Thickness determination method and device for protective wall, equipment, medium and program product
By obtaining the corresponding relationship between radiation protection design parameters and nuclear parameters, the thickness of the protective wall in nuclear medicine is automatically calculated, which solves the problems of low computing efficiency and accuracy in the existing technology, and achieves efficient and accurate determination of the thickness of the protective wall.
Patent Information
- Application Number
- CN202510383679.5
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2025-03-28
- Publication Date
- 2025-07-22
AI Technical Summary
The thickness calculation efficiency and accuracy of the protective walls in the prior art CNM are low, and radiation damage cannot be effectively controlled.
By obtaining the radiation protection design parameters of the area to be monitored, including material type and nuclide category data, the correspondence between the preset protection parameters and the nuclear parameters is used to calculate and output the thickness of the protective wall to achieve automated and programmatic thickness determination.
The calculation efficiency and accuracy of the thickness of the protective wall is improved, and the radiation protection in the nuclear medicine department meets the standard requirements.
Smart Images
Figure CN120354484A_ABST
Abstract
Description
Technical Field
[0001] The present disclosure relates to the technical field of radiation protection, and in particular, to a method, device, equipment, medium and program product for determining the thickness of a protective wall. Background Art
[0002] In the related art, radioactive nuclides are usually used in the process of medical diagnosis and treatment in the nuclear medicine department. The radiation generated by these nuclides must be strictly controlled to prevent radiation damage to personnel and the environment. For this reason, relevant specifications have clear requirements for the thickness of the protective wall in the nuclear medicine department. The thickness of the protective wall is usually calculated manually, which results in low calculation efficiency and accuracy. Summary of the Invention
[0003] The present disclosure provides a method, device, equipment, medium and program product for determining the thickness of a protective wall. The technical solution of the present disclosure is as follows:
[0004] In a first aspect, the present disclosure provides a method for determining the thickness of a protective wall, including:
[0005] Obtaining radiation protection design parameters of a to-be-monitored area; wherein, the radiation protection design parameters include material type data of a proposed protective wall and nuclide category data;
[0006] Obtaining the corresponding relationship between preset protection parameters and nuclear parameters;
[0007] Determining target nuclear parameters corresponding to the material type data of the proposed protective wall and the nuclide category data according to the corresponding relationship between the preset protection parameters and the nuclear parameters;
[0008] Calculating the thickness of the protective wall of the to-be-monitored area based on the radiation protection design parameters and the target nuclear parameters;
[0009] Outputting the thickness of the protective wall of the to-be-monitored area.
[0010] In a possible implementation manner, the radiation protection design parameters further include nuclide usage dose data, and the nuclide usage dose data includes the maximum activity of the radiation source used; the target nuclear parameters include the tenth value layer thickness TVL and the ambient dose equivalent rate constant Γ.
[0011] In a possible implementation manner, after outputting the thickness of the protective wall of the to-be-monitored area, at least one of the following is further included:
[0012] Calculating the distance between a second reference point and the radiation source according to the thickness of the protective wall of the to-be-monitored area; and verifying whether the thickness of the protective wall of the to-be-monitored area meets the requirements based on the distance between the second reference point and the radiation source;
[0013] Calculate a second dose rate control value based on the distance between the second reference point and the radiation source and the thickness of the shielding wall of the area to be monitored; verify whether the thickness of the shielding wall of the area to be monitored meets the requirements based on the second dose rate control value.
[0014] In a possible implementation, the radiation protection design parameters further include a first dose rate control value;
[0015] The calculating the distance between the second reference point and the radiation source according to the thickness of the shielding wall of the area to be monitored includes:
[0016] Calculate the distance between the second reference point and the radiation source according to the target nuclear parameter, the nuclide category data, the nuclide usage dose data, the material type data of the shielding wall to be adopted, the first dose rate control value, and the thickness of the shielding wall of the area to be monitored;
[0017] The calculating the second dose rate control value based on the distance between the second reference point and the radiation source and the thickness of the shielding wall of the area to be monitored includes:
[0018] Calculate the second dose rate control value according to the target nuclear parameter, the nuclide category data, the nuclide usage dose data, the material type data of the shielding wall to be adopted, the thickness of the shielding wall of the area to be monitored, and the distance between the second reference point and the radiation source.
