CN-122024938-A - Construction method, dose evaluation method and system of material section library

CN122024938ACN 122024938 ACN122024938 ACN 122024938ACN-122024938-A

Abstract

The application relates to a construction method, a dose evaluation method and a system of a material section library. The method comprises the steps of setting material energy nodes, obtaining material information, wherein the material information at least comprises component nuclides and nuclide particle number density, and constructing a material section library according to the material energy nodes and the material information. By adopting the method, the calculation efficiency of the section value of the material where the particles are positioned can be improved.

Inventors

Zhong Wanbing
CHEN JIANG

Assignees

中硼(厦门)医疗器械有限公司

Dates

Publication Date: 20260512
Application Date: 20251104
Priority Date: 20241111

Claims (15)

1. A method of constructing a library of material sections, the method comprising: Setting a material energy node; acquiring material information, wherein the material information at least comprises a composition nuclide and a nuclide particle number density; And constructing a material section library according to the material energy nodes and the material information.
2. The method of claim 1, wherein the setting material energy nodes comprises: determining the minimum nuclide energy node value and the maximum nuclide energy node value in nuclide energy nodes of all the component nuclides based on the nuclide cross section library of the component nuclides, determining the minimum nuclide energy node value as the minimum material energy node, and determining the maximum nuclide energy node value as the maximum material energy node; and setting the material energy node according to the minimum material energy node and the maximum material energy node.
3. The method of building of claim 2, wherein said setting said material energy nodes based on said minimum material energy node and said maximum material energy node comprises: And uniformly logarithmically interpolating a preset number of energy intervals between the minimum material energy node and the maximum material energy node to obtain the material energy node.
4. The method of building of claim 2, wherein said setting said material energy nodes based on said minimum material energy node and said maximum material energy node comprises: evenly logarithmically interpolating a preset number of energy intervals between the minimum material energy nodes and the maximum material energy nodes to obtain evenly logarithmically interpolated energy nodes; Determining a resonance energy node of the constituent nuclides based on a nuclide cross-section library of the constituent nuclides; And adding the resonance energy nodes of the component nuclides into the energy nodes after the even logarithmic interpolation to obtain the material energy nodes.
5. The method of claim 4, wherein determining the resonant energy node of the constituent species based on the library of species cross-sections of the constituent species comprises: Acquiring nuclide section values of the component nuclides at a plurality of continuous nuclide energy nodes based on a nuclide section library of the component nuclides; Identifying whether a peak or a trough exists in the component nuclide according to nuclide section values of the component nuclide at a plurality of continuous nuclide energy nodes; when the constituent species is identified as having a peak or trough, a corresponding plurality of successive species energy nodes are determined as resonant energy nodes of the constituent species.
6. The method of building of claim 1, wherein said building a material cross-section library from said material energy nodes and said material information comprises: determining the nuclide section value of the component nuclide corresponding to the material energy node according to the nuclide section library of the component nuclide; Determining a material section value of the material energy node according to the nuclide section value of the material energy node corresponding to the component nuclide and the nuclide particle number density; a material section library is constructed based on the material energy nodes and the material section values.
7. The method of claim 6, wherein determining the nuclide cross-section values of the constituent nuclides corresponding to the material energy nodes from the nuclide cross-section library of the constituent nuclides comprises: Identifying whether the material energy node is a nuclide energy node of a nuclide cross-section library of the constituent nuclides; If the material energy node is the nuclide energy node of the nuclide cross section library of the component nuclides, acquiring a nuclide cross section value corresponding to the nuclide energy node as the nuclide cross section value of the component nuclides corresponding to the material energy node; If the material energy node is not the nuclide energy node of the nuclide cross section library of the component nuclides, a first nuclide energy node and a second nuclide energy node which are adjacent to the material energy node in the nuclide cross section library are obtained, wherein the first nuclide energy node is smaller than the second nuclide energy node, a first nuclide cross section value corresponding to the first nuclide energy node and a second nuclide cross section value corresponding to the second nuclide energy node are obtained, and the nuclide cross section value of the component nuclides corresponding to the material energy node is determined according to the material energy node, the first nuclide energy node, the second nuclide energy node, the first nuclide cross section value and the second nuclide cross section value.
8. A method of dose evaluation, the method comprising: Setting a material energy node; acquiring material information of a three-dimensional voxel model, wherein the material information at least comprises a composition nuclide and a nuclide particle number density; Constructing a material section library according to the material energy nodes and the material information; And carrying out particle simulation calculation according to the material section library to obtain the section value of the material where the particles are located, and evaluating the dosage according to the section value of the material where the particles are located.
