CN109925610B - Neutron capture therapy system - Google Patents
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- CN109925610B CN109925610B CN201711350436.3A CN201711350436A CN109925610B CN 109925610 B CN109925610 B CN 109925610B CN 201711350436 A CN201711350436 A CN 201711350436A CN 109925610 B CN109925610 B CN 109925610B
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Abstract
The neutron capture treatment system comprises an accelerator, a neutron generating part and a beam shaping body, wherein the accelerator is used for generating a charged particle beam, the neutron generating part reacts with the charged particle beam to generate a neutron beam, the beam shaping body comprises a containing part, a retarder, a reflector, a shielding device and a beam outlet, the containing part is provided with a vacuum tube connected with the accelerator, the neutron generating part is arranged at the end part of the vacuum tube, the vacuum tube transmits the charged particles accelerated by the accelerator to the neutron generating part to enable the neutron generating part to react with the charged particle beam to form the neutron beam, the neutron generating part moves between a first position and a second position, the neutron generating part reacts with the charged particle beam to generate neutrons in the first position, the neutron generating part falls off from the beam shaping body, and the beam shaping body and the shielding device enable the neutron generating part to move from the first position to the second position in a shielding manner all the time so as to prevent radiation leaked from the neutron generating part from radiating to workers.
Description
Technical Field
The invention relates to a radioactive ray irradiation system, in particular to a neutron capture treatment system.
Background
With the development of atomic science, radiation therapy such as cobalt sixty, linac, electron beam, etc. has become one of the main means for cancer therapy. However, the traditional photon or electron treatment is limited by the physical condition of the radioactive rays, and a large amount of normal tissues on the beam path can be damaged while killing tumor cells; in addition, due to the different sensitivity of tumor cells to radiation, traditional radiotherapy often has poor therapeutic effects on malignant tumors with relatively high radiation resistance (such as glioblastoma multiforme (glioblastoma multiforme) and melanoma (melanoma)).
In order to reduce radiation damage to normal tissue surrounding a tumor, the concept of target treatment in chemotherapy (chemotherapy) has been applied to radiotherapy; for tumor cells with high radiation resistance, radiation sources with high relative biological effects (relative biological effectiveness, RBE) such as proton therapy, heavy particle therapy, neutron capture therapy, etc. are also actively developed. The neutron capture treatment combines the two concepts, such as boron neutron capture treatment, and provides better cancer treatment selection than the traditional radioactive rays by means of the specific aggregation of boron-containing medicaments in tumor cells and the accurate neutron beam regulation.
In an accelerator neutron capture treatment system, a charged particle beam is accelerated by an accelerator, the charged particle beam is accelerated to energy sufficient to overcome the coulomb repulsion of a neutron generating part in a beam shaping body, nuclear reaction is carried out with the neutron generating part to generate neutrons, so that the neutron generating part is irradiated by the accelerated charged particle beam with high power in the process of generating neutrons, the temperature of the neutron generating part is greatly increased, the service life of the neutron generating part is influenced, a great amount of radiation rays are required to be generated by the neutron generating part irradiated by the accelerated charged particle beam with high energy level, and the radiation safety hazard is required to be generated when the neutron generating part is replaced.
Disclosure of Invention
In order to provide a neutron capture therapy system for reducing radiation safety hazards, one embodiment of the application provides a neutron capture therapy system comprising an accelerator for generating a charged particle beam, a neutron generating part for generating a neutron beam by reacting with the charged particle beam, and a beam shaping body, wherein the beam shaping body comprises a containing part, a retarder adjacent to the neutron generating part, a reflector surrounding the retarder, a thermal neutron absorber adjacent to the retarder, a radiation shield arranged in the beam shaping body, a shielding device adjacent to the beam shaping body and a beam outlet, the containing part is provided with a vacuum tube connected to the accelerator, the neutron generating part is arranged at the end part of the vacuum tube, the vacuum tube transmits the charged particles accelerated by the accelerator to the neutron generating part so as to enable the neutron generating part to react with the charged particle beam to generate neutrons, the neutrons form a neutron beam, the retarder limits a main shaft, the retarder decelerates neutrons generated from the neutron generating part to an epithermal neutron energy region, the reflector returns deviated neutrons to the shielding device, and the neutron generating radiation beam from the second position is used for generating radiation beam, the neutron radiation beam is not normally generated between the neutron generating part and the second position, and the neutron capturing therapy system is used for generating radiation from the second position, and the neutron capturing therapy system is normally irradiated by the second position, the beam shaping body and the shielding device enable the neutron generating part to be always in shielding during the process of moving from the first position to the second position so as to prevent radiation leaked from the neutron generating part from being irradiated to staff.
When the neutron producing device is positioned in the beam shaping body, the radiation shield in the beam shaping body can shield the radiation leaked from the neutron producing device to avoid radiating the radiation to the staff; after the neutron generating part breaks away from the beam integer, the neutron generating part cannot be shielded through radiation shielding, and the neutron generating part is shielded through the shielding device at the moment, so that the neutron generating part is always in a shielding state in the process of moving from the first position to the second position, and radiation leaked by the neutron generating part is prevented from being irradiated to staff.
