Boron neutron capture therapy system and treatment plan generation method therefor

Abstract

To provide a boron neutron capture therapy system and a treatment plan generation method therefor.SOLUTION: A boron neutron capture therapy system 100 comprises a neutron beam irradiation device 10, a treatment planning module 20, and a control module 30. The neutron beam irradiation device is used to generate a therapeutic neutron beam N during irradiation therapy and irradiate the same to an irradiated body that has ingested a boron (10B)-containing drug so as to form an irradiated site. According to medical image data of the irradiated site and a parameter of the therapeutic neutron beam generated by the neutron beam irradiation device, the treatment planning module performs a dosage simulation calculation and generates a treatment plan, the medical image data of the irradiated site comprising tissue-related information and boron (10B) concentration-related information. The control module retrieves, from the treatment planning module, a treatment plan corresponding to the irradiated body, and controls the neutron beam irradiation device to perform irradiation therapy on the irradiated body according to the treatment plan.SELECTED DRAWING: Figure 3

Description

[Technical Field]

[0001] One aspect of the present invention relates to a radiation therapy system, and in particular to a boron neutron capture therapy system. Another aspect of the present invention relates to a treatment plan generation method, particularly for boron neutron capture therapy systems. This invention relates to a method for generating a treatment plan for a stem. [Background technology]

[0002] With the development of atomic science, radiation such as cobalt-60, linear accelerators, and electron beams Radiation therapy has already become one of the main methods of cancer treatment. However, conventional photon or electron Therapy is limited by the physical conditions of the radiation itself, killing tumor cells and The radiation damages many normal tissues. Also, the degree of sensitivity of tumor cells to radiation varies. Therefore, conventional radiotherapy can only treat highly radioresistant malignant tumors (e.g., glioblastoma multiforme). Glioblastoma multiforme, melanoma The treatment effect is not good.

[0003] Chemotherapy is used to reduce radiation damage to the normal tissue surrounding the tumor. The concept of targeted therapy in radiation therapy is being used in radiation therapy. Currently, the relative biological effectiveness (RBI) is high against tumor cells. Radiation sources with high radioactivity effectiveness (RBE) are being actively developed ( For example, proton therapy, heavy particle therapy, neutron capture therapy, etc.) Of these, neutron capture therapy is , which combines the above two concepts. For example, boron neutron capture therapy (BOC) Neutron Capture Therapy (BNCT), a boron-containing drug The particles specifically concentrate on tumor cells, and by combining this with highly precise beam control, it is possible to In comparison, it offers better cancer treatment options.

[0004] 3D models are widely used in the fields of scientific experiment analysis and simulation. For example, in the field of nuclear radiation and protection, it is used to estimate the absorbed dose in the human body under specific radiation conditions. Computer technology is constantly being used to simulate and assist physicians in formulating treatment plans. Various processing techniques are used to process medical image data, and the results are required for Monte Carlo software. We established the necessary accurate lattice model and performed simulations in combination with Monte Carlo software. In the field of neutron capture therapy, Monte Carlo simulations are performed based on medical image data. When establishing the grid model required for Carlo software and performing dose calculation and evaluation, In the model, basic biological information reflected by each grid, such as tissue type and boron concentration information, is defined. The accuracy and precision of the information determines the reliability of the dose calculation results. However, boron concentration information is usually based on blood sample testing or section testing. boron concentration data was obtained, and thus the corresponding tissue and tumor boron concentrations were estimated. This gives the regional boron concentration value in the corresponding model region, given The boron concentration information obtained will be used to determine the true distribution of boron-containing drugs in vivo and the time course of boron-containing drugs. This affects the reliability of the dose calculation results because it does not take into account the radiation status.

[0005] Therefore, there is a need to provide a boron neutron capture therapy system and a method for generating a treatment plan therefor. There is. Summary of the Invention

[0006] To overcome the deficiencies of the prior art, a boron neutron capture therapy system according to one aspect of the present invention is provided. The system includes a neutron beam irradiation device, a treatment planning module, and a control module. The beam irradiation device generates a therapeutic neutron beam during irradiation treatment and 10 B) Containing drugs The treatment planning module irradiates the object into which the substance has been taken to form an irradiation area. medical image data of the irradiation site and the therapeutic neutron beam generated by the neutron beam irradiation device; Based on the neutron beam parameters, dose simulation calculations are performed and treatment planning is carried out. and the medical image data of the irradiated area is used to generate tissue-related information and boron ( 10 B) Concentration relationship The control module receives from the treatment planning module information corresponding to the irradiated object. calling up the treatment plan and administering radiation treatment to the irradiated subject in accordance with the treatment plan; The neutron beam irradiation device is controlled to obtain boron concentration-related information from medical image data of the irradiated area. Based on this information, dose simulation is performed and treatment planning is carried out, and a model is established and The accuracy of dose calculations can be improved.

[0007] Further, the treatment planning module may determine a corresponding tissue type based on the tissue-related information. Establishing a 3D voxel prosthetic tissue model with boron concentration-related data Based on the information, the three-dimensional voxel-based prosthetic tissue model is Based on the boron concentration related information of the medical image data of the irradiated area, Providing boron concentration data would better match the actual situation.

[0008] Preferably, the tissue-related information is obtained by non-radionuclide medical imaging of the irradiated area. and the treatment planning module performs a correlation between the non-radionuclide medical image data and tissue types. Based on the transformation relationship, each voxel of the three-dimensional voxel prosthetic tissue model is Automatic or manual definition of tissue types. 3D voxel prosthetic tissue. The model is established based on the transformation relationship between medical image data and tissue types, so that the tissue The established geometric model provides more accurate information about the type (elemental composition) of the medical image data. Furthermore, the non-radioactive nuclide medical images are more reflective of the actual situation. , CT.

