CN115270531B - Multi-radiation-source shielding calculation method and device, electronic equipment and storage medium - Google Patents

Multi-radiation-source shielding calculation method and device, electronic equipment and storage medium Download PDF

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CN115270531B
CN115270531B CN202211190174.XA CN202211190174A CN115270531B CN 115270531 B CN115270531 B CN 115270531B CN 202211190174 A CN202211190174 A CN 202211190174A CN 115270531 B CN115270531 B CN 115270531B
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dose
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CN115270531A (en
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宋文
杨韵颐
全国萍
余慧
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State Power Investment Group Science and Technology Research Institute Co Ltd
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State Power Investment Group Science and Technology Research Institute Co Ltd
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Abstract

The present disclosure provides a multi-radiation source shielding calculation method, device, electronic device and storage medium, including: determining a plurality of radiation sources that have a radiation effect on a dose point location; establishing a multi-radiation-source geometric model based on a plurality of radiation sources; according to many radiation source geometric model, flux and dose rate of calculation dosage point position department, this disclosure is through setting up many radiation source geometric model, handles simultaneously to a plurality of radiation sources, carries out shielding calculation to many radiation sources simultaneously to can make this model more be applicable to the scene that the radiation source is complicated, effectively promote modeling efficiency and computational efficiency, guarantee the accuracy and the objectivity of computational result.

Description

Multi-radiation-source shielding calculation method and device, electronic equipment and storage medium
Technical Field
The disclosure relates to the technical field of radiation shielding of nuclear power plants, and in particular to a multi-radiation-source shielding calculation method and device, electronic equipment and a storage medium.
Background
In the operation process of a nuclear power plant, a certain amount of active corrosion products with radioactivity are deposited in each system device of an auxiliary factory building, and meanwhile, waste liquid/waste gas stored in the device also has radioactivity. These radioactive materials can cause radiation exposure to personnel performing routine dose monitoring and equipment maintenance. Therefore, it is very important to perform shielding calculation on each system equipment room of the nuclear power plant auxiliary plant.
In the related art, a point-kernel integration method is generally used to perform mask calculation for a single radiation source.
In this way, multiple modeling and multiple calculation are required to obtain the radiation flux and dose rate of the multiple radiation sources for the position of the dose point, respectively, the modeling efficiency and the calculation efficiency are insufficient, and the error between the calculation result and the actual situation is large.
Disclosure of Invention
The present disclosure is directed to solving, at least to some extent, one of the technical problems in the related art.
Therefore, the purpose of the disclosure is to provide a multi-radiation-source shielding calculation method, a multi-radiation-source shielding calculation device, electronic equipment and a storage medium, wherein a multi-radiation-source geometric model is built, a plurality of radiation sources are processed simultaneously, and shielding calculation is performed on the multi-radiation sources, so that the model is more suitable for scenes with complicated radiation sources, the modeling efficiency and the calculation efficiency are effectively improved, and the accuracy and the objectivity of calculation results are ensured.
The embodiment of the first aspect of the present disclosure provides a multiple-radiation-source shielding calculation method, including: determining a plurality of radiation sources that produce radiation effects on the dose point location; establishing a multi-radiation-source geometric model based on a plurality of radiation sources; from the multiple radiation source geometric model, the flux and dose rate at the dose point locations are calculated.
According to the multi-radiation source shielding calculation method provided by the embodiment of the first aspect of the disclosure, through determining a plurality of radiation sources which generate radiation influence on the position of a dose point, then based on the plurality of radiation sources, a multi-radiation source geometric model is established, the flux and the dose rate at the position of the dose point are calculated according to the multi-radiation source geometric model, through building the multi-radiation source geometric model, the plurality of radiation sources are processed simultaneously, meanwhile, the multi-radiation source is subjected to shielding calculation, so that the model is more suitable for the complex scenes of the radiation sources, the modeling efficiency and the calculation efficiency are effectively improved, and the accuracy and the objectivity of the calculation result are ensured.
A second aspect of the present disclosure provides a multi-radiation-source shielding computing apparatus, including: a determination module for determining a plurality of radiation sources that have a radiation effect on a dose point location; the building module is used for building a multi-radiation source geometric model based on a plurality of radiation sources; and the calculation module is used for calculating the flux and the dose rate at the position of the dose point according to the multi-radiation source geometric model.
The multi-radiation source shielding calculation device provided by the embodiment of the second aspect of the disclosure establishes a multi-radiation source geometric model by determining a plurality of radiation sources which generate radiation influence on the position of a dosage point, and calculates the flux and the dosage rate at the position of the dosage point according to the multi-radiation source geometric model, simultaneously processes a plurality of radiation sources by building the multi-radiation source geometric model, and simultaneously performs shielding calculation on the multi-radiation sources, so that the model is more suitable for complex scenes of the radiation sources, the modeling efficiency and the calculation efficiency are effectively improved, and the accuracy and the objectivity of calculation results are ensured.