Preferably, the vacuum tube includes at least a first vacuum tube portion connected to the accelerator, a second vacuum tube portion accommodated in the beam shaper accommodating portion and accommodating the neutron generator, and a third vacuum tube portion connecting the first vacuum tube portion and the second vacuum tube portion, wherein the third vacuum tube portion is detachable to provide a space in which the neutron generator moves out of the accommodating portion, and in the second position, the neutron generator moves out of the accommodating portion together with the second vacuum tube portion and falls off from the beam shaper.
Further, the shielding device comprises a bottom wall, a fourth side wall and a second side wall, wherein the fourth side wall and the second side wall are connected to the bottom wall and are oppositely arranged, the bottom wall and the two side walls form a U-shaped structure with a first opening, a second opening and a third opening, the first opening is adjacent to the first vacuum tube part, the second opening is adjacent to the second vacuum tube part, and the third vacuum tube part penetrates through the third opening. In this application, the shielding device is preferably disposed outside the vacuum tube, and then the third vacuum tube is detached, and in actual operation, the shielding device may be mounted after the third vacuum tube is detached.
Further, the shielding device further comprises a top wall, a third side wall and a first side wall, wherein the top wall is arranged opposite to the bottom wall, the third side wall is connected with the bottom wall, the top wall is arranged opposite to the first side wall, the bottom wall, the top wall and the four side walls form a shielding space, the top wall can rotate around the second side wall or the fourth side wall in a direction away from the shielding space, and the first side wall and the third side wall can rotate around the bottom wall in a direction away from the shielding space respectively, so that the shielding device is of a U-shaped structure. When the shielding device is positioned between the first vacuum tube part and the second vacuum tube part, the shielding device is in a U-shaped structure; when the neutron producing section is located together with the second vacuum tube section, the shielding device forms a shielding space to shield the neutron producing section.
Further, in order to facilitate the neutron generating part to move out of the accommodating part, a filler is filled between the outer periphery of the vacuum tube and the inner wall of the accommodating part, the neutron capture treatment system further comprises a cooling device which is positioned in the accommodating part and cools the neutron generating part, the filler is filled in the outer periphery of the vacuum tube and the inner wall of the accommodating part to wrap the cooling device, and when the neutron generating part moves into the shielding device, the cooling device and the filler move into the shielding device together with the neutron generating part.
Further, the filler is a material capable of absorbing neutrons or reflecting neutrons.
Further, the neutron capture treatment system further comprises a cooling device which is positioned in the accommodating part and used for cooling the neutron generating part, and the filler is filled in the periphery of the vacuum tube and the inner wall of the accommodating part to wrap the cooling device.
As one preferable, the cooling device includes a first cooling part located at an end of the vacuum tube to be in planar contact with the neutron generating part, and a second cooling part and a third cooling part located at both sides of the first cooling part and respectively communicated with the first cooling part, the second cooling part and the third cooling part extending in a direction parallel to the axis of the neutron beam and being respectively located at upper and lower sides of the vacuum tube to form a type structure with the first cooling part.
Further, in order to further reduce the contact between the staff and the neutron generating part and improve the radiation safety, the neutron capturing treatment system further comprises a containing device positioned below the vacuum tube, the neutron generating part moves into the shielding device from the containing part and then falls into the containing device, and the containing device is made of shielding materials.
Further, the accommodating device comprises a bottom and four side parts connected to the bottom, the bottom and the four side parts are connected to form an accommodating space with an opening, the accommodating device is further provided with two rotating parts shielded in the opening, one end of each rotating part is connected with the side part, the other end of each rotating part can rotate relative to the connected side part into the accommodating space, and in a natural state, the two rotating parts are shielded above the accommodating space to form the top of the accommodating device; under the action of external force, the rotating part rotates to the accommodating space and is accommodated in the accommodating space; when the external force is removed, the rotating part is restored to a natural state.
Drawings
FIG. 1 is a schematic view of a first embodiment of a neutron capture therapy system of the present application, wherein a neutron producing device is located at a first location;
FIG. 2 is a cross-sectional view of the cooling device of FIG. 1 taken perpendicular to the direction of irradiation of the neutron beam;
FIG. 3 is a partial cross-sectional view of the neutron capture therapy system of FIG. 1 taken perpendicular to the direction of irradiation of the neutron beam;
FIG. 4 is a schematic view of the third vacuum tube section of the vacuum tube of FIG. 1, disassembled;
FIG. 5 is a schematic view of the third vacuum tube section of FIG. 4 removed, with the second vacuum tube section and neutron-generating section moved out of the receiving section, i.e., the neutron-generating section is in a second position;
FIG. 6 is a schematic diagram of a second embodiment of a neutron capture therapy system of the present application, wherein a shielding device is mounted between a first vacuum tube portion and a second vacuum tube portion;
FIG. 7 is a schematic view of the second vacuum tube section and neutron-generating section of FIG. 6 moved into a shielding device;
FIG. 8 is a schematic view of the shielding device of FIG. 6 with the second vacuum tube section and neutron generator section housed therein;
fig. 9 is a schematic perspective view of the shielding device of fig. 6;
FIG. 10 is a schematic view of another embodiment of the shielding device of FIG. 9;
fig. 11 is a perspective view of the shielding device shown in fig. 10;
FIG. 12 is a schematic view of a third embodiment of a neutron capture treatment system of the present application;
FIG. 13 is a schematic view of the second shielding portion of FIG. 12 moving away from the neutron-generating portion relative to the first shielding portion;
FIG. 14 is a partial cross-sectional view of the neutron capture therapy system of FIG. 12 taken perpendicular to the direction of irradiation of the neutron beam;
FIG. 15 is a partial cross-sectional view of the neutron capture therapy system of FIG. 13 taken perpendicular to the direction of irradiation of the neutron beam;
FIG. 16 is a schematic view of the first vacuum tube section and neutron-generating section moving out of the receiving space after the second shielding section shown in FIG. 14 has moved;
FIG. 17 is a partial cross-sectional view of the neutron capture therapy system of FIG. 16 taken perpendicular to the direction of irradiation of the neutron beam;
FIG. 18 is a schematic view of the receiving device of FIG. 15 in a natural state;
fig. 19 is a schematic view of the accommodating device in fig. 18 after an external force is applied.