[0009] Preferably, the treatment planning module is adapted to generate the three-dimensional voxel prosthetic tissue model. Boron concentration data was given for different types of tissue in the same sample, and different concentrations were given for the same type of tissue. Provide boron concentration data according to the actual situation and calculate the dose stain. In particular, different boron concentrations in the same tissue type are used for the treatment planning. Providing concentration data can improve the accuracy of model establishment and dose calculation.

[0010] Preferably, the boron concentration related information is obtained by radionuclide medical images of the irradiated area. The subject is radiolabeled to perform the radionuclide medical imaging scan. The boron-containing drug or a non-boron-containing drug with tumor cell affinity similar to that of the boron-containing drug was used. and the treatment planning module performs a calculation between the radionuclide medical image data and the boron concentration. Based on the transformation relationship, each voxel unit of the three-dimensional voxel prosthetic tissue model The boron concentration of the radionuclide medical image is automatically or manually defined. The image is PET, and the radiolabeled boron-containing drug is18 It is F-BPA.

[0011] Preferably, the boron concentration related information includes the body weight of the subject. , the dose of the administered drug (Injection Dose), the time for measuring the drug activity (Measurement Time) re Time), contrast time (Scan Time), radionuclide half-life (Half T ime) and Image Pixel Intensity pixel ) the treatment planning module is configured to calculate the three-dimensional boron concentration based on the boron concentration-related information. The boron concentration in each voxel of the prosthetic tissue model is calculated, and the treatment plan is The module calculates each of the three-dimensional voxel prosthetic tissue models based on the calculation results. Further, the treatment planning module provides boron concentration data on a voxel-by-voxel basis. Each voxel of the three-dimensional voxel prosthetic tissue model is analyzed based on the element concentration-related information. The step of calculating the boron concentration at Image pixel intensity of blood image approximated using Equation 1 blood and calculating Using Equation 2, the boron concentration in each voxel of the 3D voxel prosthetic tissue model is calculated. and calculating the ratio of the concentration to the blood boron concentration.

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[0012] Furthermore, the treatment planning module may be implemented using a Monte Carlo simulation program. The boron dose per unit time (D B ), Fast neutron dose (D f ), superthermal neutron dose (D epi ), thermal neutron dose (D th ) and light Child dose (D γ ) was simulated and the 3D voxel prosthesis was modeled using Eq. Calculate the equivalent dose rate D of the tissue model. D(Gy-Eq)=CBE×B pixel (ppm) x D B (Gy / ppm)+RBE f ×D f (Gy)+RBE epi ×D epi (Gy)+RBE th ×D th (Gy)+R BE γ ×D γ (Gy) (Equation 3) where CBE is the compound biological effect of a unit concentration of a boron-containing drug, and RBE f is the relative biological effectiveness of fast neutrons, RBE epi The relative biomass of superthermal neutrons RBE th is the relative biological effectiveness of thermal neutrons, RBE γ is light (The relative biological effectiveness of the

[0013] Preferably, the treatment planning module is a neutron beam irradiation device. The therapeutic neutron beam parameters, the tissue type data, and the boron concentration data are collected. Based on the three-dimensional voxel prosthetic tissue model, a Monte Carlo simulation was performed. When the irradiation treatment of the therapeutic neutron beam is performed on the irradiation area according to the application program, The physical dose rate distribution is simulated.

[0014] Furthermore, the treatment planning module samples and simulates different irradiation angles. and at least one irradiation angle is suitably selected based on the equivalent dose rate distribution calculated by the simulation. Select the degree.

[0015] A method for generating a treatment plan for a boron neutron capture therapy system according to another aspect of the present invention includes: Based on the tissue-related information of the medical image data of the region, a third-order image having corresponding tissue type data is obtained. Establishing a voxel-based prosthetic tissue model and medical image data of the irradiated area Ta's way ( 10 B) Based on the element concentration related information, the three-dimensional voxel prosthetic tissue Boron ( 10 B) Steps for providing concentration data and Monte Carlo Define beam parameters in the simulation program to support different irradiation angles. A step of performing a dose simulation calculation by sampling, and and a step of generating a treatment plan by suitably selecting an irradiation angle for each of the beams. Based on the boron concentration related information of the medical image data of the irradiated area, boron concentration data is calculated. By providing the dose, performing dose simulations, and formulating treatment plans, it is possible to more accurately match the actual situation. The accuracy of model establishment and dose calculation can be improved.

[0016] Preferably, the three-dimensional image is obtained based on boron concentration related information of medical image data of the irradiated area. The step that gives the boron concentration data for each voxel of the voxel prosthetic tissue model The rFPC decodes the boron concentration-related information from the medical image data of the irradiated area and calculates the weight ( Body Weight, Injection Dose, Drug Activity measurement time (Measure Time), imaging time (Scan Time), radioactivity Nuclide half-life (Half Time) and image pixel intensity (Image Pixel Int ensity pixel ) and obtaining the three-dimensional voxel prosthesis assembly. A step of calculating the boron concentration in each voxel of the tissue model, and The boron concentration data for each voxel of the 3D voxel prosthesis tissue model is given. and a step of: Calculating the cell-by-cell boron concentration comprises: Image pixel intensity of blood image approximated using Equation 1 blood and calculating Using Equation 2, the boron concentration in each voxel of the 3D voxel prosthetic tissue model is calculated. Concentration B pixel Blood boron concentration B blood calculating a ratio to nothing.