According to a third aspect of the present disclosure, there is provided an electronic device comprising: at least one processor; and a memory communicatively coupled to the at least one processor; wherein the memory stores instructions executable by the at least one processor, the instructions being executable by the at least one processor to enable the at least one processor to perform the method for calculating a multiple radiation source shielding proposed in the embodiment of the first aspect of the present disclosure.
According to a fourth aspect of the present disclosure, a non-transitory computer-readable storage medium is proposed, in which computer instructions are stored, the computer instructions being configured to cause the computer to perform the multi-radiation-source-mask calculation method proposed in the embodiments of the first aspect of the present disclosure.
According to a fifth aspect of the present disclosure, a computer program product is provided, which comprises a computer program, when being executed by a processor, implements the multiple radiation source shield calculation method set forth in the embodiments of the first aspect of the present disclosure.
Additional aspects and advantages of the disclosure will be set forth in part in the description which follows and, in part, will be obvious from the description, or may be learned by practice of the disclosure.
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The above and/or additional aspects and advantages of the present disclosure will become apparent and readily appreciated from the following description of the embodiments, taken in conjunction with the accompanying drawings of which:
FIG. 1 is a schematic flow chart diagram illustrating a method for calculating a multiple radiation source mask according to an embodiment of the present disclosure;
FIG. 2 is a schematic flow chart diagram of a method for calculating a multiple radiation source shielding according to another embodiment of the present disclosure;
FIG. 3 is a schematic flow chart diagram of a multi-radiation source mask calculation method according to another embodiment of the present disclosure;
FIG. 4 is a schematic flow chart diagram of a multi-radiation source mask calculation method according to another embodiment of the present disclosure;
FIG. 5 is a schematic structural diagram of a multi-radiation source shielding computing device according to an embodiment of the present disclosure;
FIG. 6 is a schematic structural diagram of a multiple radiation source shielding computing device according to another embodiment of the present disclosure;
FIG. 7 illustrates a block diagram of an exemplary electronic device suitable for use in implementing embodiments of the present disclosure.
Detailed Description
Reference will now be made in detail to the embodiments of the present disclosure, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to the same or similar elements or elements having the same or similar functions throughout. The embodiments described below with reference to the accompanying drawings are illustrative only for the purpose of explaining the present disclosure, and are not to be construed as limiting the present disclosure. On the contrary, the embodiments of the disclosure include all changes, modifications and equivalents coming within the spirit and terms of the claims appended hereto.
Fig. 1 is a schematic flowchart of a method for calculating a multiple radiation source shielding according to an embodiment of the disclosure.
As shown in fig. 1, the multi-radiation source shielding calculation method includes:
s101: a plurality of radiation sources that have a radiation effect on the position of the dose point is determined.
Where the mask calculation is to be performed, this may be referred to as dose point position.
It is understood that the radiation source is primarily affected by radiation from fission products, activated corrosion products, and the like. During the operation of the reactor, the radiation sources flow along with the coolant through a primary loop main system (including a pressure vessel, a main pump, a pressure stabilizer, a main pipeline and the like), a chemical vessel control system, a radioactive waste liquid treatment system and the like, and the radiation sources can be distributed on a primary loop coolant system, auxiliary system equipment and the surface of the primary loop coolant system, namely, a plurality of radiation sources which generate radiation influence on the position of a dosage point can be arranged.
In the embodiment of the present disclosure, a plurality of radiation sources that generate radiation influence on the position of the dose point may be inferred by related staff according to engineering experience, or a radiation source analysis model may be set up, and a plurality of radiation sources that generate radiation influence on the position of the dose point are determined based on the radiation source analysis model in combination with the states of the respective system devices, or the system devices that generate radiation influence on the position of the dose point may be directly used as radiation sources, which is not limited herein.
S102: based on the plurality of radiation sources, a multiple radiation source geometric model is established.
The point-kernel integration model established based on the multiple radiation sources can be called a multiple radiation source geometric model.
In the embodiment of the present disclosure, an automatic modeling technology may be used to perform physical modeling on the position of the dose point, and information of multiple radiation sources is integrated into the model, so as to generate a multiple radiation source geometric model, or corresponding modeling software may process information of multiple radiation sources, so as to automatically build the multiple radiation source geometric model, or related staff may manually build the multiple radiation source geometric model according to information of multiple radiation sources, without any limitation.
The multi-radiation-source geometric model can be used for modeling a plurality of radiation sources simultaneously, so that the plurality of radiation sources which generate radiation influence on the positions of dose points are integrated in the same model simultaneously, and the modeling efficiency and the calculation efficiency are effectively improved.
The embodiments of the present disclosure may implement shielding calculation of the position of the dose point based on a multi-radiation source geometric model established by the multi-radiation source, which may be specifically referred to in the following embodiments.
S103: from the multiple radiation source geometric model, the flux and dose rate at the dose point locations are calculated.
The radiation energy received by a unit area at a position of a dose point in a unit time can be called flux density, namely flux; which is used to represent the radiation dose received per unit time, may be referred to as a dose rate.
In the embodiment of the disclosure, a radiation scene at the position of a dose point can be simulated and modeled based on a geometric model of multiple radiation sources, and then shielding calculation processing is performed at the position of the dose point based on the radiation condition of the multiple radiation sources to obtain flux and dose rate at the position of the dose point.