Detailed Description
Neutron capture therapy has been increasingly used in recent years as an effective means of treating cancer, where it is most common to supply neutrons from a boron neutron capture therapy to a nuclear reactor or accelerator. Taking accelerator boron neutron capture therapy as an example, the basic components of accelerator boron neutron capture therapy generally include an accelerator for accelerating charged particles (e.g., protons, deuterons, etc.), a neutron production and heat removal system, and a beam shaping body. Wherein the accelerated charged particles react with the metallic neutron generator to generate neutrons,the appropriate nuclear reaction is selected according to the required neutron yield and energy, the available energy and current of the accelerated charged particles, the physicochemical properties of the metal neutron generator, and the like. The nuclear reactions in question are 7 Li(p,n) 7 Be and Be 9 Be(p,n) 9 And B, the two reactions are endothermic reactions, and the energy threshold values of the two nuclear reactions are 1.881MeV and 2.055MeV respectively. Because the ideal neutron source for boron neutron capture treatment is epithermal neutrons with a keV energy level, theoretically, if protons with energy only slightly higher than a threshold are used to bombard a metallic lithium neutron generating part, relatively low-energy neutrons can Be generated, and the neutron capturing treatment can Be used clinically without too much retarding treatment, however, the proton action cross section of the two neutron generating parts of lithium metal (Li) and beryllium metal (Be) and the threshold energy is not high, and in order to generate enough neutron flux, protons with higher energy are generally selected to initiate nuclear reaction.
The ideal neutron generator should have high neutron yield, a neutron energy distribution close to that of the epithermal neutron energy region (described in detail below), no too much intense penetrating radiation, safety, low cost, easy operation, and high temperature resistance, but practically no nuclear reaction meeting all the requirements can be found. In the embodiment of the application, a neutron generating part made of lithium metal is adopted. However, it is well known to those skilled in the art that the material of the neutron generating element may be made of other metallic materials than those mentioned above.
The requirements for the heat removal system will vary depending on the chosen nuclear reaction, e.g 7 Li(p,n) 7 Be has lower melting point and thermal conductivity due to the metal neutron generator (lithium metal), and requires a heat removal system 9 Be(p,n) 9 B is high. In the examples of the present application use is made of 7 Li(p,n) 7 Nuclear reaction of Be. From this, it is understood that the temperature of the neutron generator irradiated with the high-energy-level accelerated charged particle beam inevitably increases greatly, and the service life of the neutron generator is affected.
Regardless of whether the neutron source of the boron neutron capture treatment is from the nuclear reaction of the charged particles of the nuclear reactor or accelerator with the neutron generating section, a mixed radiation field is generated, i.e. the beam contains neutrons and photons with low energy to high energy. For boron neutron capture treatment of deep tumors, the more radiation content, except for epithermal neutrons, the greater the proportion of non-selective dose deposition of normal tissue, and therefore the less radiation that will cause unnecessary doses. In addition to the air beam quality factor, in order to better understand the dose distribution of neutrons in the human body, the embodiments of the present application use a human head tissue prosthesis for dose calculation, and use the prosthesis beam quality factor as a design reference for neutron beams, as will be described in detail below.
The international atomic energy organization (IAEA) gives five air beam quality factor suggestions for neutron sources for clinical boron neutron capture treatment, and the five suggestions can be used for comparing the advantages and disadvantages of different neutron sources and serve as reference bases for selecting neutron production paths and designing beam shaping bodies. These five suggestions are as follows:
epithermal neutron beam flux Epithermal neutron flux>1x10 9 n/cm 2 s
Fast neutron contamination Fast neutron contamination<2x10 -13 Gy-cm 2 /n
Photon pollution Photon contamination<2x10 -13 Gy-cm 2 /n
The ratio thermal to epithermal neutron flux ratio of thermal neutron to epithermal neutron flux is less than 0.05
Neutron current to flux ratio epithermal neutron current to flux ratio >0.7
Note that: the epithermal neutron energy region is between 0.5eV and 40keV, the thermal neutron energy region is less than 0.5eV, and the fast neutron energy region is more than 40keV.
