding materials have been added, for example, It is a concrete containing uran and barite, which forms a neutron shielding space. In another embodiment, the ceiling of the chamber (e.g., the beam transfer chamber 103, the irradiation chamber 101, 101′) A neutron shielding plate 60 is installed on the surface of the concrete of the well plate, floor plate, wall, etc., and The PE plate containing the neutron shielding space is installed to form a neutron shielding space. The concrete surface may be in close contact with the concrete surface or may be spaced a predetermined distance apart. It may be installed on the entire surface of the wall, or only in a partial area, for example, in the irradiation chamber. A neutron shielding plate is installed on the surface of the floor plate in the central area of ​​the irradiation chamber, and a neutron shielding plate is installed on the surface of the floor plate in the entrance area of ​​the irradiation chamber. No neutron shielding panels are installed, and the two areas are connected by a slope, creating a difference in altitude. The neutron shield 60 is mounted on the concrete surface by a support assembly 61, e.g. 8a and 8b show the beam transfer chamber 103 and the beam transfer chamber 103 at the partition wall W1. 03 and the layout of the neutron shielding plate 60 and the support assembly 61. 9 shows a fixing method of the neutron shielding plate 60 and the support assembly 61. 60 is formed by combining multiple plates and is anchored to the concrete of the partition wall W1. A long support assembly 61 is installed at a predetermined distance by bolts, and the neutron shielding plate Each plate of 60 is fixed in its corresponding position on the support assembly 61 by a screw, i.e., The support assembly 61 is connected to the concrete on one side and to the neutron shielding plate 60 on the other side. In this embodiment, the support assembly 61 is made up of two L-shaped brackets connected by bolts. As can be appreciated, the support assembly 61 and the fixing method may be different from other installation methods. For example, the support assembly 61 may be constructed at least in part from a molded material. The neutron shielding plate 60 may be fixed directly to the surface of the concrete, and the partition wall W1 The side wall of the accommodation groove that accommodates the neutron beam generating unit 13 is provided with a neutron shielding plate 60. This may be done.

[0129] Other devices in the room, such as auxiliary devices 14, for neutron capture therapy. A neutron shield 60 is provided around the auxiliary equipment 14 to reduce radiation damage and contamination. As shown in FIG. 10, in one embodiment, The room transfer chamber 103 includes an auxiliary device storage chamber 105 for storing or enclosing the auxiliary device 14 and the like. The auxiliary equipment housing 105 is at least partially enclosed by the support assembly 61 and the support The neutron shielding plate 60 is fixed to the assembly 61 (the drawing shows only a part of the neutron shielding plate 60). In this embodiment, the auxiliary equipment housing chamber 105 is located in the beam transfer chamber 103. It is installed at a corner and shares part of the wall and floor of the beam transfer chamber 103. The bridge 61 and the neutron shielding plate 60 fixed to the support assembly 61 are connected to the beam transfer chamber 103. together with some of the walls and floorboards, form a space that houses and surrounds the auxiliary equipment 14, i.e., the support assembly The neutron shielding plates 60 fixed to the assembly 61 form three sides of the cubic storage space, and Some walls and floor plates of the room transfer chamber 103 form the other three sides of the cubic storage space. The auxiliary device housing chamber 105 includes a door 1051 and its movement mechanism 1052. 52 is a door 1051 through which an operator can enter the auxiliary device housing chamber 105 when inspecting the device. The door 1051 includes a guide rail 1052a and a slide rod 1052b. The slide rod 1052b slides horizontally along the guide rail 1052a. In this embodiment, the door 1051 is supported by a door support assembly 1051a. and a neutron shielding plate 60 fixed to the door support assembly 1051a, The rod 1052b is fixedly connected to the door support assembly 1051a, e.g., the door 10 51, and the guide rail 1052a is connected to the support assembly of the auxiliary equipment housing 105. 10. As can be appreciated, the moving mechanism 1052 may be of other construction. For example, the door may be rotatable. 1052c and pulley 1052d, and the lifting assembly 1052c lifts the door 1051. By lifting the pulley 1052d vertically, the pulley 1052d is placed at the bottom of the door 1051. Therefore, the door 1051 can slide horizontally by the pulley 1052d. In this embodiment, the lifting assembly 1052c includes a jack 1052e and The door support assembly 1051a is connected to a connecting plate 1052f. 52e acts on the connecting plate 1052f, and the door 1051 moves in the direction of the slide rod 10 52b, the vertical direction along the guide rail 1052a, As can be seen, the lifting assembly 1052c is lifted in a vertical direction. The auxiliary device housing chamber 105 may have a structure as follows: 1053, which is a fixing member that integrally connects the door 1051 and the auxiliary device housing chamber 105. In this embodiment, the fixing member 1053 is L The two side plates of the L-shaped plate are respectively connected to the door support assembly 1051 a and is fixed to the support assembly 61 or the neutron shielding plate 60 of the auxiliary equipment housing chamber 105. The auxiliary device housing chamber 105 may have an opening 1054 through which a pipe, a cable, etc. may pass. In an embodiment, openings 1054 are located adjacent corners in walls and floorboards. The support assembly 61 of the auxiliary equipment housing 105 and the door support assembly 1051a are As can be seen, the auxiliary equipment chamber 105 is made up of other structures. Alternatively, the auxiliary device housing may be provided in another space.