[0019] In a possible implementation, the radiation protection design parameters further include the distance between the first reference point and the radiation source;
[0020] The verifying whether the thickness of the shielding wall of the area to be monitored meets the requirements based on the distance between the second reference point and the radiation source includes:
[0021] Calculate the distance difference between the distance between the second reference point and the radiation source and the distance between the first reference point and the radiation source;
[0022] When the distance difference belongs to a first preset range, determine that the thickness of the shielding wall of the area to be monitored meets the requirements.
[0023] In a possible implementation, the verifying whether the thickness of the shielding wall of the area to be monitored meets the requirements based on the second dose rate control value includes:
[0024] Calculate the dose rate difference between the second dose rate control value and the first dose rate control value;
[0025] When the difference in dose rates belongs to the second preset range, it is determined that the thickness of the protective wall of the area to be monitored meets the requirements.
[0026] In a second aspect, the present disclosure provides a device for determining the thickness of a protective wall, including:
[0027] A data acquisition module, configured to acquire radiation protection design parameters of an area to be monitored; wherein, the radiation protection design parameters include data on the type of material of the protective wall to be used and data on the nuclide category;
[0028] A corresponding relationship acquisition module, configured to acquire the corresponding relationship between preset protection parameters and nuclear parameters;
[0029] A nuclear parameter determination module, configured to determine target nuclear parameters corresponding to the data on the type of material of the protective wall to be used and the data on the nuclide category according to the corresponding relationship between the preset protection parameters and the nuclear parameters;
[0030] A thickness calculation module, configured to calculate the thickness of the protective wall of the area to be monitored based on the radiation protection design parameters and the target nuclear parameters;
[0031] A thickness output module, configured to output the thickness of the protective wall of the area to be monitored.
[0032] In a third aspect, the present disclosure provides an electronic device, including:
[0033] A processor;
[0034] A memory for storing instructions executable by the processor;
[0035] Wherein, the processor is configured to execute the instructions to implement the method for determining the thickness of the protective wall according to the first aspect.
[0036] In a fourth aspect, the present disclosure provides a computer-readable storage medium, on which a computer program is stored, characterized in that when the computer program is executed by a processor, the method for determining the thickness of the protective wall according to the first aspect is implemented.
[0037] In a fifth aspect, the present disclosure provides a computer program product, including computer programs / instructions, characterized in that when the computer programs / instructions are executed by a processor, the method for determining the thickness of the protective wall according to the first aspect is implemented.
[0038] The technical solutions disclosed in the present disclosure at least bring the following beneficial effects:
[0039] In an embodiment of the present disclosure, by obtaining the radiation protection design parameters of the area to be monitored; wherein, the radiation protection design parameters include the material type data and nuclide category data of the proposed protective wall; obtaining the corresponding relationship between the preset protection parameters and the nuclear parameters; determining the target nuclear parameters corresponding to the material type data and nuclide category data of the proposed protective wall according to the corresponding relationship between the preset protection parameters and the nuclear parameters; calculating the thickness of the protective wall of the area to be monitored based on the radiation protection design parameters and the target nuclear parameters; and outputting the thickness of the protective wall of the area to be monitored. In this way, the automatic calculation and programmed calculation of the thickness of the protective wall of the area to be monitored can be realized, thereby effectively improving the calculation efficiency and accuracy of the thickness of the protective wall of the area to be monitored.
[0040] It should be understood that the above general description and the following detailed description are only exemplary and explanatory, and cannot limit the present disclosure. BRIEF DESCRIPTION OF THE DRAWINGS
[0041] The drawings herein are incorporated into the specification and constitute a part of this specification, showing embodiments consistent with the present disclosure, and are used together with the specification to explain the principles of the present disclosure and do not constitute an improper limitation to the present disclosure.