1. Epithermal neutron beam flux:
the neutron beam flux and the boron-containing drug concentration in the tumor together determine the clinical treatment time. If the concentration of the boron-containing medicament in the tumor is high enough, the requirement on the neutron beam flux can be reduced; conversely, if the boron-containing drug concentration in the tumor is low, a high flux epithermal neutron is required to administer a sufficient dose to the tumor. IAEA requires a epithermal neutron beam flux of greater than 10 epithermal neutrons per square centimeter per second 9 This fluxThe lower neutron beam can generally control the treatment time to be within one hour for the current boron-containing drugs, and the short treatment time not only has advantages for positioning and comfort of patients, but also can effectively utilize the limited residence time of the boron-containing drugs in tumors.
2. Fast neutron contamination:
since fast neutrons cause unnecessary normal tissue doses, which are positively correlated with neutron energy, as a matter of pollution, the fast neutron content should be minimized in the neutron beam design. Fast neutron contamination is defined as the fast neutron dose accompanied by a unit epithermal neutron flux, with IAEA recommended for fast neutron contamination as less than 2x10 -13 Gy-cm 2 /n。
3. Photon pollution (gamma ray pollution):
gamma rays belonging to the intense penetrating radiation can cause non-selective dose deposition of all tissues on the beam path, so reducing the gamma ray content is also an essential requirement for neutron beam design, gamma ray pollution is defined as the gamma ray dose accompanied by the unit epithermal neutron flux, and the proposal of IAEA on gamma ray pollution is less than 2x10 -13 Gy-cm 2 /n。
4. Ratio of thermal neutron to epithermal neutron flux:
because of high thermal neutron attenuation speed and poor penetrating capacity, most of energy is deposited on skin tissues after entering a human body, and thermal neutrons are required to be used as neutron sources for boron neutron capture treatment for superficial tumors such as melanoma and the like, so that the thermal neutron content is required to be reduced for deep tumors such as brain tumors and the like. The IAEA to thermal neutron to epithermal neutron flux ratio is recommended to be less than 0.05.
5. Neutron current to flux ratio:
the ratio of neutron current to flux represents the directionality of the beam, the larger the ratio is, the better the frontage of the neutron beam is, the high frontage neutron beam can reduce the surrounding normal tissue dose caused by neutron divergence, and the treatable depth and the posture setting elasticity are improved. IAEA is recommended to have a neutron current to flux ratio greater than 0.7.
In order to solve the replacement problem of the neutron generating part, and simultaneously, the contact between workers and radial rays is reduced as much as possible, the application provides a neutron capture treatment system.
Since the main radiation to the target person is the radiation generated by nuclear reaction after the charged particle beam is irradiated to the neutron generating section, the present application is intended to explain disassembly of the neutron generating section after nuclear reaction, and does not explain installation of a new neutron generating section.
As shown in fig. 1, the neutron capture therapy system 100 includes an accelerator 200 for generating a charged particle beam, a neutron generating section 10 for generating a neutron beam N by reacting with the charged particle beam P, and a beam shaping body 20, wherein the beam shaping body 20 includes a housing section 21, a retarder 22 adjacent to the neutron generating section 10, a reflector 23 surrounding the retarder 22, a thermal neutron absorber 24 adjacent to the retarder 22, a radiation shield 25 and a beam outlet 26 provided in the beam shaping body 20, the housing section 21 houses a vacuum tube 30 connected to the accelerator 200, and the neutron generating section 10 is provided at an end of the vacuum tube 30 so as to be adjacent to the retarder 22. The vacuum tube 30 transmits the charged particles P accelerated by the accelerator 200 to the neutron generator 10, and the accelerator 200 accelerates the charged particles P to energy sufficient to overcome the nuclear force of the target material and generate the energy with the neutron generator 10 7 Li(p,n) 7 Be nuclear reacts to produce neutrons, which form a neutron beam N defining a principal axis I. The retarder 22 retards neutrons generated from the neutron generator 10 to an epithermal neutron energy region. The reflector 23 directs the deflected neutrons back to the moderator 22 to increase the epithermal neutron beam intensity. The thermal neutron absorber 24 is used to absorb thermal neutrons to avoid overdosing with shallow normal tissue during treatment. The radiation shield 25 is used to shield the leaking neutrons and photons to reduce the normal tissue dose in the non-irradiated region.
Referring to fig. 2, the neutron capture therapy system 100 further includes a cooling device 40 that cools the neutron generating section 10 to increase the useful life of the neutron generating section.