[0130] The neutron shielding plate 60 is a boron-containing PE plate, and the support assembly 61, the door support assembly assembly 1051a, guide rail 1052a, slide rod 1052b, and fixing member The material of 1053 is an aluminum alloy, and as can be seen, the material of the neutron shielding plate 60 The material may be other neutron shielding materials, and different thicknesses may be used at different locations as needed. The surface may have other decorations or grooves for attaching other parts. The aluminum alloy has a certain strength, and the product after being irradiated by neutrons is radioactive. It has no radioactivity, or the radioactivity of the product after irradiation with neutrons is very low, or it is neutral. Other materials in which the radioisotopes produced after irradiation by neutrons have short half-lives, e.g., carbon Fiber composites or glass fiber composites may be substituted.

[0131] As shown in FIGS. 11 to 13, a treatment table positioning device 70A is provided in the irradiation rooms 101 and 101′. and a shielding device 70B of the treatment table positioning device may be installed, and the treatment table positioning device 70 A includes a linear axis 71a and a robot arm 72a, and the robot arm 72a is 71a and the treatment table 20, and supports and positions the treatment table 20, and The treatment table 20 and the robot arm 72a are connected to the linear axis 71a. In this embodiment, the linear axis 71a is aligned with the ceiling of the irradiation chamber. The entire robot arm 72a is attached to the floor of the irradiation chamber and extends toward the floor. Alternatively, the linear axis 71a may be attached to other surfaces, such as a wall or floorboard. The linear axis 71a is connected to a slide rail 711a fixed to the ceiling board and a robot arm 7 2a, and the support base 712a is connected to the slide rail 711. The linear axis 71a slides along the ceiling. It is fixed directly to the plate, and does not require a separate linear axis fixing mechanism, such as a steel structure gantry, Reduced steel usage in the firing chamber, and secondary radiation generated by neutron activation of the locking mechanism The robot arm 72a is connected to the support table 712a and the treatment table 20. The robot arm is a multi-axis robot arm having a plurality of arm portions 721a (721a').

[0132] The support base 712a is connected to the robot arm 72a and slides along the slide rail 711a. The neutron shielding plate 60 installed on the ceiling or other fixed surface reserves the sliding space in advance. This will result in exposure of the slide rail and radiation leakage. The device 70B includes a slide rail cover member 71b. b moves together with the support base 712a and always covers the exposed part of the slide rail 711a. The shielding device 70B includes at least one arm portion 721a of the robot arm 72a. The robot arm protection cover 72b further includes a robot arm protection cover 72b that covers the robot arm protection cover 72b. The material of the protective cover 72b is at least partially a neutron shielding material, and the arm portion and the Metallic components and electronic devices installed in the arm mechanism were irradiated with neutrons and then damaged. It is possible to prevent the material from being damaged or broken, for example, by using a boron-containing glass fiber composite material. As can be appreciated, other shielding materials may also be used.

[0133] The treatment table positioning device 70A may include a drive mechanism 73a, and Alternatively, the treatment table control device 70C may be installed in the control room 104. 0C is connected to the drive mechanism 73a and controls the drive mechanism 73a to operate the linear axis 7 and controls the movement of the linear axis 71a and the robot arm 72a. The position information may be fed back to the treatment table control device 70C, and the driving mechanism 73a , linear axis 71a or robot arm 72a, for example, support base 712a or at least one The arm portion 721a may be provided with the stator 721b.