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[0017] Furthermore, we defined the beam parameters in the Monte Carlo simulation program. A step of performing dose simulation calculation by sampling different irradiation angles. The sampled irradiation angles are used to measure the 3D voxel prosthetic tissue model. The boron dose (D) received by each voxel unit per unit time in the defined beam irradiation is B ) , fast neutron dose (D f ), superthermal neutron dose (D epi ), thermal neutron dose (D th ) and Photon dose (D γ simulating the physical dose, including: A defined beam illumination for each voxel of the three-dimensional voxel prosthetic tissue model. and calculating the equivalent dose rate D per unit time at the irradiation. D(Gy-Eq)=CBE×B pixel (ppm) x D B (Gy / ppm)+RBE f ×D f (Gy)+RBE epi ×D epi (Gy)+RBE th ×D th (Gy)+R BE γ ×D γ (Gy) (Equation 3) where CBE is the compound biological effect of a unit concentration of a boron-containing drug, and RBE f is the relative biological effectiveness of fast neutrons, RBE epi The relative biomass of superthermal neutrons RBE th is the relative biological effectiveness of thermal neutrons, RBE γ is light (The relative biological effectiveness of the

[0018] A boron neutron capture therapy system according to a further aspect of the present invention includes a neutron beam irradiation device; The neutron beam irradiation device includes a treatment planning module and a control module. Generate a therapeutic neutron beam and 10 B) Irradiating the subject who has taken the drug containing The treatment planning module forms an irradiation area based on medical image data of the irradiation area. Based on this, tissue types are defined, and a 3D voxel prosthetic tissue having tissue type data is generated. and the treatment planning module establishes a three-dimensional voxel prosthetic tissue model. Boron concentration data was given for different types of tissues in the model, and for the same type of tissue. and the treatment planning module calculates the 3D voxel plots of the boron concentration data. The osseous tissue model, the boron concentration data, and the data generated by the neutron beam irradiation device Based on the generated parameters of the therapeutic neutron beam, a dose simulation calculation is performed. A control module performs a treatment plan and generates a treatment plan. Calling up the treatment plan corresponding to the irradiated object, and irradiating the irradiated object according to the treatment plan. The neutron beam irradiation device is controlled to perform irradiation treatment. The boron concentration is adjusted according to the actual situation. The dose simulation is performed by providing the dose data, and the treatment plan is formulated. Providing different boron concentration data for different tissues improves the accuracy of model establishment and dose calculation. It can be raised. [Effects of the Invention]

[0019] The boron neutron capture therapy system and the treatment plan generation method thereof of the present invention are The accuracy of dose calculations can be improved. [Brief explanation of the drawings]

[0020] [Figure 1] FIG. 1 is a schematic diagram of a boron neutron capture reaction. [Figure 2] This is the nuclear reaction equation for neutron capture in 10B(n,α)7Li. [Figure 3] 1 is a block diagram of a neutron capture therapy system according to an embodiment of the present invention. [Figure 4] 1 is a flow diagram of a method by which a treatment planning module generates a treatment plan, according to an embodiment of the present invention. [Figure 5] 1 is a flow diagram of a method for establishing a three-dimensional voxel prosthetic tissue model according to an embodiment of the present invention. [Figure 6] 1 is a flow diagram of a method for providing boron concentration data for each voxel of a three-dimensional voxel prosthetic tissue model according to an embodiment of the present invention. [Figure 7] 1 is a flow diagram of a method for dose simulation calculations according to an embodiment of the present invention. DETAILED DESCRIPTION OF THE INVENTION

[0021] 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.

[0022] Preferably, a neutron capture therapy system and a treatment plan generation method therefor are embodiments of the present invention. Neutron capture therapy, particularly boron neutron capture therapy, will be briefly explained below.

[0023] Neutron capture therapy has been increasingly applied in recent years as an effective cancer treatment. Of these, boron neutron capture therapy has become the most common. The neutrons used in the experiment can be provided by a nuclear reactor or an accelerator. Take boron neutron capture therapy as an example. The basic module of accelerator boron neutron capture therapy is usually: Accelerators, targets, etc. used to accelerate charged particles (protons, deuterium nuclei, etc.) The beam shaping assembly includes a heat removal system and a beam shaping assembly. Neutrons are generated by the action of the neutrons, and the required neutron yield and energy, the available accelerated charged particles The appropriate atom is selected depending on the energy and current of the electrons, and the physical and chemical properties of the metal target. A nuclear reaction is selected. The most commonly studied nuclear reactions are: 7 Li(p,n) 7 Be and 9 Be(p,n) 9 B, and both of these reactions are endothermic. The reactions have energy thresholds of 1.881 MeV and 2.055 MeV, respectively. The ideal neutron source for neutron capture therapy is hyperthermal neutrons at the keV energy level. Theoretically, the impact of protons with energies slightly above the threshold on a metallic lithium target The impact produces neutrons with relatively low energy, which can be used clinically without requiring much moderation. However, the application of lithium metal (Li) and beryllium metal (Be) The two types of targets do not have a large cross section for interacting with protons of threshold energy, so To generate neutron flux, nuclear reactions are generally carried out using protons with relatively high energy. be caused.

[0024] Boron Neutron Capture Therapy y, BNCT) is a boron ( 10 B) The drug has a large capture cross section for thermal neutrons. Utilizing these characteristics, 10 B(n,α) 7 Li neutron capture and fission reactions 4 He and 7 L Figures 1 and 2 show the reaction of boron neutron capture, respectively. Schematic diagram and 10 B(n,α) 7 The nuclear reaction formula for Li neutron capture is shown below. The two types of charged particles are: The average energy is about 2.33 MeV, and the linear energy transfer is high. It has the characteristics of short range and linear energy transfer (LET). The energy input and range are 150 keV / μm and 8 μm, respectively. 7 Li heavy charged particles In the case of the ion beam, the total range of the two particles is 175 keV / μm and 5 μm, respectively. Since the radiation dose is close to the normal level, radiation damage to the living body can be suppressed to the cellular level. By concentrating the neutrons in tumor cells and combining them with an appropriate neutron source, it is possible to avoid causing significant damage to normal tissue. This achieves the goal of partially killing tumor cells.