The cooling device 40 includes a first cooling portion 41 positioned at an end of the vacuum tube 30 to be in planar contact with the neutron generating portion 10, and a second cooling portion 42 and a third cooling portion 43 positioned at both sides of the first cooling portion 41 and respectively communicating with the first cooling portion 41. A gap exists between the outer periphery of the vacuum tube 30 and the inner wall of the housing portion 21, and the second cooling portion 42 and the third cooling portion 43 extend in the gap in a direction parallel to the neutron beam axis I and are located on the upper and lower sides of the vacuum tube 30, respectively, to form a type structure with the first cooling portion 41. In order to ensure that the beam shaping body 20 obtains good neutron beam quality while the cooling device 40 cools the neutron generating section 10 at the end of the vacuum tube 30, a portion of the vacuum tube 30 is embedded in the retarder 22 (not shown). The second cooling unit 42 inputs the cooling medium to the first cooling unit 41, and the third cooling unit 43 outputs the cooling medium in the first cooling unit 41. The first cooling part 41 is located between the neutron producing part 10 and the retarder 22, one side of the first cooling part 41 is in direct planar contact with the neutron producing part 10, and the other side is in contact with the retarder 14.
The first cooling portion 41 includes a first contact portion 411, a second contact portion 412, and a cooling groove 413 between the first contact portion 411 and the second contact portion 412 through which a cooling medium passes. The first contact portion 411 is in direct contact with the neutron production portion 10, and the second contact portion 412 may be in direct contact with the retarder 22 or may be in indirect contact with the retarder through air. The cooling tank 413 has an input tank 414 communicating with the second cooling unit 42 and an output tank 415 communicating with the third cooling unit 43. The first contact 411 is made of a thermally conductive material. The first contact portion 411 is made of a heat conductive material (such as a material having good heat conductive properties such as Cu, fe, al, etc.) or a material capable of both heat conduction and foaming inhibition, and the second contact portion 412 is made of a foaming inhibition material or a material capable of both heat conduction and foaming inhibition is made of any one of Fe, ta, or V. The neutron generator 10 is heated by the accelerated irradiation temperature rise of a high energy level, and the first contact 411 outputs heat, and the cooling medium flowing through the cooling tank 413 brings out heat, thereby cooling the neutron generator 10. In the present embodiment, the cooling medium is water.
Referring to fig. 1 and 5, fig. 1 is a schematic view of a neutron generating device in a first position, and fig. 5 is a schematic view of the neutron generating device in a second position. The neutron generator 10 moves between a first position in which the neutron generator 10 is capable of reacting with the charged particle beam to generate neutrons, and a second position in which the neutron generator 10 is disengaged from the beam shaper 20.
Referring to fig. 3, a gap is formed between the housing portion 21 and the outer wall of the vacuum tube 30, and the gap is filled with a filler 50. The filler 50 is coated on the outer wall of the vacuum tube 30 and the cooling device 40. The filler 50 is a substance capable of absorbing or reflecting neutrons, such as a lead alloy or an aluminum alloy. In the embodiment of the application, the content of lead in the lead alloy is more than or equal to 85%, and the content of aluminum in the aluminum alloy is more than or equal to 85%. The filler 50 can reflect neutrons reflected or scattered into the gap into the retarder 22 or the reflector 23, so that the yield of epithermal neutrons is increased and the time required for the irradiated body to be irradiated is reduced; on the other hand, the leakage of neutrons to the outside of the beam shaping body 20 can be avoided, the adverse effect on the instrument of the neutron capture treatment system can be avoided, and the radiation safety can be improved. When the neutron generator 10 moves to the outside of the housing 21, the cooling device 40 and the filler 50 can move out of the housing 21 together with the neutron generator 10, and can be detached from the beam shaping body 20.
As a first embodiment, referring to fig. 1, 4 to 5, the vacuum tube 30 includes a first vacuum tube 31 connected to the accelerator 200, a second vacuum tube 32 accommodated in the accommodating portion 21, and a third vacuum tube 33 connecting the first vacuum tube 31 and the second vacuum tube 32. One end of the second vacuum tube 32 is adjacent to the retarder 22, and the other end extends out of the housing 21 and is connected to the third vacuum tube 33, and the neutron generator 10 is provided at an end of the second vacuum tube 32 and is adjacent to the retarder 22. The third vacuum tube portion 33 is detachable from the first and second vacuum tube portions 31 and 32 to shorten the overall length of the vacuum tube 30, thereby providing a space in which the neutron generating portion 10 moves out of the housing portion 21 in the opposite direction to the irradiation of the neutron beam N. When the third vacuum tube 33 is detached from between the first vacuum tube 31 and the second vacuum tube 32, the second vacuum tube 32 can be moved out of the housing 21 in the opposite direction to the irradiation of the neutron beam N, and is detached from the beam shaping body 20.
In this embodiment, the vacuum tube 30 can be detached from the beam shaping body 20 because the first vacuum tube 31 has a space to move out of the accommodating portion 21 in the opposite direction to the irradiation of the neutron beam N after the second vacuum tube 32 is detached, that is, a space for giving way to the neutron generating portion 10 is provided by changing the entire length of the vacuum tube 30. As another embodiment of changing the overall length of the vacuum tube, the neutron generating section may be configured to retract along the direction of irradiation of the neutron beam (e.g., by configuring a portion of the vacuum tube outside the beam shaper as a retractable bellows, the overall length of the vacuum tube becomes shorter when the bellows is compressed, and the neutron generating section moves the exit beam shaper along with the vacuum tube in the opposite direction of irradiation of the neutron beam), which will not be described in detail herein.