In the embodiment of the present disclosure, the flux at the position of the dose point may be determined through a geometric model of multiple radiation sources, and then the dose rate at the position of the dose point may be calculated according to a flux-dose conversion factor. Wherein the flux-dose conversion factor can be derived via corresponding flux-dose conversion criteria.
That is to say, in the embodiment of the present disclosure, the flux and the dose rate at the dose point position may be directly calculated and obtained through the multiple radiation source geometric model, or the flux at the dose point position may also be calculated and determined through the multiple radiation source geometric model, and the dose rate at the dose point position is further calculated and determined according to the data information corresponding to the flux.
In this embodiment, through confirming a plurality of radiation sources that produce radiation effect to dosage point position, then based on a plurality of radiation sources, establish many radiation source geometric model, and according to many radiation source geometric model, calculate the flux and the dose rate of dosage point position department, owing to be through setting up many radiation source geometric model, carry out simultaneous processing to a plurality of radiation sources, carry out shielding calculation to many radiation sources simultaneously, thereby can make this model more be applicable to the complicated scene of radiation source, effectively promote modeling efficiency and computational efficiency, guarantee the accuracy and the objectivity of calculated result.
Fig. 2 is a schematic flowchart of a multi-radiation source mask calculation method according to another embodiment of the present disclosure.
As shown in fig. 2, the multi-radiation source shielding calculation method includes:
s201: a plurality of radiation sources that have a radiation effect on the position of the dose point is determined.
For specific description of S201, reference may be made to the foregoing embodiments, which are not described herein again.
S202: geometric information of a plurality of radiation sources is determined.
The embodiment of the disclosure can divide a scene where the dose point position is located into a plurality of regions, each region can be regarded as being composed of the same or different uniform materials, the region has a corresponding geometric space, the geometric space of the scene where the dose point position is located can be constructed and described according to a geometric technology, and geometric information of a plurality of radiation sources is determined according to the geometric space.
The geometric information of the radiation sources is information of spatial distribution, geometric shape characteristics, sizes, materials and the like of the multiple radiation sources in different geometric spaces, and the geometric information of the different radiation sources can be the same or different, which is not limited.
In the embodiment of the present disclosure, the types of the geometric features are various, such as a cylinder structure type, a sphere structure type, a rectangular parallelepiped structure type, and the like, which is not limited herein.
In the embodiment of the present disclosure, the geometric information corresponding to the multiple radiation sources may be respectively determined according to the scene where the multiple radiation sources are located, or the scene where the dose point is located may be explored (for example, radar ranging), and the geometric information corresponding to the multiple radiation sources is determined, or the geometric information corresponding to the multiple radiation sources may be determined in a manner of spatial dispersion, and the like, without limitation.
S203: and establishing a multi-radiation source geometric model according to the geometric information.
In the embodiment of the disclosure, a multi-radiation source geometric model can be built according to geometric information and by combining with scene information of the multi-radiation source, that is, the multi-radiation source geometric model can be built according to information such as spatial distribution, geometric structures, sizes, materials and the like of a plurality of radiation sources.
S204: a corresponding geometrical coordinate system is selected for each of the plurality of radiation sources.
The geometric coordinate system is a geometric space coordinate system corresponding to the radiation source, and the geometric coordinate system may include a cylindrical coordinate system, a spherical coordinate system, a rectangular coordinate system, and the like, which is not limited to this.
Optionally, in the embodiment of the present disclosure, the types of the geometric coordinate systems are multiple, and the geometric coordinate systems corresponding to the multiple radiation sources may be the same or different, and because multiple geometric coordinate systems are provided, the radiation sources in the multiple radiation source geometric model can all find the adapted geometric coordinate system, so that the reliability of the model can be effectively enhanced, and the applicability of the model calculation is improved.
In the embodiment of the present disclosure, the geometric coordinate system may include a cylindrical coordinate system, a spherical coordinate system, a rectangular coordinate system, and the like, wherein the selection of the geometric coordinate system may correspond to the characteristics of the geometric shape, that is, the cylindrical structure type corresponds to the cylindrical coordinate system, the spherical structure type corresponds to the spherical coordinate system, and the rectangular coordinate system corresponds to the rectangular coordinate system, coordinate axes used by different coordinate systems may be the same or different, the cylindrical coordinate system includes a radius of a bottom surface of the cylinder, an angle, and a symmetry axis in a height direction of the cylinder, the spherical coordinate system includes a radius of the sphere and an angle, the rectangular coordinate system includes three mutually perpendicular coordinate axes intersecting with a certain vertex in the rectangular solid, and of course, other geometric coordinate systems also have coordinate axes corresponding thereto, which is not limited.
In the embodiment of the present disclosure, different radiation sources may correspond to the same or different geometric coordinate systems, and corresponding geometric coordinate systems may be allocated to the radiation sources according to the scene conditions of the positions of the radiation sources.
S205: and carrying out source intensity discrete processing on the radiation source according to a geometric coordinate system to generate a plurality of point sources.