[0134] The treatment table positioning device 70A includes a sensor 741a, a sensor control assembly 742a, and a head It may also include a collision prevention protection mechanism 74a including a human-machine interface 743a. , the sensor 741a is installed in the robot arm protective cover 72b, and as can be seen, It may be installed between the robot arm protective cover 72b and the robot arm 72a. Will the edge of the robot arm 72a or the robot arm protective cover 72b come into contact with other objects? Or, when another object reaches a predetermined range of the sensor 741a, the sensor 741a is triggered. The signal transmitted by the sensor 741a is transmitted to the sensor control assembly 742a. and displayed on the human machine interface 743a, and the sensor control assembly The assembly 742a transfers the received signal to the treatment table control device 70C and performs corresponding control. For example, the treatment table control device 70C controls the drive mechanism 73a to move the linear axis 71a and the robot. 72a, i.e., the treatment table 20 is stopped from being driven to move. As can be seen, the sensor control assembly may determine the corresponding The operator may control the robot based on the display of the human-machine interface. The driving mechanism may be manually controlled to stop the driving, and the treatment table may be controlled to stop the movement. Instead of the collision, other safety maneuvers may be performed, for example, a pre-crash reversal. Sensor 741a is a mechanical sensor, photoelectric sensor, radar sensor, ultrasonic sensor, laser rangefinder etc., or may be installed at other positions.

[0135] The linear shaft 71a and its drive mechanism 73a are illuminated by a fixed or supporting member (not shown). The support and fixing members may be attached to a fixed surface of the chamber 101, 101'. For example, the slide rail 711a may be made of aluminum material. The drive mechanism 73a of the support base 712a and the linear shaft 71a is fixed to the support member. The slide rail cover member 71b is fixed to or supported by the ceiling board by the support base 712a. The neutron shielding plate 60 is installed between the fixed surface of the linear shaft 71a. As shown, in one embodiment, the slide rail cover members 71b are all connected in sequence. A first portion including a flat plate supported by the support member 713b of the slide rail cover member The first portion 711b and the second portion 712b are supporting portions. One end of the support base 712a adjacent to the support base 712a along the sliding direction A of the support base 712a is a connecting plate 7111b, 121b is fixedly connected to the support base 712a, and the other end is fixedly connected to the support member 713b. As can be seen, the fastening method can be screw connection, adhesive connection, etc. The plates of the second part 711b and the second part 712b are connected in a slidable manner (see FIG. 14). 14) or pivotally connected (first part 711b shown on the left) or pivotally connected (second part 711b shown on the right 12b), as can be understood, there may be other connection methods between the plates, and the drawings show Only different connection methods are shown, and the first part 711b and the second part 712b may be the same as those shown if necessary. The support member 713b may be connected to the linear shaft 71a by the same or different connection method. It may be connected to and fixed to a fixed member or support member of the drive mechanism 73a, or may be directly fixed to a fixed surface. The support member 713b may be made of aluminum alloy and may be fixed to the slide rail. The material of the cover member 71b includes boron-containing PE or other neutron shielding material, and The shielding plate 60 covers the support member 713b and, together with the slide rail cover member 71b, The linear shaft 71a, the drive mechanism 73a of the linear shaft 71a and its mounting portion (support base 712a) The neutron shielding plate 60 is covered with aluminum (except for the portion that penetrates the plate). The alloy has a certain strength, and the product after being irradiated with neutrons is not radioactive; or the radioactivity of the product after irradiation with neutrons is very low, or The radioisotopes produced after the radioactive material is extracted may be replaced by other materials with short half-lives, and support The member 713b may be made of a neutron shielding material, in which case the neutron shielding plate 60 may be Instead of covering the support member 713b, it may be fitted to the support member 713b. The shielding plate 60, the support member 713b and the slide rail cover member 71b are all connected to the linear shaft 71. a, the drive mechanism 73a of the linear axis 71a and its mounting portion (neutron shielding of the support base 712a) The support base 712a covers the slide rail 711a (except for the portion that penetrates the plate 60). During the process of moving along the slide rail cover member 71b, the first portion 711b and The expansion and contraction of the first and second portions 712a and 712b reduces the leakage of neutrons during the entire movement process. .