Fig. 6-8 are schematic diagrams of a second embodiment of a neutron capture therapy system of the present application, where the neutron capture therapy system 100 further includes a shielding device 60 to further reduce the radiation safety hazard to personnel.
Referring to fig. 9, the shielding device 60 includes a bottom wall 61, a top wall 62 disposed opposite to the bottom wall 61, and first, second, third and fourth side walls 63, 64, 65 and 66 connecting the bottom wall 61, the top wall 62. The first side wall 63 and the third side wall 65 are disposed opposite to each other, the second side wall 64 and the fourth side wall 66 are disposed opposite to each other, and the bottom wall 61, the top wall 62, and the four side walls are connected to form a shielding space 67. The top wall 62 is rotatable about the second side wall 64 or the fourth side wall 66 in a direction away from or toward the shielding space 67, and the first side wall 63 and the third side wall 65 are rotatable about the bottom wall 61 in a direction away from or toward the shielding space 67, respectively. The rotation of the top wall 62, the first side wall 63 and the third side wall 65 is achieved by a rotation member 68 mounted on the bottom wall 61, the first side wall 63 and the third side wall 65. When the top wall 62, the first side wall 63 and the third side wall 65 rotate around the rotating member 68 in a direction away from the shielding space 67, the shielding device 60 has a U-shaped structure, so as to facilitate the staff to move the first vacuum tube 31 out of the beam shaping body 20 to move the neutron generating part 10 in the shielding space 67.
Of course, as another embodiment of the shielding device 60 (in conjunction with fig. 10 and 11), the shielding device 60 may also include only the bottom wall 61 and two side walls (64, 66) connected to the bottom wall 61 and disposed opposite each other. The bottom wall 61 and the two side walls form a first opening 631, a second opening 651, which are oppositely arranged, and a third opening 621, which is oppositely arranged to the bottom wall 61, i.e. the bottom wall 61 and the two side walls form a U-shaped structure with a shielding space 67. The first opening 631 is adjacent to the first vacuum tube portion 31, the second opening 651 is adjacent to the second vacuum tube portion 32, the third vacuum tube portion passes through the third opening 621 for a worker to move the second vacuum tube portion 31 to the shielding space 67. In this embodiment, the shielding device 60 is disposed on the outer periphery of the vacuum tube 30, when the neutron generating portion needs to be replaced, the third vacuum tube portion is detached, the worker moves the second vacuum tube portion 32 until the neutron generating portion 10, the filling portion 50 and the cooling device 40 all move along with the second vacuum tube portion 32 and are contained in the shielding space 67 of the shielding device 60, the shielding device 60 is removed from the first vacuum tube portion 31, and then the top wall 62, the first side wall 63 and the third side wall 65 are rotated respectively, so that the top wall 62, the first side wall 63 and the third side wall 65 are covered in the shielding space 67 respectively to comprehensively shield the radiation in the shielding space 67. The shielding device 60 shields the radiation rays remaining in the neutron generator 10 after the nuclear reaction, thereby reducing the potential safety hazard of the radiation rays to the staff. Of course, in the actual operation, the shielding device 60 may be disposed between the first vacuum tube 31 and the second vacuum tube 32 after the third vacuum tube 33 is detached.
The shielding device 60 may be provided by connecting (abutting) the first opening 631 and the first vacuum tube portion 31, and connecting (abutting) the second opening 651 and the second vacuum tube portion 32 (beam shaping body 20), or by providing an additional structure to support it on the outer periphery of the vacuum tube 30.
Because the staff stands in the side of beam integer body and carries out the change work to the neutron production portion, consequently when the staff removes second vacuum tube portion, the diapire and the lateral wall of shielding portion all can shield the radiation that remains in the neutron production portion, and after the neutron production portion moved in the shielding space jointly with the second vacuum tube portion, rotated roof, first lateral wall and third lateral wall, made the shielding space surrounded by shielding material totally to further reduce the radiation potential safety hazard of staff. Of course, the shielding device 60 of the U-shaped structure is also sufficient to shield the radiation that may be radiated by the staff to reduce the radiation safety hazard of the staff.
Fig. 12-17 are schematic diagrams illustrating a third embodiment of a neutron capture therapy system of the present application. The neutron capture therapy system 100' further includes a shielding portion adjacent to the retarder 22, and the shielding portion is wrapped around the outer periphery of the housing portion 21. The shielding portion includes a first shielding portion 71 and a second shielding portion 72, and the second shielding portion 72 is movable relative to the first shielding portion 71 in a direction away from the vacuum tube 30 to drop the neutron generating portion 10 from the housing portion 2. The vacuum tube 30 includes at least a first vacuum tube portion 31' connected to the accelerator 200 and a second vacuum tube portion 32' connected to the first vacuum tube portion 31' and accommodated in the accommodating portion 21. When the first vacuum tube 31 'is separated from the second vacuum tube 32' and the second shielding portion 72 moves away from the neutron generator 10 to the extent that the first vacuum tube 31 'can be lowered from the accommodating portion 21, the neutron generator 10 moves out of the accommodating portion 21 together with the second vacuum tube 32' and is separated from the beam shaping body 20. The filling part and the cooling device are also detached from the beam shaping body 20 together with the neutron generator 10.