It can be understood that, in the plurality of radiation sources, there are a plurality of radiation source types such as a point source, a surface source and a source, and when the radiation source type is a surface source or a source, it is cumbersome to directly shield the radiation source, and then a strong discrete process may be performed on the radiation source with the surface source and the source to convert the surface source or the source into an equivalent plurality of point sources, so as to facilitate the shielding calculation.
In the embodiment of the present disclosure, a spatial discrete function may be set to perform source intensity dispersion on a plurality of radiation sources to generate a plurality of point sources, or a point nuclear integration model may also be set up to perform spatial discrete processing on the radiation sources based on the point nuclear integration model to generate a plurality of point sources, or any other possible implementation manner may also be used to perform source intensity discrete processing on the radiation sources to generate a plurality of point sources, which is not limited to this.
In the embodiment of the present disclosure, the radiation source may generate one or more corresponding equivalent point sources through source intensity discretization processing, and then in the multiple radiation source geometric model, the source intensity discretization processing may be performed on a plurality of radiation sources therein, respectively.
In the embodiment of the present disclosure, the radiation source in which the source intensity is to be discretized may be manually selected, or, when the type of the radiation source is detected as a surface source and a source, the source intensity discretization step may be triggered to process the radiation source into one or more point sources, which is not limited herein.
S206: from the multiple radiation source geometric model, the flux and dose rate at the dose point locations are calculated.
For specific description of S206, reference may be made to the above embodiments, which are not described herein again.
In the embodiment, as the geometric model of the multiple radiation sources is built, the multiple radiation sources are processed simultaneously, and the multiple radiation sources are shielded and calculated, the model is more suitable for the scene with complex radiation sources, the modeling efficiency and the calculation efficiency are effectively improved, and the accuracy and the objectivity of the calculation result are ensured. Because according to the geometric information of a plurality of radiation sources, a multi-radiation-source geometric model is established, the plurality of radiation sources can be organically integrated into one model, the spatial distribution condition of each device in a nuclear power plant can be simulated more accurately, and the effect of the multi-radiation-source geometric model is effectively improved. Because a plurality of geometric coordinate systems are arranged, the radiation sources in the multi-radiation source geometric model can all find the adaptive geometric coordinate system, so that the reliability of the model can be effectively enhanced, and the adaptability of model calculation is improved. Because the source intensity discrete processing is carried out on the radiation source according to the geometric coordinate system to generate a plurality of point sources, the complex geometric model can be simplified, the shielding calculation of the radiation source is convenient, and the shielding calculation accuracy of the radiation source is improved.
Fig. 3 is a schematic flowchart of a method for calculating a multiple radiation source shielding according to another embodiment of the disclosure.
As shown in fig. 3, the multi-radiation source shielding calculation method includes:
s301: a plurality of radiation sources that produce a radiation effect on a dose point location is determined.
S302: geometric information of a plurality of radiation sources is determined.
S303: and establishing a multi-radiation source geometric model according to the geometric information.
S304: a corresponding geometrical coordinate system is selected for each of the plurality of radiation sources.
S305: and carrying out source intensity discrete processing on the radiation source according to a geometric coordinate system to generate a plurality of point sources.
For specific descriptions of S301 to S305, reference may be made to the above embodiments, which are not described herein again.
S306: determining at least one geometric space traversed at each point source-to-dose point location, determining a constituent material at each point source-to-dose point location from constituent materials of the geometric space.
The radiation source body is wrapped by a shielding material in a nuclear power plant, and the shielding material and the radiation source body can be both called as a composition material, such as a composition shielding layer of iron and lead, without limitation.
In the embodiment of the disclosure, information such as size thickness, density, element composition, mass ratio and the like of the composition materials corresponding to the radiation source and the shielding body can be determined according to the condition of the nuclear power plant, so as to determine the composition materials from the point source to the position of the dosage point.
It will be appreciated that the point source-to-dose point locations may pass through at least one geometric space, and different geometric spaces may correspond to the same or different constituent materials, and thus, the point source-to-dose point locations may pass through a plurality of geometric spaces composed of the same or different constituent materials, and when a ray passes through a certain geometric space, the constituent material corresponding to that geometric space may be determined.
S307: the optical distance of the point source from the position of the dose point is determined according to the constituent materials.
The optical distance is calculated by considering the material density and the mass attenuation coefficient of different composition materials and combining the geometric distance.
In the embodiment of the present disclosure, the optical distance between the point source and the dose point position may be calculated according to the composition material from the point source to the dose point position, in combination with the mass attenuation coefficient.
Optionally, in the embodiments of the present disclosure, the point source to dose point position passes through at least one geometric space, and the travel distance from the point source to the dose point position in the geometric space is determined; determining the mass attenuation coefficient of the ray passing through the geometric space according to the composition materials; and determining the optical distance from the point source to the position of the dosage point according to the mass attenuation coefficient corresponding to the at least one geometric space.
In the embodiment of the present disclosure, the point source to the dose point position passes through at least one geometric space, and different geometric spaces may correspond to the same or different constituent materials, that is, the entrance distance and the exit distance of the ray in different geometric spaces may be calculated respectively, and then the distance between the entrance and the exit of the ray in a certain geometric space may be referred to as a travel distance.