[0025] The Monte Carlo method is used to calculate the collision trajectories and energy distribution of nuclear particles in three-dimensional space within the radiation target. It can accurately simulate the radiation exposure under specific radiation conditions in neutron capture therapy. To simulate the absorbed dose in the human body at 1000 Hz to help doctors develop treatment plans In addition, various processing steps are always performed on medical images using computer technology, and Monte Carlo simulations are performed. Establish accurate lattice models required for Monte Carlo software and combine them with Monte Carlo software. It is necessary to perform simulation calculations in conjunction with the above. Medical image data is a nuclear magnetic resonance image. Magnetic Resonance Imaging (MRI), computer Computed Tomography (CT), Positron Emission Computing Positron Emission Tomography (PET) , PET-CT or X-Ray imaging. As known to those skilled in the art, other medical image data may be used, and the medical image data may be 3D voxel prosthetic tissue model, the radiation therapy disclosed in the present invention The present invention can be applied to a system and a method for generating a treatment plan.

[0026] Referring to FIG. 3, the radiation therapy system of this embodiment preferably includes a boron neutron capture system. The therapy system 100 includes a neutron beam irradiation device 10, a treatment planning module 20, and a control The neutron beam irradiation device 10 includes a neutron generator 11 and a treatment table. The neutron generator 11 generates a therapeutic neutron beam N during irradiation treatment. Boron on table 12 ( 10 B) Irradiate the patient who has taken the drug to form an irradiated area. Before treatment, the treatment planning module 20 calculates the medical image data of the patient's area to be irradiated and the neutron emission A treatment plan is created based on the parameters of the therapeutic neutron beam N generated by the device 11. During radiation treatment, the control module 30 generates the current patient and based on the treatment plan, Control the exposure.

[0027] In one embodiment, the patient receives radiolabeled boron ( 10 B) Contains Taking drugs and radionuclide medical imaging (e.g., PET) 10 B) Concentration relationship It is necessary to obtain related information, i.e., medical image data of the irradiated area of the patient contains tissue-related information. The tissue-related information includes information related to the radionuclide concentration and information related to the boron concentration, and the tissue-related information is obtained from radionuclide medical images. It may also be obtained from other non-radionuclide medical images (e.g., CT). Thus, radionuclide medical imaging may be PET-CT or the like, and non-radionuclide medical imaging may be The image may be an MRI or the like, and the present invention is not specifically limited thereto. The imaging module 20 determines the corresponding tissue-related information of the medical image data of the irradiated area based on the tissue-related information of the medical image data. A 3D voxel prosthetic tissue model with tissue type and tissue density data was established. Based on the boron concentration-related information of the medical image data of the irradiated area, a 3D voxel projection was performed. Boron concentration data for each voxel of the osteotic tissue model was given, and the neutron generator 1 Parameters of the therapeutic neutron beam N generated by 1, as well as tissue type data and tissue density Based on a 3D voxel prosthetic tissue model with data and boron concentration data , the dose distribution when a patient receives radiation treatment using a Monte Carlo simulation program The tissue density is calculated by simulating the fabric and generating a treatment plan. It is not necessary to define the boron concentration based on the boron concentration related information of the medical image data of the irradiated area. By providing iodine concentration data, performing dose simulations, and formulating treatment plans, more realistic results can be achieved. This can meet the situation and improve the accuracy of model establishment and dose calculation.

[0028] Referring to FIG. 4, the method by which the treatment planning module 20 of this embodiment generates a treatment plan is as follows: specifically, Based on the tissue-related information of the medical image data of the irradiated area, corresponding tissue type data and Step S of establishing a 3D voxel prosthetic tissue model with tissue density data 410 and Based on the boron concentration-related information of the medical image data of the irradiated area, a 3D voxel process Step S420 of providing boron concentration data for each voxel of the thesis structure model; Monte Carlo simulation programs (e.g., MCNP, Monte Carlo o In the N Particle Transport Code, beam parameters The dose simulation calculation is performed by sampling different irradiation angles. Step S430: Step S440: Selecting the irradiation angle appropriately based on the calculation result and generating a treatment plan. and,

[0029] Referring to FIG. 5, in one embodiment, a 3D voxel processor is generated based on medical image data. The step S410 of establishing a status organization model includes: A step S510 of reading medical image data; a step S520 of establishing a three-dimensional medical image voxel model; A step S530 of defining or reading the boundaries of the region of interest; Based on the transformation relationship between CT image data, tissue type, and tissue density, Tissue type (elemental composition) and tissue density can be automatically defined or manually defined by the user For example, a specific tissue type and tissue density is assigned to each voxel within the boundary of each region of interest. Step S540; and a step S550 of establishing a three-dimensional voxel prosthetic tissue model. That's fine too.

[0030] The 3D voxel prosthetic tissue model is based on medical image data, tissue type, tissue density, and Since it is established based on the conversion relationship between the tissue type (element composition) and tissue density, The established geometric model accurately represents the actual situation reflected by the medical imaging data. Based on medical image data, 3D voxel prosthetic tissue is created. The detailed process for establishing the model was disclosed on March 8, 2017, and the publication number is CN 106474634A, the invention title of which is "Method for establishing a geometric model based on medical image data" No. 6,299,399, the entire contents of which are incorporated herein by reference.