[0136] As shown in FIG. 16, in this embodiment, a robot arm protection device that encases the arm portion 721a The cover 72b is integrally and fixedly connected to the arm portion 721a and the arm portion 721a. The drive mechanism 73a (for example, a motor, a circuit board, etc.) or the control mechanism (for example, a sensor control A first case 721b enclosing the control assembly 742a (or a component of the treatment table control device 70C) The first case 721b and the second case 722b are made of the following materials: A boron-containing glass fiber composite material, which has a certain strength and The product after irradiation with neutrons is not radioactive or has very low radioactivity, and the secondary The boron absorbs neutrons and prevents radiation from being generated. Metal components and electronic devices in the drive mechanism or control mechanism are irradiated with neutrons and then fail. As can be seen, the first case and the second case can be prevented from being damaged. The material of the second case may be other neutron shielding material with a certain strength.

[0137] In this embodiment, the robot arm protection cover 72b' that encases the arm portion 721a' is The first case 721b and the second case 722b are fixedly connected together. The third case 723b and the fourth case 724b encase the second case 721b and the second case 722b. Furthermore, the sensor 741a is located between the first case 721b and the third case 723b and between the second case 721b and the third case 723b. The sensor 741a is installed between the case 722b and the fourth case 724b. The first case 721b and the second case 722b are arranged around the arm portion 721a. A receiving cavity 725b is provided to receive the sensor 741a. The housing cavity 725b is provided between the first case 721b and the third case 723b. and between the second case 722b and the fourth case 724b by interference fit. Specifically, the gap between the first case 721b and the third case 723b and the gap between the second case 722b and the fourth case 723b. A gap 726b in which the sensor 741a is attached is provided between the case 724b and the case 724b. The power supply and communication cables of the sensor 741a pass through the gap 726b and are connected to the sensor control assembly. The sensors in the third case 723b and the fourth case 724b may be connected to the bridge 742a. A through hole at a position corresponding to 741a through which the power supply for the sensor 741a, a communication cable, etc. pass 727b (not shown) may also be installed. As can be appreciated, the sensor 741a may be installed in addition to other In this embodiment, the sensor 741a is a pressure sensor. The pressure received by the third case 723b and the fourth case 724b is converted into a pressure signal, and the sensor control assembly 742a and transmits the numerical value to the human machine interface 743a. If the pressure signal received by the sensor 741a exceeds a predetermined value, a predetermined pressure signals exceeding the threshold are preferentially forwarded to the sensor control assembly 742a and A warning is displayed on the machine interface 743a, for example, by lighting or sound. The sensor control assembly 742a transmits the signal to the couch control device 70C, which controls the linear axis 71 a and the robot arm 72a to stop the movement, and the operator manually operates the linear axis 7 The movement of the robot arm 1a and the robot arm 72a may be stopped.

[0138] The third case 723b and the fourth case 724b are made of a glass fiber resin composite material. , has a certain intensity, and the product after irradiation with neutrons is not radioactive or It has very low radiation, prevents secondary radiation from occurring, and has a certain intensity, as can be seen. and the product after irradiation with neutrons is not radioactive or The radioactivity of the product is very low or the radioisotopes produced after irradiation with neutrons Other materials with short half-lives may be used. The material of the robot may be replaced with a boron-containing glass fiber composite, i.e., The outermost case of the arm protection cover 72b is made of a material that can absorb neutrons. Metallic components and electronic equipment in the drive mechanism or control mechanism installed in the facility are irradiated by neutrons. The materials of the first and second cases are The case of the sensor 741a is made of aluminum alloy, and is not made of conventional steel. It produces long-lived radioisotopes, such as cobalt-60, after being irradiated by neutrons. As can be seen, aluminum alloys have a certain and the product after irradiation with neutrons is not radioactive or is irradiated by neutrons. The radioactivity of the product after irradiation by neutrons is very low, or The radioisotopes may be replaced by other materials with shorter half-lives. The sensor 741a is located between the first case 721b and the third case 723b and / or the second case. It may be installed between the base 722b and the fourth case 724b.

[0139] Between the first case 721b and the second case 722b and between the third case 723b and the fourth case The fixed connection between the connector 724b and the connector 724b may be by screw connection, welding, etc., and the connecting member is It is an aluminum alloy that has a certain strength and is activated by neutrons. The half-life of the radioactive isotopes produced by the process is short, and aluminum alloys have a certain strength. And the product after irradiation with neutrons is not radioactive or is irradiated with neutrons. The radioactivity of the resulting product is very low, or the radioisotope produced after irradiation with neutrons is Other materials with short isotopic half-lives may be substituted.