The mass attenuation coefficient in the embodiment of the present disclosure is related to photon energy of a ray and also related to a composition material, and the mass attenuation coefficients of different photon energies and different composition materials may also be different. Thus, the mass attenuation coefficient of a ray traversing a geometric space can be determined based on the photon energy of a particular radiation source, in combination with the constituent materials.
In some embodiments, a calculation formula of the mass attenuation coefficient may be set, and the mass attenuation coefficient may be determined according to information such as the type of the constituent material, and the like, in combination with the photon energy of the radiation source, which is not limited to this.
In the embodiment of the present disclosure, the point source to the dose point position may pass through one or more geometric spaces, and when passing through a plurality of geometric spaces, the mass attenuation coefficients of the geometric spaces may be calculated respectively, so as to calculate optical distances corresponding to the geometric spaces respectively, and integrate the optical distances of the geometric spaces as the optical distance from the point source to the dose point position.
Of course, the present disclosure also supports using multiple ways to calculate the mass attenuation coefficients corresponding to the rays passing through different geometric spaces, and further calculate the optical distance from the point source to the dose point, which is not limited herein.
S308: the accumulation factor is calculated from the constituent materials.
The ratio of the intensity of radiation (including scattered radiation) of the radiation beam passing through a thickness of a constituent material to the intensity of radiation at the same point (including no scattering) may be referred to herein as an accumulation factor, which may be used in the calculation of the flux and dose rate at the location of the dose point.
It is understood that factors affecting the accumulation factor are photon energy and the properties of the constituent materials.
In some embodiments of the present disclosure, the accumulation factor may be calculated by combining material properties of the constituent materials (e.g., material type, material density, fitting parameters of the material, etc.) with the photon energy of the radiation source.
In some embodiments, an accumulation factor calculation formula may be manually constructed to calculate the accumulation factor, or the accumulation factor may also be calculated by using a Geometric Progression (GP) method, a Taylor exponential fitting (Taylor) method, or the like, which is not limited to this.
S309: flux and dose rates at the dose point locations are generated from the optical distances and the accumulation factors via multiple radiation source geometry model calculations.
In embodiments of the present disclosure, after calculating the optical distance and the accumulation factor, the optical distance and the accumulation factor may be used as inputs to a multi-radiation source geometric model to generate the flux and dose rate at the dose point location.
When the flux at the position of the dose point is calculated, the parameters of the iterative model can be continuously adjusted in an iterative calculation mode until the error of the calculation result of the multi-radiation source geometric model meets the preset error requirement, so that a better multi-radiation source geometric model meeting the requirement can be obtained.
In this embodiment, because through setting up many radiation sources geometric model, handle simultaneously a plurality of radiation sources, shield the calculation to many radiation sources simultaneously to can make this model more be applicable to the scene that the radiation source is complicated, effectively promote modeling efficiency and computational efficiency, guarantee the accuracy and the objectivity of calculated result. The flux and the dose rate at the position of the dose point are generated through calculation of the multi-radiation source geometric model according to the optical distance and the accumulation factor, so that the accuracy of the calculation result is effectively ensured, and the calculation efficiency is improved.
Fig. 4 is a flowchart illustrating a method for calculating a multi-radiation source mask according to another embodiment of the present disclosure.
As shown in fig. 4, the multi-radiation source mask calculation method includes:
in step S401, a plurality of radiation sources that produce a radiation effect on a dose point location is determined;
in step S402, a multi-radiation source geometric model is built according to geometric information such as spatial distribution, geometric structure and size, and material of the multiple radiation sources;
in step S403, according to the geometric features of the multiple radiation sources, a cylindrical coordinate system, a spherical coordinate system, or a rectangular coordinate system is selected as a relative coordinate system, and source intensity dispersion is performed on the radiation sources, that is, a surface source/a source are dispersed into multiple point sources;
in step S404, calculating a mass attenuation coefficient according to the constituent materials, and further solving an optical distance from each point source to a dose point after dispersion;
in step S405, an accumulation factor is solved according to the constituent materials;
in step S406, the flux and dose rate at the dose point location are calculated.
In the embodiment of the disclosure, a cylindrical coordinate system, a spherical coordinate system or a rectangular coordinate system may be selected as a relative coordinate system, and source intensity discretization may be performed on the radiation sources according to the relative coordinate system, and different radiation sources may form a plurality of equivalent point sources through source intensity discretization, so as to perform calculation of a multi-radiation-source geometric model based on the point sources after source intensity discretization.
In the embodiment of the present disclosure, a cylindrical coordinate system, a spherical coordinate system, or a rectangular coordinate system may be selected as the relative coordinate system according to the geometric information of the radiation source, for example, if the geometric information of a certain radiation source indicates that the radiation source is a cylindrical structure, the cylindrical coordinate system may be used as the coordinate system of the radiation source, and the radiation source may be discretized into a plurality of point sources according to the source intensity discretization process.