[0031] Based on the boron concentration-related information of the medical image data of the irradiated area, a 3D voxel process In step S420, boron concentration data for each voxel of the thesis structure model is provided. The geometric model labeled with tissue boron concentration information allows us to estimate the boron-containing drug concentration in each tissue. The concentration of ions can be clearly understood, and when neutron irradiation simulation is performed, , which more realistically reflects the actual situation. The boron concentration-related information is The subject is exposed to a radionuclide for radionuclide medical imaging. The patient receives a labeled boron-containing drug, and the treatment planning module uses radionuclide medical imaging data. and boron concentration in a 3D voxel prosthetic tissue model. The boron concentration for each voxel is defined automatically or manually. Radionuclide medical imaging is PET, which uses radioactively labeled holograms taken up by the subject. Usine-containing drugs include: 18 F-BPA. 18 F-BPA also has other may be replaced with a radiolabeled boron-containing drug or other boron-containing drug, Non-boron-containing drugs that mimic the tumor cell affinity of radiolabeled boron-containing drugs, e.g., 18 Currently, boron-containing compounds such as BPA for boron neutron capture therapy are used. Boron-containing drugs are generally expensive, and non-boron-containing drugs are used instead of boron-containing drugs to improve treatment planning. By performing simulation, costs can be significantly reduced.

[0032] Referring to FIG. 6, in one embodiment, step S420 includes steps S610 to S620. The device may further include a step S630.

[0033] In S610, boron concentration related information of the medical image data of the irradiated area, i.e., radionuclide Medical image data information IOD (Inf) related to boron concentration obtained by medical image scanning Decipher the Ormation Object Definition.

[0034] Medical image data is usually stored in DICOM (Digital Imaging and Communication Communications in Medicine) format, The IOD related to boron concentration in the M data is calculated based on the body weight of the irradiated subject. ht), the dose of the administered drug (Injection Dose), the time for measuring drug activity (Me Imaging Time, Scan Time, Radionuclide Half-Life f Time), and understandably, the type of drug (Radiopharmaceutical tical), etc., which may be used to initiate radionuclide medical imaging scans. The information source may be determined at the start of the process, or may be manually entered by an operator. It may be automatically acquired or called up. For example, Table 1 shows DIC Data tags for boron concentration-related information in OM data and corresponding data names ( Description) are listed. [Table 1]

[0035] The IOD related to boron concentration in DICOM data is the image grid intensity (Image It may further include Pixel Intensity, and is useful for radionuclide medical imaging scans, e.g. In PET, when positrons generated by the decay of radioactive nuclides collide with electrons in tissue, An electron-positron annihilation reaction occurs, and at this time, a detector such as a photomultiplier tube (PMT) detects the The emitted gamma radiation is detected, and then the computer calculates the positron-emitting isotope distribution. In one embodiment, a cross-sectional image is formed that reflects the 18 F-BPA-PET scan ,The raw data of each grid in the image is 18 emitted by the annihilation of a proton and an electron emitted in F decay The count rate of generated photons is calculated as the image pixel intensity of each grid in the PET image. intensity pixel and output as medical image data, 18 F Because BPA is labeled, the raw data on the PET image is 10 BThe basis for quantification As can be seen, the tumor cell affinity of radiolabeled, boron-containing drugs is closely related to When radionuclide medical imaging is performed using non-boron-containing drugs, the raw data on the image Ta also 10 BIt can be used as a basis for quantification.

[0036] In S620, a 3D voxel prosthesis is created based on the decoded boron concentration-related information. The boron concentration is calculated for each voxel of the tissue model.

[0037] Standard Uptake Value (SUV) is the standard uptake value for radionuclides. It is a semi-quantitative index collected from medical images and measures the amount of contrast agent (radiolabeled or otherwise) taken up by local tissues. This refers to the ratio of the radioactivity of the drug (injected) to the whole-body average radioactivity, as shown in Equation 1. The IOD associated with the boron concentration obtained at 0 allows us to obtain the SUV of the corresponding lattice. Each grid of the radionuclide medical image scan is then converted into a 3D voxel prosthetic tissue model. There is a one-to-one correspondence with each voxel unit in the

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[0038] The SUV value of blood was set to 1, i.e., the radioactivity of blood was considered to be approximately equal to the whole-body average radioactivity. Formula 2 to SUV blood=1 The raw data of radionuclide medical images at the time, i.e., Approximated blood image grid intensity Image Pixel Intensity blood Take You will benefit.

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[0039] At the same time, the ratio of each grid to the standard intake value of blood was used to obtain the ratio of each grid to the blood boron concentration. , that is, the method for calculating the density of each voxel of the 3D voxel prosthetic tissue model using Equation 3. The ratio of the boron concentration to the blood boron concentration is calculated.

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[0040] Each voxel of the 3D voxel prosthetic tissue model is measured using the blood boron concentration as the reference value. Boron concentration in units of SUV pixel / SUV blood Converting it to each voxel unit Obtain the ratio of boron concentration in the blood to boron concentration in the blood and establish the heterogeneous boron concentration distribution. If the blood boron concentration value is obtained by blood sampling or other tests, the specific The actual boron concentration value can be obtained.

[0041] In S630, boron concentration data for each voxel is given based on the calculation results, and the calculation is performed. It may be given automatically based on the results, or may be given manually by the user, e.g., Based on the results, specific boron concentration data is provided for each voxel within the boundary of each region of interest.