9. The dose evaluation method according to claim 8, wherein the performing a particle simulation calculation according to the material section library to obtain a section value of a material in which particles are located comprises: Determining a first material energy node and a second material energy node adjacent to the particle energy based on the material energy nodes, the first material energy node being less than the particle energy and the second material energy node being greater than the particle energy; acquiring a first material section value corresponding to the first material energy node and a second material section value corresponding to the second material energy node from a material section library corresponding to the material where the particles are located; and obtaining the section value of the material where the particles are located according to the particle energy, the first material energy node, the second material energy node, the first material section value and the second material section value.
10. A dose evaluation system, comprising: the material section library construction module is used for constructing a material section library of the three-dimensional voxel model; the particle simulation calculation module is used for carrying out particle simulation calculation according to the material section library to obtain the section value of the material where the particles are located; The dose evaluation module is used for evaluating the dose according to the section value of the material in which the particles are positioned; wherein, the material cross section library construction module comprises: The material energy node setting unit is used for setting material energy nodes; the material information acquisition unit is used for acquiring material information of the three-dimensional voxel model, wherein the material information at least comprises a composition nuclide and a nuclide particle number density; and the material section library construction unit is used for constructing a material section library according to the material energy nodes and the material information.
11. The dose evaluation system of claim 10 wherein the material energy node setting unit comprises: The first energy node setting subunit is used for determining the minimum nuclide energy node value and the maximum nuclide energy node value in the nuclide energy nodes of all the component nuclides based on the nuclide cross section library of the component nuclides, determining the minimum nuclide energy node value as the minimum material energy node, and determining the maximum nuclide energy node value as the maximum material energy node; and the second energy node setting subunit is used for setting the material energy nodes according to the minimum material energy node and the maximum material energy node.
12. The dose evaluation system of claim 11 wherein the second energy node arrangement subunit comprises: the even logarithmic interpolation unit is used for evenly logarithmic interpolation of a preset number of energy intervals between the minimum material energy node and the maximum material energy node to obtain even logarithmic interpolated energy nodes; a resonance node determining unit for determining a resonance energy node of the constituent nuclide based on a nuclide cross-section library of the constituent nuclide; and the resonance node adding unit is used for adding the resonance energy nodes of the component nuclides into the energy nodes after the even logarithmic interpolation to obtain the material energy nodes.
13. The dose evaluation system of claim 10 wherein the material cross-section library construction unit comprises: The nuclide section value determining subunit is used for determining the nuclide section value of the component nuclide corresponding to the material energy node according to the nuclide section library of the component nuclide; A material section value determining subunit, configured to determine a material section value of the material energy node according to a nuclide section value of the material energy node corresponding to the component nuclide and the nuclide particle number density; A material section library construction subunit for constructing a material section library based on the material energy nodes and the material section values.
14. The dose evaluation system of claim 13 wherein the nuclide cross-section value determination subunit comprises: The nuclide energy node identification unit is used for identifying whether the material energy node is the nuclide energy node of the nuclide cross section library of the component nuclides; The first nuclide section value acquisition unit is used for acquiring a nuclide section value corresponding to the nuclide energy node as a nuclide section value of the component nuclide corresponding to the material energy node if the material energy node is a nuclide energy node of the nuclide section library of the component nuclide; And the second nuclide cross section value acquisition unit is used for acquiring a first nuclide energy node and a second nuclide energy node adjacent to the material energy node in the nuclide cross section library if the material energy node is not the nuclide energy node of the nuclide cross section library of the component nuclides, wherein the first nuclide energy node is smaller than the second nuclide energy node, acquiring a first nuclide cross section value corresponding to the first nuclide energy node and a second nuclide cross section value corresponding to the second nuclide energy node, and determining the nuclide cross section value of the component nuclides corresponding to the material energy node according to the material energy node, the first nuclide energy node, the second nuclide energy node, the first nuclide cross section value and the second nuclide cross section value.
15. The dose evaluation system of claim 10 wherein the particle simulation calculation module comprises: An adjacent energy node determining unit configured to determine, based on the material energy nodes, a first material energy node and a second material energy node adjacent to the particle energy, the first material energy node being smaller than the particle energy, the second material energy node being larger than the particle energy; A material section value obtaining unit, configured to obtain, in a material section library corresponding to a material where the particle is located, a first material section value corresponding to the first material energy node and a second material section value corresponding to the second material energy node; And the particle simulation calculation unit is used for obtaining the section value of the material where the particles are located according to the particle energy, the first material energy node, the second material energy node, the first material section value and the second material section value.