[0042] Figure 1 It is a schematic flow chart of a method for determining the thickness of a protective wall provided by an embodiment of the present disclosure;
[0043] Figure 2 It is a schematic structural diagram of a device for determining the thickness of a protective wall provided by an embodiment of the present disclosure;
[0044] Figure 3 It is a schematic structural diagram of an electronic device provided by an embodiment of the present disclosure. DETAILED DESCRIPTION OF THE EMBODIMENTS
[0045] In order to enable those of ordinary skill in the art to better understand the technical solutions of the present disclosure, the technical solutions in the embodiments of the present disclosure will be clearly and completely described below with reference to the accompanying drawings.
[0046] It should be noted that the terms "first", "second", etc. in the specification and claims of the present disclosure and the above drawings are used to distinguish similar objects and do not necessarily need to describe a specific order or sequence. It should be understood that such data used can be interchanged under appropriate circumstances so that the embodiments of the present disclosure described herein can be implemented in an order other than those illustrated or described herein. The embodiments described in the following exemplary embodiments do not represent all embodiments consistent with the present disclosure. On the contrary, they are only examples of devices and methods consistent with some aspects of the present disclosure as detailed in the appended claims.
[0047] It should be noted that the information (including but not limited to user device information, user personal information, etc.), data (including but not limited to data for analysis, stored data, displayed data, etc.) and signals involved in this disclosure are all authorized by the user or fully authorized by all parties, and the collection, use and processing of relevant data need to comply with the relevant laws, regulations and standards of relevant countries and regions.
[0048] In the technical solution of this disclosure, the acquisition, storage, use, processing, etc. of data all comply with the relevant provisions of national laws and regulations.
[0049] It should be noted that in the embodiments of this disclosure, there may be existing solutions in the industry for certain software, components, models, etc. They should be regarded as exemplary, and their purpose is only to illustrate the feasibility in the implementation of the technical solution of this disclosure, but it does not mean that the applicant has already or necessarily used this solution.
[0050] The following will, with reference to the accompanying drawings, detail the technical solutions provided by the embodiments of this disclosure.
[0051] Figure 1 It is a flowchart of a method for determining the thickness of a protective wall provided by an embodiment of this disclosure. As Figure 1 shown, the method for determining the thickness of a protective wall may include the following steps:
[0052] S101, obtain the radiation protection design parameters of the area to be monitored.
[0053] Among them, the radiation protection design parameters may include the data of the material type of the proposed protective wall and the data of the nuclide category.
[0054] In the embodiments of this disclosure, when determining the thickness of the protective wall of a certain monitoring area (i.e., the area to be monitored), the radiation protection design parameters of the area to be monitored may be obtained first. Exemplarily, obtaining the radiation protection design parameters of the area to be monitored may include obtaining the data of the material type of the proposed protective wall in the area to be monitored. The data of the material type of the proposed protective wall may be the shielding material used for the protective wall, such as lead material, brick material, concrete, etc.; and, obtaining the data of the nuclide category in the area to be monitored. The data of the nuclide category may be used to indicate the nuclide category used by the user (such as the patient), such as iodine - 131, technetium - 99, fluorine - 18, etc. It can be understood that the area to be monitored may be, for example, the monitoring area in the nuclear medicine department; the specific data of the radiation protection design parameters may be input by the staff. For example, it may be input through the user interface.
[0055] S102, obtain the corresponding relationship between the preset protection parameters and the nuclear parameters.
[0056] In an embodiment of the present disclosure, after obtaining the radiation protection design parameters of the area to be monitored, the corresponding relationship between the preset protection parameters and the nuclear parameters can be obtained. For example, it can be the corresponding relationship between the data of the material type of the protective wall to be adopted and the nuclide category data, and the nuclear parameters (such as TVL and Γ). The corresponding relationship between the preset protection parameters and the nuclear parameters can be preset and stored in the database. Specific examples can be seen in Table 1. Referring to Table 1, the nuclear parameters corresponding to different protective materials may be the same or different.