[0042] The calculation results are more consistent with the actual situation, and the treatment planning module is a 3D voxel processor. Boron concentration data was given for different types of tissue in the Stasis tissue model, and the same type For each tissue, different boron concentration data can be provided, and the model can be established and the dose calculated. 3D voxel analysis with tissue type and tissue boron concentration can improve the accuracy of the analysis. After establishing the prosthesis tissue model, a Monte Carlo simulation program was used. In BNCT, the collision of nuclear particles in the internal three-dimensional space when the patient is irradiated with a neutron beam is The impact trajectory and energy distribution can be simulated, i.e., the physical dose rate distribution can be simulated and the equivalent dose rate distribution calculated based on the physical dose rate distribution. Furthermore, the proposed treatment plan is selected based on the dose index. Step S430 includes the following steps S710 to S720.

[0043] In S710, the beam parameters ( Define the beam energy, intensity, radius, etc. and sample different irradiation angles. By imaging, the physical properties of the 3D voxel prosthetic tissue model can be visualized at different irradiation angles. The dose rate distribution is simulated in three dimensions, i.e., at each sampling irradiation angle. Each voxel unit of the voxel prosthesis tissue model is irradiated with a defined beam in a unit time. Simulate the physical dose received per person.

[0044] When sampling, the starting position and beam angle of the calculated beam must be determined. The determination of the starting position and angle in the calculation is performed using either a forward or a backward algorithm. In the forward algorithm, the starting position is determined as an extracorporeal position and a fixed angle is It can be calculated by sampling sequentially by degree or distance interval, and also by random sampling. The beam angle can be measured from the irradiation point to the tumor center of gravity. Or it can be set as a vector direction to the deepest position of the tumor, The position of the end point can be adjusted according to the user's needs, and the backward algorithm In this case, a starting position is determined within the tumor area, and the starting position can be the tumor center, the deepest position, or the tumor area. The beam angle may be randomly sampled or may be random points within the tumor area. may be determined by sampling at specified intervals.

[0045] When sampling, the beam angle is selected, for example, the beam angle is evaluated, and the evaluation result is The beam angle used in subsequent calculations may be selected based on the After the calculation, the beam angle is selected, e.g., the radiation dose distribution result or the beam angle The beam angle evaluation method will not be described in detail in this specification. Without further details, it was disclosed on June 16, 2017, and its publication number is CN106853272A. , the patent application entitled "Method for Evaluating Beam Irradiation Angle" can be referred to. The entire contents of which are incorporated herein.

[0046] In boron neutron capture therapy, the main factor contributing to the dose has three parts: do.

[0047] 1) Boron dose D B Dose is the amount of boron-containing drugs in tissues and tumors that are irradiated with neutrons. 10 B(n, α) 7 High linear energy transfer α produced by generating a Li neutron capture reaction, 7 It comes from Li particles.

[0048] 2) Neutron dose: Fast neutron dose D depending on neutron energy f , superthermal neutron dose D e pi and thermal neutron dose D th The constituent elements of tissues and organs are mainly 1 H(n,n') The dose resulting from recoil protons generated by elastic scattering of p neutrons with hydrogen, 14 N(n, p) 14 Doses from protons and recoil carbon ions produced by the C action, and neutrons and other It is a micro dose that interacts with the elements.

[0049] 3) Photon dose D γ : Neutrons interact with the shielding structure, causing a capture reaction with human tissue. The latter includes photons induced by 1 H(n,γ) 2 H reaction occurs The photon is 2.22 MeV, generated by the electron beam.

[0050] In one embodiment, in step S710, the physical dose received per unit time is calculated using Monte Carlo method. per unit time obtained by simulation using the Carlo simulation program Boron dose (D B ), fast neutron dose (D f ), superthermal neutron dose (D epi ), thermoneutral Child dose (D th ) and photon dose (D γ ) is included.

[0051] In S720, equivalent lines at different irradiation angles of a 3D voxel prosthetic tissue model are Calculate the dose rate distribution.

[0052] In boron neutron capture therapy, the biological effects of photons and neutrons are different, so The relative viability of different tissues for neutron, hyperthermal, thermal and photon doses is Relative biological effectiveness The equivalent dose is calculated by multiplying the RBE by For boron dose, α,7 The range of Li particles is short, and the damage is usually caused by boron neutron capture. The site of action is limited, and different cell types absorb boron-containing drugs. Because of the difference in ability, the distribution of boron concentration in the body is uneven, and in order to calculate the equivalent dose, The compound biological effect of each tissue was calculated based on this dose. effectiveness, CBE) and the corresponding boron concentration (defined in step S630) (defined as the dose rate per voxel), i.e., the voxel-wise equivalent dose rate D is calculated using Equation 4. Calculate, D(Gy-Eq)=CBE×B pixel (ppm) x D B (Gy / ppm)+RBE f ×D f (Gy)+RBE epi ×D epi (Gy)+RBE th ×D th (Gy)+R BE γ ×D γ (Gy) (Equation 4) where CBE is the compound biological effect of a unit concentration of a boron-containing drug, and RBE f teeth , the relative biological effectiveness of fast neutrons, RBE epi The relative biology of hyperthermal neutrons RBE th is the relative biological effectiveness of thermal neutrons, RBE γ is a photon The relative biological effectiveness of

[0053] In step S440, a mathematical calculation is performed based on the equivalent dose rate distribution calculated in S720. Combined with a comprehensive algorithm, different treatment plan proposals (irradiation angles and corresponding irradiation times) are proposed. Evaluate or select a suitable region of interest, for example, select one of the regions of interest as a target. Then, sampling is performed using the maximum dose, average dose, or prescription dose of the region of interest as a constraint. The irradiation time corresponding to the sampled irradiation angle is calculated, and the sampled irradiation angle is calculated at the irradiation time. The equivalent dose distribution in the 3D voxel prosthetic tissue model is then calculated using the dose field. Different irradiation angles and corresponding doses are calculated using dose histograms (DVH), isodose curves, and dose tables. The irradiation time was simulated using a 3D voxel prosthetic tissue model. The equivalent dose distribution is evaluated or suitably selected, and the irradiation angle evaluation described above is further performed. This allows doctors and other operators to select treatment plan proposals that better meet their needs. As can be seen, the optimization algorithm can be used to select at least two beam angles. The specific number of irradiation angles may be manually set; It may be acquired automatically by an algorithm or by using intensity-modulated rotational irradiation. , the sampling of illumination angles may be performed on the same or opposite side of the patient.