[0140] In this embodiment, the third case 723b, the fourth case 724b and the sensor 741a are It is installed on arm section 721a' with a large range of movement, and on arm section 721a with a small range of movement. Only the first case 721b and the second case 722b are installed. All of the arm portions of the mat arm 72a are provided with a third case 723b and a fourth case 724. b and a sensor 741a may be installed, and the arm portion where the driving mechanism 73a is not installed may be installed. The robot arm protective cover 72b may not be installed. In this case, the robot arm portion may be The strength of the material is such that the product after irradiation with neutrons is not radioactive or is not affected by neutrons. The radioactivity of the product after irradiation by neutrons is very low, or the radioactivity of the product after irradiation by neutrons is very low. They may also be made of other materials, such as aluminum alloys, in which the half-life of the radioisotopes involved is short. It may also be made of neutron shielding material.

[0141] As can be appreciated, the couch positioner 70A need not include a linear axis, in which case In this case, the shielding device 70B does not include the slide rail cover member 71b, and the irradiation chamber 1 is Treatment table 20, treatment table positioning device 70A, and treatment table positioning device 101' The shielding device 70B may be installed.

[0142] To ensure that the equipment is clearly visible, radiation shielding devices should be installed to protect against other alarms, measuring devices, and monitoring devices. Good too.

[0143] In order to realize the operation of each device in the system and control of the treatment process, As shown in Figure 17, the control cables must be installed and arranged rationally. 01, conduits for passing and supporting cables in the control room 104 and accelerator room 102 The conduit 80A is installed in the cable extension direction. The cable is at least partially sealed in the circumferential direction around the cable in the extension direction, and is sealed perpendicular to the extension direction of the cable. The cross-sectional shape is circular, polygonal, V-shaped, horizontal V-shaped, U-shaped, horizontal U-shaped, etc., and the connecting part The electric wire is fixed to the wall, floor board, or ceiling board by a material (for example, a bolt). The radiation tube 80A passes through the irradiation room 101, the control room 104, and the accelerator along the corners of the ceiling and walls. It is to be understood that the electrical conduit 80A may be located in another location or space. The size of the conduit 80A can be designed according to the number of cables to be accommodated. The support frame 80B is installed in the accelerator chamber 102 and the beam transfer chamber 103. The accelerator 112, beam transfer section 12, auxiliary equipment 14, etc. are connected via many power, communication, and control cables. and a liquid (e.g., cooling medium) or gas (e.g., insulating gas) pipe has a support frame. The frame 80B is installed to place and guide the cables and conduits, and the support frame The frame 80B has a support surface S for supporting a cable or a pipe, and the support surface S is parallel to the ground. The mounting surface S is fixed to the ground, ceiling panel or other object in such a way that it is perpendicular to the ground. The support frame 80B may be fixed to the wall in some manner and installed in other spaces as needed. The drawing shows a support frame installed along the beam transfer section 12 in the beam transfer chamber 103. Only the support frame 80B is shown, and the support frame 80B is mounted on the ground in such a manner that the mounting surface S is parallel to the ground. The frame is made up of a side plate 81b and a plurality of horizontal plates 82b connected to the side plate 81b at predetermined intervals. The horizontal plate 82b forms the mounting surface S. The material is aluminum alloy, and as you can understand, aluminum alloy has a certain strength and the product after irradiation with neutrons is not radioactive or is not irradiated by neutrons. The radioactivity of the product after irradiation is very low, or it is produced after irradiation with neutrons. The half-life of radioactive isotopes is short, e.g., 90% or more (by weight) of which are C, H, O, N , Si, Al, Mg, Li, B, Mn, Cu, Zn, S, Ca, Ti It may be replaced by other materials consisting of one element.