In the embodiment, as the geometric model of the multiple radiation sources is built, the multiple radiation sources are processed simultaneously, and the multiple radiation sources are shielded and calculated, the model is more suitable for the scene with complex radiation sources, the modeling efficiency and the calculation efficiency are effectively improved, and the accuracy and the objectivity of the calculation result are ensured.
Fig. 5 is a schematic structural diagram of a multi-radiation source shielding computing device according to an embodiment of the disclosure.
As shown in fig. 5, a multiple radiation source shield computing device 50 includes:
a determining module 501 for determining a plurality of radiation sources that have a radiation effect on a dose point position;
an establishing module 502 for establishing a multi-radiation-source geometric model based on a plurality of radiation sources;
a calculation module 503 for calculating the flux and dose rate at the position of the dose point according to the multiple radiation source geometric model.
In some embodiments of the present disclosure, as shown in fig. 6, fig. 6 is a schematic structural diagram of a multiple radiation source shielding computing apparatus according to another embodiment of the present disclosure, wherein the establishing module 502 is specifically configured to:
determining geometric information of a plurality of radiation sources;
and establishing a multi-radiation source geometric model according to the geometric information.
In some embodiments of the present disclosure, as shown in fig. 6, further comprising:
a selecting module 504, configured to select corresponding geometric coordinate systems for the multiple radiation sources after establishing the multiple radiation source geometric model according to the geometric information;
a processing module 505, configured to perform source intensity discretization on the radiation source according to the geometric coordinate system, so as to generate a plurality of point sources;
in some embodiments of the present disclosure, as shown in fig. 6, the types of the geometric coordinate systems are various, and the geometric coordinate systems corresponding to the plurality of radiation sources may be the same or different.
In some embodiments of the present disclosure, as shown in fig. 6, the calculating module 503 is specifically configured to:
determining at least one geometric space traversed by each point source-to-dose point location, determining constituent materials at each point source-to-dose point location from constituent materials of the geometric space;
determining the optical distance between the point source and the position of the dosage point according to the composition material;
calculating an accumulation factor according to the constituent materials;
flux and dose rates at the dose point locations are generated from the optical distances and the accumulation factors via multiple radiation source geometry model calculations.
In some embodiments of the present disclosure, as shown in fig. 6, the calculating module 503 is specifically configured to:
determining the travel distance from a point source to the position of a dose point in a geometric space;
determining the mass attenuation coefficient of the ray passing through the geometric space according to the composition materials;
and determining the optical distance from the point source to the position of the dosage point according to the mass attenuation coefficient corresponding to the at least one geometric space.
In correspondence with the multi-radiation source shielding calculation method provided in the embodiment of fig. 1 to 4, the present disclosure also provides a multi-radiation source shielding calculation apparatus, and since the multi-radiation source shielding calculation apparatus provided in the embodiment of the present disclosure corresponds to the multi-radiation source shielding calculation method provided in the embodiment of fig. 1 to 4, the implementation manner of the multi-radiation source shielding calculation method is also applicable to the multi-radiation source shielding calculation apparatus provided in the embodiment of the present disclosure, and will not be described in detail in the embodiment of the present disclosure.
In this embodiment, through confirming a plurality of radiation sources that produce radiation influence to dosage point position, then based on a plurality of radiation sources, establish many radiation source geometric model, and according to many radiation source geometric model, calculate the flux and the dose rate of dosage point position department, owing to be through setting up many radiation source geometric model, carry out simultaneous processing to a plurality of radiation sources, carry out shielding calculation to many radiation sources simultaneously, thereby can make this model more be applicable to the scene that the radiation source is complicated, effectively promote modeling efficiency and computational efficiency, guarantee the accuracy and the objectivity of computational result.
In order to achieve the above embodiments, the present disclosure also proposes a non-transitory computer-readable storage medium on which a computer program is stored, which program, when executed by a processor, implements the multiple radiation source shield calculation method as proposed by the previous embodiments of the present disclosure.
In order to implement the above embodiment, the present disclosure further provides an electronic device, including: a memory, a processor and a computer program stored on the memory and executable on the processor, the processor when executing the program implementing the method for calculating a multiple radiation source shielding as proposed by the aforementioned embodiments of the present disclosure.
In order to implement the above embodiments, the present disclosure also proposes a computer program product, which when being executed by an instruction processor in the computer program product, performs the multi-radiation source mask calculation method as proposed by the foregoing embodiments of the present disclosure.
FIG. 7 illustrates a block diagram of an exemplary electronic device suitable for use in implementing embodiments of the present disclosure. The electronic device 12 shown in fig. 7 is only an example and should not bring any limitation to the function and the scope of use of the embodiments of the present disclosure.
As shown in FIG. 7, electronic device 12 is embodied in the form of a general purpose computing device. The components of the electronic device 12 may include, but are not limited to: one or more processors or processing units 16, a system memory 28, and a bus 18 that couples various system components including the system memory 28 and the processing unit 16. Bus 18 represents one or more of any of several types of bus structures, including a memory bus or memory controller, a peripheral bus, an accelerated graphics port, a processor, or a local bus using any of a variety of bus architectures. These architectures include, but are not limited to, industry Standard Architecture (ISA) bus, micro Channel Architecture (MAC) bus, enhanced ISA bus, video Electronics Standards Association (VESA) local bus, and Peripheral Component Interconnect (PCI) bus, to name a few.