Description

Construction method, dose evaluation method and system of material section library Technical Field The application relates to the technical field of computers, in particular to a construction method, a dose evaluation method and a system of a material section library. 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, conventional photon or electron therapy is limited by the physical condition of the radiation itself, and damages a large amount of normal tissues on the beam path while killing tumor cells, and in addition, due to the difference of sensitivity of tumor cells to radiation, the conventional radiation therapy 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 therapy in chemotherapy (chemotherapy) is applied to radiotherapy, and 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 for tumor cells with high radiation resistance. The neutron capture therapy combines the two concepts, such as boron neutron capture therapy (Boron Neutron Capture Therapy, BNCT), and provides better cancer therapy selection than traditional radioactive rays by means of the specific accumulation of boron-containing drugs in tumor cells and the accurate beam regulation. The boron neutron capturing treatment utilizes the characteristic that boron (10B) containing medicine has a high capturing section for thermal neutrons, and two heavy charged particles of 4He and 7Li are generated by 10B (n, alpha) 7Li neutron capturing and nuclear division reaction, and the total range of the two particles is approximately equal to the cell size, so that radiation damage to organisms can be limited at the cell level, and when the boron containing medicine is selectively gathered in tumor cells, the purpose of killing the tumor cells locally can be achieved on the premise of not causing too great damage to normal tissues by matching with a proper neutron source. In boron neutron capture therapy, dose assessment is often required to make a treatment plan, and the most accurate and reliable method of dose assessment is the monte carlo method. Disclosure of Invention When the Monte Carlo method is adopted for dose evaluation, the section values of all nuclides of the material where the particles are located are accumulated to obtain the section values of the material where the particles are located. The above-mentioned process is usually executed by a processor, and the calculation is inefficient due to the large calculation amount and the large number of calculation branches. Aiming at the technical problems, the invention provides a construction method, a dose evaluation method and a system of a material section library, which can effectively improve the calculation efficiency. In a first aspect, the application provides a method for constructing a material section library. The method comprises the following steps: Setting a material energy node; acquiring material information, wherein the material information at least comprises a composition nuclide and a nuclide particle number density; and constructing a material section library according to the material energy nodes and the material information. In one embodiment, a material energy node is provided, comprising: based on a nuclide cross section library of the component nuclides, determining a minimum nuclide energy node value and a maximum nuclide energy node value, determining the minimum nuclide energy node value as a minimum material energy node, and determining the maximum nuclide energy node value as a maximum material energy node; And setting the material energy nodes according to the minimum material energy node and the maximum material energy node. In one embodiment, the material energy nodes are configured according to a minimum material energy node and a maximum material energy node, comprising: and uniformly logarithmically interpolating a preset number of energy intervals between the minimum material energy node and the maximum material energy node to obtain the material energy node. In one embodiment, the material energy nodes are configured according to a minimum material energy node and a maximum material energy node, comprising: uniformly logarithmically interpolating a preset number of energy intervals between the minimum material energy nodes and the maximum material energy nodes to obtain uniformly logarithmically interpolated energy nodes; Determining resonance energy nodes of the constituent nuclides based on a nuclide cross-section library of the constituent nuclides