[0057] In a further possible implementation, the radiation protection design parameters may further include the nuclide usage dose data. The nuclide usage dose data may include the maximum activity A of the radiation source used. The value range of the maximum activity A of the radiation source used is generally provided by the nuclear medicine department. The values of the maximum activity A of the radiation source used by the nuclear medicine department in different usage scenarios are different. Specific examples can be seen in Table 1. The target nuclear parameters may include TVL (tenth value layer thickness) and Γ (ambient dose equivalent rate constant).
[0058] Table 1
[0059]
[0060] S103. According to the corresponding relationship between the preset protection parameters and the nuclear parameters, determine the target nuclear parameters corresponding to the data of the material type of the protective wall to be adopted and the nuclide category data.
[0061] In an embodiment of the present disclosure, after obtaining the corresponding relationship between the preset protection parameters and the nuclear parameters, based on this corresponding relationship, the nuclear parameters corresponding to the data of the material type of the protective wall to be adopted and the nuclide category data can be determined, that is, the target nuclear parameters. Exemplarily, according to the corresponding relationship between the preset protection parameters and the nuclear parameters, the target nuclear parameters corresponding to the data of the material type of the protective wall to be adopted and the nuclide category data can be found in the corresponding relationship between the preset protection parameters and the nuclear parameters. As an example, taking the data of the material type of the protective wall to be adopted as concrete and the nuclide category data as technetium-99, in combination with the corresponding relationship between the preset protection parameters and the nuclear parameters shown in Table 1, the target nuclear parameters can be found to be TVL = 110 and Γ = 0.0303.
[0062] S104. Based on the radiation protection design parameters and the target nuclear parameters, calculate the thickness of the protective wall of the area to be monitored.
[0063] In an embodiment of the present disclosure, after determining the target nuclear parameters corresponding to the material type data and nuclide category data of the proposed protective wall, the thickness of the protective wall can be automatically calculated based on the radiation protection design parameters and the target nuclear parameters, that is, the thickness of the protective wall in the area to be monitored. In this way, the programmed calculation of the thickness of the protective wall in the area to be monitored can be realized. As an example, the radiation protection design parameters may further include a dose rate control value (i.e., the first dose rate control value) and the distance between the reference point and the radiation source (i.e., the distance between the first reference point and the radiation source). Among them, the dose rate control value can be the upper limit value of the radiation dose rate set to ensure the safety of personnel in the nuclear medicine workplace. For example, the ambient dose equivalent rate control target value at a distance of 0.3 meters from the outer surface of the shield outside the nuclear medicine control area should not be greater than 2.5 μSv / h; the distance between the reference point and the radiation source can refer to the distance from the radiation source to the point of interest (i.e., the point where the dose rate needs to be controlled) in the nuclear medicine shielding calculation. In practical applications, for the sake of simplicity in calculation, a standard distance is usually taken, such as 1 meter. It can be understood that common nuclide types, usage dose ranges, wall material types, and their radiation shielding performance data can also be stored for the convenience of users to select and refer to.
[0064] As an example, the calculation method of the thickness of the protective wall in the area to be monitored can be seen in formula (1).
[0065]
[0066] Where x represents the thickness of the protective wall in the area to be monitored; TVL represents the tenth-value layer thickness of gamma rays, with the unit of millimeters (mm); A represents the nuclide usage dose data including the maximum activity of the radiation source used, and the unit can be megabecquerel (MBq); Γ represents the ambient dose equivalent rate constant, such as the ambient dose equivalent rate constant at a distance of 1m, with the unit of uSvm 2 / MBq . h; H p represents the first dose rate control value, that is, the dose rate control value at the point of interest outside the shield, with the unit of microsievert per hour uSv / h; r represents the distance between the first reference point and the radiation source, with the unit of meter.
[0067] S105, output the thickness of the protective wall in the area to be monitored.