Electronic device 12 typically includes a variety of computer system readable media. Such media may be any available media that is accessible by electronic device 12 and includes both volatile and nonvolatile media, removable and non-removable media.
Memory 28 may include computer system readable media in the form of volatile Memory, such as Random Access Memory (RAM) 30 and/or cache Memory 32. The electronic device 12 may further include other removable/non-removable, volatile/nonvolatile computer system storage media. By way of example only, storage system 34 may be used to read from and write to non-removable, nonvolatile magnetic media (not shown in FIG. 7, and commonly referred to as a "hard drive").
Although not shown in FIG. 7, a disk drive for reading from and writing to a removable, nonvolatile magnetic disk (e.g., a "floppy disk") and an optical disk drive for reading from or writing to a removable, nonvolatile optical disk (e.g., a Compact disk Read Only Memory (CD-ROM), a Digital versatile disk Read Only Memory (DVD-ROM), or other optical media) may be provided. In these cases, each drive may be connected to bus 18 by one or more data media interfaces. Memory 28 may include at least one program product having a set (e.g., at least one) of program modules that are configured to carry out the functions of embodiments of the disclosure.
A program/utility 40 having a set (at least one) of program modules 42 may be stored, for example, in memory 28, such program modules 42 including, but not limited to, an operating system, one or more application programs, other program modules, and program data, each of which examples or some combination thereof may comprise an implementation of a network environment. Program modules 42 generally perform the functions and/or methodologies of the embodiments described in this disclosure.
Electronic device 12 may also communicate with one or more external devices 14 (e.g., keyboard, pointing device, display 24, etc.), with one or more devices that enable a user to interact with electronic device 12, and/or with any devices (e.g., network card, modem, etc.) that enable electronic device 12 to communicate with one or more other computing devices. Such communication may be through an input/output (I/O) interface 22. Also, the electronic device 12 may communicate with one or more networks (e.g., a Local Area Network (LAN), a Wide Area Network (WAN), and/or a public Network such as the Internet) via the Network adapter 20. As shown, the network adapter 20 communicates with other modules of the electronic device 12 via the bus 18. It should be understood that although not shown in the figures, other hardware and/or software modules may be used in conjunction with electronic device 12, including but not limited to: microcode, device drivers, redundant processing units, external disk drive arrays, RAID systems, tape drives, and data backup storage systems, among others.
The processing unit 16 executes programs stored in the system memory 28 to perform various functional applications and data processing, such as implementing the multi-radiation source mask calculation method mentioned in the previous embodiment.
Other embodiments of the disclosure will be apparent to those skilled in the art from consideration of the specification and practice of the disclosure disclosed herein. This disclosure is intended to cover any variations, uses, or adaptations of the disclosure following, in general, the principles of the disclosure and including such departures from the present disclosure as come within known or customary practice within the art to which the disclosure pertains. It is intended that the specification and examples be considered as exemplary only, with a true scope and spirit of the disclosure being indicated by the following claims.
It will be understood that the present disclosure is not limited to the precise arrangements described above and shown in the drawings and that various modifications and changes may be made without departing from the scope thereof. The scope of the present disclosure is limited only by the appended claims.
It should be noted that, in the description of the present disclosure, the terms "first", "second", etc. are used for descriptive purposes only and are not to be construed as indicating or implying relative importance. In addition, in the description of the present disclosure, the meaning of "a plurality" is two or more unless otherwise specified.
Any process or method descriptions in flow charts or otherwise described herein may be understood as representing modules, segments, or portions of code which include one or more executable instructions for implementing specific logical functions or steps of the process, and the scope of the preferred embodiments of the present disclosure includes other implementations in which functions may be executed out of order from that shown or discussed, including substantially concurrently or in reverse order, depending on the functionality involved, as would be understood by those reasonably skilled in the art of the embodiments of the present disclosure.
It should be understood that portions of the present disclosure may be implemented in hardware, software, firmware, or a combination thereof. In the above embodiments, the various steps or methods may be implemented in software or firmware stored in memory and executed by a suitable instruction execution system. For example, if implemented in hardware, as in another embodiment, any one or combination of the following techniques, which are known in the art, may be used: a discrete logic circuit having a logic gate circuit for implementing a logic function on a data signal, an application specific integrated circuit having an appropriate combinational logic gate circuit, a Programmable Gate Array (PGA), a Field Programmable Gate Array (FPGA), or the like.
It will be understood by those skilled in the art that all or part of the steps carried by the method for implementing the above embodiments may be implemented by hardware related to instructions of a program, which may be stored in a computer readable storage medium, and when the program is executed, the program includes one or a combination of the steps of the method embodiments.
In addition, functional units in the embodiments of the present disclosure may be integrated into one processing module, or each unit may exist alone physically, or two or more units are integrated into one module. The integrated module can be realized in a hardware mode, and can also be realized in a software functional module mode. The integrated module, if implemented in the form of a software functional module and sold or used as a stand-alone product, may also be stored in a computer readable storage medium.