[0144] In order to meet the normal operation and safety requirements of the system, a tubular member 90A (e.g., Pipes through which gas and liquid pass, such as ventilation pipes and fire pipes, and rod-shaped member 90B (various devices The support rods, screws, and other fixing rods required for the fixed installation are also included. These are generally made of steel and have a half-life of 1000 times longer after being irradiated with neutrons. Long-term radioisotopes, such as cobalt-60, are produced, secondary radiation occurs, and the pipe and fixed To reduce radiation damage and contamination to the rod, tubular member 90A (described above) The cooling medium and insulating gas pipes or rod-shaped member 90B are irradiated with neutrons. The product is not radioactive or the radioactivity of the product after irradiation with neutrons is very low, or materials in which the radioisotopes produced after irradiation by neutrons have short half-lives (e.g. 90% (by weight) or more of C, H, O, N, Si, Al, Mg, Li, B, Mn, Aluminum alloy consisting of at least one element selected from Cu, Zn, S, Ca, and Ti , plastic, or rubber), and the tubular member 90A or the rod-shaped member 18, an annular shielding device 91 may be provided on the outer periphery of the shielding device 90B. The annular shielding device 91 includes an inner sleeve 911, an outer sleeve 912, and an inner sleeve 911 and an outer sleeve 912, and a shielding material 913 is disposed between the inner sleeve 91 The outer sleeve 912 is a PVC tubular member, and the cross-sectional shape can be adjusted to suit specific needs. As can be seen, the inner sleeve 911 and the outer sleeve 91 2 is that the product after irradiation with neutrons is not radioactive or is The radioactivity of the product after irradiation is very low, or the radioactivity produced after irradiation with neutrons is It may also be made of other materials with short isotope half-lives, for example, the inner sleeve 911 and outer sleeve 920. 90% (by weight) or more of the material of the internal sleeve 912 is C, H, O, N, Si, Al At least one element selected from the group consisting of Mg, Li, B, Mn, Cu, Zn, S, Ca, and Ti The outer sleeve 912 may be a neutron moderator, and the neutrons after moderation are shielded. The shielding material 913 can absorb the neutrons better, and the shielding material 913 is a neutron shielding material, e.g. For example, the resin is made of a boron-containing resin. In one embodiment, the liquid boron-containing resin is mixed with PVC. The boron-containing resin was filled between the inner sleeve 911 and the outer sleeve 912, and solidified. Then, the entire annular shielding device 91 is formed, and the central axis of the annular shielding device 91 is located. The plane is divided into two parts, and the cable, the tubular member 90A or the rod-shaped member 90B is inserted from both sides. The two parts are fixed together by wrapping, gluing, bundling, etc., and the The shielding material 913 may be made of other neutron shielding materials, and may have other configurations, such as the inner sleeve 911 and the outer sleeve 912. The annular shielding device 91 may be disposed between the outer sleeve 912 and the tubular member in other ways. For example, the tubular member 90A or the rod-shaped member 90B may be provided on the outer periphery of the tubular member 90A or the rod-shaped member 90B. Before attaching the member 90B, the tubular member 90A or the rod-shaped member 90B is inserted into the annular shielding device 91. The cable is inserted into a sleeve 911. As can be seen, the cable has an annular shielding device 91 around its circumference. may be installed to further reduce the secondary radiation generated after the cable is irradiated by neutrons. Decrease.

[0145] The above description of exemplary specific embodiments of the present invention will help those skilled in the art to understand the present invention. While this facilitates the understanding of the present invention, it is clear that the present invention is not limited in scope to specific embodiments, and that the present invention will be readily apparent to those skilled in the art. Therefore, various modifications are within the spirit and scope of the present invention, which is defined and determined by the appended claims. These variations are obvious and within the scope of the present invention.

Claims

1. A neutron capture therapy system comprising: a charged particle beam generator; a beam transporter; and a neutron capture therapy system. a beam generating unit, the charged particle beam generating unit including an ion source that generates charged particles; Accelerating the charged particles generated by the ion source to generate charged particles having a desired energy and an accelerator for obtaining a neutron beam, the neutron beam generating unit including a target, a beam shaper, and and a collimator, and the target is disposed between the beam transfer section and the beam shaper. The charged particle beam generated by the accelerator is transferred to the beam transfer unit. The target is irradiated and interacts with the target to generate neutrons, and the generated neutrons The neutrons then pass through the beam shaper and collimator to form a therapeutic neutron beam. The neutron capture therapy system is entirely housed within a concrete building and illuminated. The irradiation chamber includes an irradiation chamber, an accelerator chamber, and a beam transfer chamber, and the irradiated object into which the drug is injected is placed in the irradiation chamber. The patient is treated by irradiation with the therapeutic neutron beam, and the accelerator chamber is The beam transfer chamber at least partially accommodates the beam generation section. The neutron beam generating section is also partially accommodated in the irradiation chamber and the beam transfer chamber.