In order to reduce the potential safety hazard of the radiation to the staff, the neutron capture treatment system may further include a shielding device 60 as in the second embodiment, and may also include a receiving device 80 located below the vacuum tube 30, where the neutron generating portion 10 falls into the receiving device 80 from the receiving portion 21, and the receiving device 80 is made of a shielding material.
Referring to fig. 18 to 19, the accommodating device 80 includes a bottom 81, a top 82 disposed opposite to the bottom 81, and four sides 83 connected to the bottom 81 and the top 82, and the bottom 81, the top 82, and the four sides 83 are connected to form the accommodating device 80 having an accommodating space 84. The top 82 of the accommodating device 80 is further provided with an opening, and the opening is covered with two oppositely arranged rotating parts 85, wherein one end of each rotating part 85 is connected to the top 82, and the other end of each rotating part can rotate relative to the top into the accommodating space 84. In a natural state, the two rotating parts 85 are located above the accommodating space 84 and are shielded from the opening; under the action of external force, the rotating part 85 rotates towards the accommodating space 84 and is accommodated in the accommodating space 84; when the external force is removed, the rotating portion 85 is restored to a natural state. The movement of the rotating portion 85 may be achieved by providing a shaft member at the top 82, and moving the rotating portion 85 around the shaft member (not shown) into the accommodating space 84 or covering the opening above the accommodating space 84, which will not be described in detail herein.
Of course, the accommodating device in the third embodiment may also be provided in the first embodiment and the second embodiment, so as to further avoid the possibility that the worker directly contacts with the radiation.
The neutron capture treatment system accelerates the charged particle beam P by an accelerator, and as a preferred embodiment, the neutron generator 10 is made of lithium metal, and the charged particle beam is accelerated to energy sufficient to overcome the coulomb repulsion of the nuclei of the neutron generator, and generates a reaction with the neutron generator 10 7 Li(p,n) 7 Be nuclear reactions to produce neutrons, beam shaping body 20 can retard neutrons to the epithermal neutron energy region and reduce thermal and fast neutron content. As shown in fig. 3, the neutron generating section 10 includes a lithium target layer 101 and an oxidation resistant layer 102 located on one side of the lithium target layer 10 for preventing oxidation of the lithium target layer 101. The oxidation resistant layer 102 of the neutron generating section 10 is made of Al or stainless steel.
The retarder 22 is made of a material having a large fast neutron action cross section and a small epithermal neutron action cross section, the reflector 23 is made of a material having a strong neutron reflection capability, and the thermal neutron absorber 24 is made of a material having a large thermal neutron action cross section. As a preferred embodiment, the retarder 22 is defined by D 2 O、AlF 3 、Fluental TM 、CaF 2 、Li 2 CO 3 、MgF 2 And Al 2 O 3 Is made of at least one of Pb or Ni, the reflector 23 is made of at least one of Pb or Ni, and the thermal neutron absorber 24 is made of 6 Li.
The radiation shield 25 includes a photon shield 251 and a neutron shield 252. As a preferred embodiment, the radiation shield 25 includes a photon shield 251 made of lead (Pb) and a neutron shield 252 made of Polyethylene (PE).
For ease of description of the present application, like reference numerals denote like elements throughout the present application.
The neutron capture therapy systems disclosed herein are not limited to the structures described in the above embodiments and shown in the drawings. For example, the retarder may be provided as a cylinder, the cooling means may be provided in several, and the receiving conduit correspondingly has several etc. Obvious changes, substitutions, or modifications to the materials, shapes, and locations of the components therein are within the scope of the present application.
Claims (9)
1. A neutron capture therapy system, characterized by: the neutron capture treatment system comprises an accelerator for generating a charged particle beam, a neutron generating part for generating a neutron beam by reacting with the charged particle beam, and a beam shaping body, wherein the beam shaping body comprises a containing part, a retarder adjacent to the neutron generating part, a reflector surrounding the retarder, a thermal neutron absorber adjacent to the retarder, a radiation shield arranged in the beam shaping body, a shielding device adjacent to the beam shaping body and a beam outlet, the containing part is provided with a vacuum tube connected with the accelerator, the neutron generating part is arranged at the end part of the vacuum tube, the vacuum tube transmits the charged particles accelerated by the accelerator to the neutron generating part to enable the neutron generating part to react with the charged particle beam to generate neutrons, the neutrons form a neutron beam, and the neutron beam defines a main shaft, the retarder retards neutrons generated from the neutron generating part to an epithermal neutron energy region, the reflector guides the deviated neutrons back to the retarder to improve the epithermal neutron beam intensity, the radiation shield is used for shielding leaked neutrons and photons to reduce normal tissue dose of a non-irradiated region, the vacuum tube at least comprises a first vacuum tube part connected with the accelerator, a second vacuum tube part accommodated in the beam shaping body accommodating part and accommodating the neutron generating part, and a third vacuum tube part connected with the first vacuum tube part and the second vacuum tube part, the neutron generating part moves between a first position and a second position, the shielding device at least comprises a bottom wall, a second side wall and a fourth side wall which are connected with the bottom wall and are oppositely arranged, and the bottom wall, the second side wall and the fourth side wall form a first opening, the shielding device further comprises a top wall, a first side wall and a third side wall which are arranged opposite to the bottom wall, the first side wall, the top wall and the third side wall are connected, the first side wall and the third side wall are arranged opposite to each other, the bottom wall, the top wall and the four side walls form a shielding space, in the first position, the neutron generating part reacts with a charged particle beam to generate neutrons, in the second position, the neutron generating part falls off from the beam shaping body and moves into the shielding space, and the beam shaping body and the shielding device enable the neutron generating part to be always in shielding in the process of moving from the first position to the second position so as to prevent radiation leaked from the neutron generating part from radiating to staff.