The storage medium mentioned above may be a read-only memory, a magnetic or optical disk, etc.
In the description herein, references to the description of the term "one embodiment," "some embodiments," "an example," "a specific example," or "some examples," etc., mean that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the present disclosure. In this specification, the schematic representations of the terms used above do not necessarily refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples.
While embodiments of the present disclosure have been shown and described above, it will be understood that the above embodiments are exemplary and not to be construed as limiting the present disclosure, and that changes, modifications, substitutions and alterations may be made to the above embodiments by those of ordinary skill in the art within the scope of the present disclosure.

Claims (4)

1. A method for multiple radiation source shielding calculation, comprising:
determining a plurality of radiation sources which generate radiation influence on the position of a dose point, wherein the position of the dose point is a position to be subjected to shielding calculation;
establishing a multiple radiation source geometric model based on the plurality of radiation sources;
calculating flux and dose rate at the dose point location from the multiple radiation source geometric model;
said building a multiple radiation source geometric model based on said plurality of radiation sources, comprising:
determining geometric information of the plurality of radiation sources;
establishing a multi-radiation source geometric model according to the geometric information;
after the building a geometric model of multiple radiation sources according to the geometric information, the method further comprises:
selecting corresponding geometric coordinate systems for the plurality of radiation sources respectively;
according to the geometric coordinate system, performing source intensity discrete processing on the radiation source to generate a plurality of point sources;
the types of the geometric coordinate systems are various, and the geometric coordinate systems corresponding to the radiation sources can be the same or different;
the calculating the flux and dose rate at the dose point location from the multiple radiation source geometric model comprises:
determining at least one geometric space traversed by each point source to the dose point location, the constituent material at each point source to dose point location being determined from the constituent material of the geometric space;
determining an optical distance of the point source from the dose point location from the constituent material;
calculating an accumulation factor from the constituent materials;
generating flux and dose rates at the dose point locations via the multi-radiation source geometry model calculation as a function of the optical distances and the accumulation factors;
the determining an optical distance of the point source from the location of the dose point from the constituent material comprises:
determining a distance of travel of the point source to the dose point location within the geometric space;
determining a mass attenuation coefficient of a ray passing through the geometric space according to the composition material;
and determining the optical distance from the point source to the position of the dosage point according to the mass attenuation coefficient corresponding to the at least one geometric space.
2. A multiple radiation source shielding computing device, comprising:
the device comprises a determining module, a calculating module and a processing module, wherein the determining module is used for determining a plurality of radiation sources which generate radiation influence on the position of a dosage point, and the position of the dosage point is a position to be subjected to shielding calculation;
an establishing module for establishing a multi-radiation-source geometric model based on the plurality of radiation sources;
a calculation module for calculating flux and dose rate at the dose point locations according to the multi-radiation source geometric model;
the establishing module is specifically configured to:
determining geometric information of the plurality of radiation sources;
establishing a multi-radiation source geometric model according to the geometric information;
after the building a geometric model of the multiple radiation sources according to the geometric information, the method further comprises the following steps:
selecting corresponding geometric coordinate systems for the plurality of radiation sources respectively;
according to the geometric coordinate system, performing source intensity discrete processing on the radiation source to generate a plurality of point sources;
the types of the geometric coordinate systems are various, and the geometric coordinate systems corresponding to the radiation sources can be the same or different;
said calculating fluxes and dose rates at said dose point locations according to said multiple radiation source geometric model, comprising:
determining at least one geometric space traversed by each point source to the dose point location, the constituent material at each point source to dose point location being determined from the constituent material of the geometric space;
determining an optical distance of the point source from the dose point location from the constituent material;
calculating an accumulation factor from the constituent materials;
generating flux and dose rates at the dose point locations via the multi-radiation source geometry model calculation as a function of the optical distances and the accumulation factors;
the determining an optical distance of the point source from the dose point location from the constituent material comprises:
determining a distance of travel of the point source to the dose point location within the geometric space;
determining a mass attenuation coefficient of a ray passing through the geometric space according to the composition material;
and determining the optical distance from the point source to the position of the dosage point according to the mass attenuation coefficient corresponding to the at least one geometric space.
3. An electronic device, comprising:
at least one processor; and
a memory communicatively coupled to the at least one processor; wherein the content of the first and second substances,
the memory stores instructions executable by the at least one processor to enable the at least one processor to perform the multi-radiation source mask calculation method of claim 1.
4. A non-transitory computer readable storage medium having stored thereon computer instructions for causing the computer to perform the multi-radiation source shield calculation method of claim 1.
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CN107290770A (en) * 2016-04-12 2017-10-24 华北电力大学 The recombination radiation source strength backstepping method and system of nuclear power plant's point-line-surface body combination
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CN107290769A (en) * 2016-04-12 2017-10-24 华北电力大学 The recombination radiation source strength backstepping method and system of nuclear power plant's point source body source combination
CN107290770A (en) * 2016-04-12 2017-10-24 华北电力大学 The recombination radiation source strength backstepping method and system of nuclear power plant's point-line-surface body combination
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