[0054] As can be seen, the above equations 1-4 and some simple examples of dose calculation, evaluation and preferred selection are given below. The transformation still falls within the scope of the present invention.

[0055] As can be seen, the present invention is directed to the treatment of boron neutron capture disorders such as Alzheimer's disease, rheumatoid arthritis, etc. It can also be applied to other diseases treatable by capture therapy, in which case tumor cells are transferred to other disease tissues. The tissue may be a tissue, and the patient may be any other subject.

[0056] The above describes exemplary specific embodiments of the present invention, and it is understood by those skilled in the art that the present invention can be understood by those skilled in the art. While it is readily apparent that the present invention is not limited in scope to specific embodiments, it will be readily apparent to those skilled in the art that various modifications and variations may be made thereto. It is to be understood that various modifications will be apparent to those skilled in the art without departing from the spirit and spirit of the invention as defined and determined by the appended claims. If within the scope of the present invention, these variations are obvious and therefore fall within the scope of the claims of the present invention. is located.

Claims

1. During irradiation treatment, a therapeutic neutron beam is generated and irradiated onto the subject who has taken a boron-containing drug. a neutron beam irradiation device that irradiates a target object with a neutron beam to form an irradiated portion; medical image data of the irradiated area and a previous image generated by the neutron beam irradiation device; performing a dose simulation calculation based on the parameters of the therapeutic neutron beam; and A treatment plan is generated, and the medical image data of the irradiated area is used to obtain tissue-related information and boron concentration-related information. a treatment planning module containing the information; Retrieving the treatment plan corresponding to the irradiated object from the treatment planning module; The neutron beam irradiation device is controlled so as to perform irradiation treatment on the subject according to the treatment plan. and a control module for controlling the boron neutron capture therapy system.

2. The treatment planning module generates corresponding tissue type data based on the tissue-related information. A three-dimensional voxel prosthesis tissue model is established, and based on the boron concentration-related information, Based on this, the boron concentration data for each voxel of the three-dimensional voxel prosthesis tissue model was calculated.

2. The boron neutron capture therapy system of claim 1, wherein the boron neutron capture therapy system provides data.

3. The tissue-related information is obtained by non-radionuclide medical imaging of the irradiated area, and The treatment planning module calculates a transformation relationship between the non-radionuclide medical image data and tissue types. Based on this, the tissue type of each voxel of the three-dimensional voxel prosthetic tissue model is determined.

3. The boron-neutral method according to claim 2, characterized in that it is automatically or manually defined. Child capture therapy system.

4. The treatment planning module may include: For tissues of the same type, boron concentration data is given, and for the same type of tissue, different boron concentrations are given.

3. The boron neutron capture therapy system of claim 2, wherein the boron neutron capture therapy system provides a measurement of the boron neutron capture rate.

5. The boron concentration-related information is obtained by radionuclide medical imaging of the irradiated area, The subject is exposed to a radioactively labeled boron-containing radioisotope for radionuclide medical imaging. A boron-containing drug or a non-boron-containing drug having tumor cell affinity similar to that of the boron-containing drug is taken, and The treatment planning module calculates a conversion relationship between the radionuclide medical image data and the boron concentration. Based on this, the boron concentration of each voxel of the three-dimensional voxel prosthetic tissue model is calculated.

3. The method of claim 2, wherein the degree is automatically or manually defined. Neutron capture therapy system.

6. The radionuclide medical imaging is PET, and the radiolabeled boron-containing drug is １８ 6. The boron neutron capture therapy system according to claim 5, wherein the boron neutron capture therapy system is F-BPA. Hmm.

7. The boron concentration-related information includes the body weight of the irradiated subject, the amount of administered drug, and the like. Injection Dose, Drug Activity Measurement Time e), imaging time (Scan Time), radionuclide half-life (Half Time), and Image Pixel Intensity ｐｉｘｅｌ ), The treatment planning module calculates the three-dimensional voxel Calculate the boron concentration in each voxel of the prosthetic tissue model; The treatment planning module generates the three-dimensional voxel prosthesis based on the calculation results.

3. The method according to claim 2, wherein boron concentration data is provided for each voxel of the tissue model. A boron neutron capture therapy system as described.

8. The treatment planning module calculates the three-dimensional voxel process based on the boron concentration-related information. The step of calculating the boron concentration for each voxel of the stasis tissue model includes: Image Pixel Intensity (Image Pixel Intensity) ｂｌｏｏｄ and calculating Using Equation 2, the boron concentration for each voxel of the three-dimensional voxel prosthetic tissue model is calculated. and calculating the ratio of the concentration of boron in the blood to the concentration of boron in the blood. Item 8. A boron neutron capture therapy system according to Item 7. [Equation 1] (Formula 1) (In the formula, SUV ｂｌｏｏｄ is the standard intake value of blood, and Calibration F (actor is the calibration value of the medical imaging scanning device) [Equation 2] (In the formula, B ｐｉｘｅｌ is a function of each voxel of the three-dimensional voxel prosthetic tissue model. is the boron concentration in units of B ｂｌｏｏｄ is the blood boron concentration, SUV ｐｉｘｅｌ teeth , which is the standard uptake value for each voxel of the three-dimensional voxel prosthetic tissue model.