[0068] In an embodiment of the present disclosure, after calculating the thickness of the protective wall of the area to be monitored, the thickness of the protective wall of the determined area to be monitored can be output. For example, the thickness of the protective wall of the area to be monitored can be displayed through a user interface so that relevant personnel can view the thickness of the protective wall of the area to be monitored and set the protective wall of the area to be monitored based on the thickness of the protective wall of the area to be monitored. It can be understood that other methods can also be used to output the thickness of the protective wall of the area to be monitored, such as sending the thickness of the protective wall of the area to be monitored to the electronic devices of relevant personnel via text messages, emails, etc.
[0069] In an embodiment of the present disclosure, by obtaining the radiation protection design parameters of the area to be monitored; wherein, the radiation protection design parameters include the material type data of the protective wall to be used and the nuclide category data; obtaining the corresponding relationship between the preset protection parameters and the nuclear parameters; according to the corresponding relationship between the preset protection parameters and the nuclear parameters, determining the target nuclear parameters corresponding to the material type data and the nuclide category data of the protective wall to be used; based on the radiation protection design parameters and the target nuclear parameters, calculating the thickness of the protective wall of the area to be monitored; outputting the thickness of the protective wall of the area to be monitored. In this way, automatic calculation and programmed calculation of the thickness of the protective wall of the area to be monitored can be realized, thereby effectively improving the calculation efficiency and accuracy of the thickness of the protective wall of the area to be monitored.
[0070] In some possible implementation manners, after outputting the thickness of the protective wall of the area to be monitored, at least one of the following is further included:
[0071] Calculating the distance between the second reference point and the radiation source according to the thickness of the protective wall of the area to be monitored; verifying whether the thickness of the protective wall of the area to be monitored meets the requirements based on the distance between the second reference point and the radiation source
[0072] Calculating the second dose rate control value according to the distance between the second reference point and the radiation source and the thickness of the protective wall of the area to be monitored; verifying whether the thickness of the protective wall of the area to be monitored meets the requirements based on the second dose rate control value.
[0073] In an embodiment of the present disclosure, it is also possible to perform reverse verification on the thickness of the protective wall of the area to be monitored. Exemplarily, based on the thickness of the protective wall of the area to be monitored, the distance between a reference point for verification and the radiation source can be calculated, that is, the distance between the second reference point and the radiation source. Then, based on the distance between the second reference point and the radiation source, the thickness of the protective wall of the area to be monitored can be verified to determine whether the thickness of the protective wall of the area to be monitored meets the requirements. Alternatively, based on the calculated distance between the second reference point and the radiation source and the thickness of the protective wall of the area to be monitored, a dose rate control value for verification can be calculated, that is, the second dose rate control value. Thereafter, based on the second dose rate control value, the thickness of the protective wall of the area to be monitored can be verified to determine whether the thickness of the protective wall of the area to be monitored meets the requirements. In this way, the accuracy of the thickness of the protective wall of the area to be monitored can be further improved.
[0074] In a further possible implementation, the radiation protection design parameter further includes a first dose rate control value.
[0075] Calculating the distance between the second reference point and the radiation source according to the thickness of the protective wall of the area to be monitored includes:
[0076] Calculating the distance between the second reference point and the radiation source according to the target nuclear parameter, nuclide category data, nuclide usage dose data, material type data of the adopted protective wall, the first dose rate control value, and the thickness of the protective wall of the area to be monitored;
[0077] Calculating the second dose rate control value according to the distance between the second reference point and the radiation source and the thickness of the protective wall of the area to be monitored includes:
[0078] Calculating the second dose rate control value according to the target nuclear parameter, nuclide category data, nuclide usage dose data, material type data of the adopted protective wall, the thickness of the protective wall of the area to be monitored, and the distance between the second reference point and the radiation source.