1. A neutron capture therapy system at least partially contained within a wall of a neutron capture therapy device.

2. The radiation treatment system further includes a drug control room and a drug injection device for injecting a drug into the subject during radiation treatment. the medication injection device includes a medication passage assembly, a medication containing mechanism, and a medication control mechanism; The drug passage assembly is installed between the drug control chamber and the irradiation chamber, and the drug collection chamber The container mechanism and the drug control mechanism are installed in the drug control room, and the drug control room is provided with the 2. The neutron capture therapy method according to claim 1, wherein the injection of a drug into the subject is controlled. Legal system.

3. The drug passage assembly includes a drug passage member for injecting a drug, and a drug passage member for at least a receiving member that also partially receives the partition wall, the receiving member being disposed within the partition wall; and the drug passage member forms a passageway passing through the partition wall.

3. The neutron capture therapy system according to claim 2.

4. The treatment table further includes a treatment table positioning device and a shielding device for the treatment table positioning device.

2. The neutron capture therapy system according to claim 1,

5. The treatment table positioning device supports and positions the treatment table and includes at least one arm. the shielding device includes a robot arm including a robot arm protection unit that encases the arm unit. The neutron capture therapy system of claim 4 , including a protective cover.

6. The robot arm protective cover is provided with a collision prevention protection mechanism. The neutron capture therapy system of claim 5 .

7. The couch positioning device further includes a linear axis, and the robotic arm is configured to and the treatment table, and the linear axis is connected to a slide rail fixed in the building. and a support table connected to the robot arm, the support table being configured to support the treatment table and The robot arm is driven to slide along the slide rail, and the shielding device 6. The neutron capture therapy device according to claim 5, wherein the slide rail cover member is included. Legal system.

8. A neutron shielded space is formed in the building, and the neutron shielded space is Alternatively, the concrete formed in the irradiation chamber is a concrete containing boron and barite. or a neutron shielding plate is installed on the surface to form the neutron shielding space.

2. The neutron capture therapy system according to claim 1, wherein the neutron capture therapy system is a neutron capture therapy system.

9. Within the building, cables or gases and liquids for the operation of the neutron capture therapy system Tubular members for passage, or rod-shaped members for fixing and mounting within the building, or the cable A support device for supporting the rod or tubular member is provided, and the support device, the tubular member or the rod-shaped member 90% (by weight) or more of the material is C, H, O, N, Si, Al, Mg, Li , B, Mn, Cu, Zn, S, Ca, Ti, or The annular shielding device is installed on the outer periphery of the cable, tubular member or rod-shaped member, and the annular shielding device The shielding device includes an inner sleeve, an outer sleeve, and a sleeve between the inner sleeve and the outer sleeve. The neutron capture therapy system of claim 1 including installed shielding.

10. a cooling device at least partially located within the accelerator chamber or the beam transfer chamber; or Insulating gas filling and recovery equipment, or compressed air compressor, or vacuum environment providing equipment 10. The neutron capture system of claim 1, further comprising an auxiliary device including a vacuum pump. Capture therapy system.

11. 3. The cooling medium of the cooling device has a hardness of less than 60 mg / L.

11. A neutron capture therapy system according to claim 10.

12. The cooling device is used to cool the ion source, the accelerator, or the target, and the cooling medium or the cooling medium is deionized water, and the hardness of the deionized water is less than 17 mg / L.

11. The neutron according to claim 10, characterized in that the conductivity is 0.5 to 1.5 μS / cm. Scavenging therapy system.

13. The cooling device includes an external circulation device, an internal circulation device, and a heat exchanger. transporting a cooling medium to an assembly to be cooled of the neutron capture therapy system to absorb heat; Next, the cooling medium whose temperature has increased after absorbing heat is transported to the heat exchanger, and is then circulated from the external circulation device to the The cooling medium is cooled by heat exchange with the cold water transported to the heat exchanger. The external circulation device continuously transfers the cold water to the heat exchanger. and recovering the cooled water that has been heated after absorbing heat.

11. The neutron capture therapy system according to claim 10.

14. The accelerator includes an accelerator high voltage power supply that provides acceleration energy, An insulating gas is supplied to the accelerator high voltage power supply. providing an insulating gas or recovering the insulating gas from the accelerator high voltage power supply. The neutron capture therapy system according to claim 10 .

15. The insulating gas filling and recovery device has a gas source and a gas supply connected to the gas source and the accelerator high voltage power supply. and a storage container connected to each other, and the gas source includes a container containing the insulating gas.

15. The neutron capture therapy system according to claim 14.

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