9. The treatment planning module performs the third-order simulation using a Monte Carlo simulation program. Boron dose per unit time (D) of the original voxel prosthetic tissue model Ｂ ), fast neutral Child dose (D ｆ ), superthermal neutron dose (D ｅｐｉ ), thermal neutron dose (D ｔｈ ) and photon dose ( D γ ) was simulated and the 3D voxel prosthetic tissue model was calculated using Eq.

9. The boron neutron capture therapy method according to claim 8, wherein the equivalent dose rate D of the boron neutron capture therapy is calculated. system. D(Gy-Eq)=CBE×B ｐｉｘｅｌ (ppm)×D Ｂ (Gy / ppm)+RBE ｆ ×D ｆ (Gy)+RBE ｅｐｉ ×D ｅｐｉ (Gy)+RBE ｔｈ ×D ｔｈ (Gy)+R B.E. γ ×D γ (Gy) (Equation 3) where CBE is the compound biological effect of a unit concentration of a boron-containing drug, and RBE is the compound biological effect of a unit concentration of a boron-containing drug. ｆ is the relative biological effectiveness of fast neutrons, RBE ｅｐｉ The relative biomass of superthermal neutrons The clinical effect is RBE ｔｈ is the relative biological effectiveness of thermal neutrons, RBE γ is light (The relative biological effectiveness of the

10. The treatment planning module is configured to: the third order neutron beam parameters, the tissue type data, and the boron concentration data; Based on the original voxel prosthetic tissue model, a Monte Carlo simulation program The physical dose when the therapeutic neutron beam is irradiated to the irradiated area by the ram.

3. The method of claim 2, wherein the rate distribution is simulated. Legal system.

11. The treatment planning module samples different irradiation angles and performs simulation calculations. and selecting at least one irradiation angle based on the equivalent dose rate distribution obtained by the method.

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

12. Based on the tissue-related information of the medical image data of the irradiated area, the corresponding tissue type data is obtained. establishing a three-dimensional voxel prosthetic tissue model; The three-dimensional voxel projection is generated based on boron concentration-related information of the medical image data of the irradiated area. providing boron concentration data for each voxel of the loss tissue model; Define the beam parameters in the Monte Carlo simulation program and performing a dose simulation calculation by sampling the irradiation angle; and generating a treatment plan by suitably selecting an irradiation angle based on the calculation result. A treatment plan generation method for a boron neutron capture therapy system, comprising:

13. The three-dimensional voxel process is performed based on boron concentration-related information of the medical image data of the irradiated area. The step of providing boron concentration data for each voxel of the stasis tissue model includes: The boron concentration-related information of the medical image data of the irradiated area is decoded to determine the body weight (Bo dy Weight), Injection Dose, Drug Activity Measurement time, scan time, radionuclide Half Time and Image Pixel Intensity city ｐｉｘｅｌ ) and The boron concentration in each voxel of the three-dimensional voxel prosthetic tissue model is calculated. and Based on the calculation results, each voxel unit of the three-dimensional voxel prosthetic tissue model and providing boron concentration data of Treatment plan generation methods.

14. The boron concentration of each voxel of the three-dimensional voxel prosthetic tissue model is calculated. The steps are: Image Pixel Intensity (Image Pixel Intensity) ｂｌｏｏｄ and calculating Using Equation 2, the boron concentration for each voxel of the three-dimensional voxel prosthetic tissue model is calculated. Concentration B ｐｉｘｅｌ Blood boron concentration B ｂｌｏｏｄ calculating a ratio to 14. The method of claim 13, further comprising: [Equation 3] (Formula 1) (In the formula, SUV ｂｌｏｏｄ is the standard intake value of blood, and Calibration F (actor is the calibration value of the medical imaging scanning device) [Equation 4] (In the formula, SUV ｐｉｘｅｌ is a function of each voxel of the three-dimensional voxel prosthetic tissue model. (This is the standard intake value per cell.)

15. Define the beam parameters in the Monte Carlo simulation program and The step of performing a dose simulation calculation by sampling the irradiation angle includes: At the sampled irradiation angles, each voxel of the three-dimensional voxel prosthetic tissue model is The boron dose (D) received per unit time in a beam irradiation where the x-unit is defined Ｂ ), high Neutral speed (D ｆ ), epithermal neutral radiation (D ｅｐｉ ), thermal neutral radiation (D ｔｈ ) and びPhoton Dose (D γ simulating a physical dose, including: For each voxel of the three-dimensional voxel prosthetic tissue model, the definition of and calculating an equivalent dose rate D per unit time at the determined beam irradiation. The method for generating a treatment plan according to claim 14, D(Gy-Eq)=CBE×B ｐｉｘｅｌ (ppm)×D Ｂ (Gy / ppm)+RBE ｆ ×D ｆ (Gy)+RBE ｅｐｉ ×D ｅｐｉ (Gy)+RBE ｔｈ ×D ｔｈ (Gy)+R B.E. γ ×D γ (Gy) (Equation 3) where CBE is the compound biological effect of a unit concentration of a boron-containing drug, and RBE is the compound biological effect of a unit concentration of a boron-containing drug. ｆ is the relative biological effectiveness of fast neutrons, RBE ｅｐｉ The relative biomass of superthermal neutrons The clinical effect is RBE ｔｈ is the relative biological effectiveness of thermal neutrons, RBE γ is light (The relative biological effectiveness of the

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