2. The neutron capture therapy system of claim 1, wherein: the third vacuum tube portion is detachable to provide a space in which the neutron generating portion moves out of the housing portion, and in the second position, the neutron generating portion can move out of the housing portion together with the second vacuum tube portion and come off from the beam shaping body.
3. The neutron capture therapy system of claim 2, wherein: the top wall can rotate around the second side wall or the fourth side wall in a direction away from the shielding space, and the first side wall and the third side wall can rotate around the bottom wall in a direction away from the shielding space respectively, so that the shielding device is of a U-shaped structure.
4. The neutron capture therapy system of claim 3, wherein: when the shielding device is positioned between the first vacuum tube part and the second vacuum tube part, the shielding device is in a U-shaped structure; when the neutron generating part is located together with the second vacuum tube part, the shielding device forms the shielding space to shield the neutron generating part.
5. The neutron capture therapy system of claim 1, wherein: the neutron capture treatment system comprises a vacuum tube, a neutron generator, a neutron shielding device, a filling material, a cooling device and a neutron capture treatment system, wherein the filling material is filled between the periphery of the vacuum tube and the inner wall of the accommodating part, the cooling device is positioned in the accommodating part and used for cooling the neutron generator, the filling material is filled in the periphery of the vacuum tube and the inner wall of the accommodating part to wrap the cooling device, and when the neutron generator moves into the shielding device, the cooling device and the filling material move into the shielding device together with the neutron generator.
6. The neutron capture therapy system of claim 5, wherein: the filler is a material capable of absorbing neutrons or reflecting neutrons.
7. The neutron capture therapy system of claim 5, wherein: the cooling device comprises a first cooling part, a second cooling part and a third cooling part, wherein the first cooling part is positioned at the end part of the vacuum tube and is in plane contact with the neutron generating part, the second cooling part and the third cooling part are positioned at two sides of the first cooling part and are respectively communicated with the first cooling part, and the second cooling part and the third cooling part extend along the direction parallel to the axis of the neutron beam and are respectively positioned at the upper side and the lower side of the vacuum tube to form a type structure with the first cooling part.
8. The neutron capture therapy system of claim 1, wherein: the neutron capture treatment system further comprises a containing device positioned below the vacuum tube, the neutron generating part moves into the shielding device from the containing part and falls into the containing device, and the containing device is made of shielding materials.
9. The neutron capture therapy system of claim 8, wherein: the accommodating device comprises a bottom and four side parts connected with the bottom, the bottom and the four side parts are connected to form an accommodating space with an opening, the accommodating device is also provided with two rotating parts shielded in the opening, one end of each rotating part is connected with the side part, the other end of each rotating part can rotate relative to the connected side part into the accommodating space, and in a natural state, the two rotating parts are shielded above the accommodating space to form the top of the accommodating device; under the action of external force, the rotating part rotates to the accommodating space and is accommodated in the accommodating space; when the external force is removed, the rotating part is restored to a natural state.
Priority Applications (7)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201711350436.3A CN109925610B (en) | 2017-12-15 | 2017-12-15 | Neutron capture therapy system |
| JP2019559284A JP7357545B2 (en) | 2017-12-15 | 2018-08-17 | Neutron capture therapy system |
| EP18887579.3A EP3685883B1 (en) | 2017-12-15 | 2018-08-17 | Neutron capture therapy system |
| RU2020114997A RU2739171C1 (en) | 2017-12-15 | 2018-08-17 | Neutron capture therapy system |
| PCT/CN2018/100963 WO2019114308A1 (en) | 2017-12-15 | 2018-08-17 | Neutron capture therapy system |
| US16/839,188 US11813483B2 (en) | 2017-12-15 | 2020-04-03 | Neutron capture therapy system |
| JP2023007754A JP2023041757A (en) | 2017-12-15 | 2023-01-23 | Neutron capture therapy system |
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| CN201711350436.3A CN109925610B (en) | 2017-12-15 | 2017-12-15 | Neutron capture therapy system |
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| CN113491841A (en) * | 2020-03-18 | 2021-10-12 | 中硼(厦门)医疗器械有限公司 | Neutron capture therapy system |
| CN117797417A (en) * | 2022-09-30 | 2024-04-02 | 中硼(厦门)医疗器械有限公司 | neutron capture therapy system |
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