[0079] In an embodiment of the present disclosure, when calculating the distance between the second reference point and the radiation source according to the thickness of the protective wall of the area to be monitored, the target nuclear parameter, nuclide category data, nuclide usage dose data, material type data of the protective wall used, the first dose rate control value, and the thickness of the protective wall of the area to be monitored can be obtained, and then based on the target nuclear parameter, nuclide category data, nuclide usage dose data, material type data of the protective wall used, the first dose rate control value, and the thickness of the protective wall of the area to be monitored, the distance between the second reference point and the radiation source is calculated in reverse. This calculation method is similar to the related art. Similarly, when calculating the second dose rate control value according to the distance between the second reference point and the radiation source and the thickness of the protective wall of the area to be monitored, it may be to first obtain the target nuclear parameter, nuclide category data, nuclide usage dose data, material type data of the protective wall used, the thickness of the protective wall of the area to be monitored, and the distance between the second reference point and the radiation source, and then based on the target nuclear parameter, nuclide category data, nuclide usage dose data, material type data of the protective wall used, the thickness of the protective wall of the area to be monitored, and the distance between the second reference point and the radiation source, the second dose rate control value is calculated in reverse.
[0080] In a further possible implementation manner, the radiation protection design parameter further includes the distance between the first reference point and the radiation source.
[0081] Based on the distance between the second reference point and the radiation source, verifying whether the thickness of the protective wall of the area to be monitored meets the requirements includes:
[0082] Calculating the distance difference between the distance between the second reference point and the radiation source and the distance between the first reference point and the radiation source;
[0083] When the distance difference belongs to the first preset range, it is determined that the thickness of the protective wall of the area to be monitored meets the requirements.
[0084] In an embodiment of the present disclosure, the thickness of the protective wall of the area to be monitored can be verified by means of the difference. Exemplarily, when verifying whether the thickness of the protective wall of the area to be monitored meets the requirements based on the distance between the second reference point and the radiation source, the distance difference between the distance between the second reference point and the radiation source and the distance between the first reference point and the radiation source can be calculated. Then, the distance difference between the distance between the second reference point and the radiation source and the distance between the first reference point and the radiation source can be compared with the first preset range to determine whether the distance difference between the distance between the second reference point and the radiation source and the distance between the first reference point and the radiation source belongs to the first preset range. If the distance difference between the distance between the second reference point and the radiation source and the distance between the first reference point and the radiation source belongs to the first preset range, it can be considered that the thickness of the protective wall of the area to be monitored meets the requirements and the verification passes.
[0085] In a further possible implementation, based on the second dose rate control value, verify whether the thickness of the protective wall of the area to be monitored meets the requirements, including:
[0086] Calculate the dose rate difference between the second dose rate control value and the first dose rate control value;
[0087] When the dose rate difference belongs to the second preset range, determine that the thickness of the protective wall of the area to be monitored meets the requirements.
[0088] In the embodiments of the present disclosure, when verifying whether the thickness of the protective wall of the area to be monitored meets the requirements based on the second dose rate control value, the dose rate difference between the second dose rate control value and the first dose rate control value can be calculated. Then, the dose rate difference between the second dose rate control value and the first dose rate control value can be compared with the second preset range to determine whether the dose rate difference between the second dose rate control value and the first dose rate control value belongs to the second preset range. If the dose rate difference between the second dose rate control value and the first dose rate control value belongs to the second preset range, it can be considered that the thickness of the protective wall of the area to be monitored meets the requirements and the verification passes.
[0089] It can be understood that the first preset range and the second preset range can be set according to the actual situation. For the case where the verification fails, the thickness of the protective wall of the area to be monitored can be recalculated, and the verification process of the thickness of the protective wall of the area to be monitored can be carried out until the verification passes.
[0090] To make the method for determining the thickness of the protective wall provided by the embodiments of the present disclosure clearer, the following is illustrated with specific examples, as follows:
[0091] Obtain the nuclide category data, nuclide usage dose data, data of the material type of the protective wall to be adopted (i.e., shielding material), the first dose rate control value Hp, and the distance r between the first reference point and the radiation source;
[0092] According to the target nuclear parameters, nuclide category data, nuclide usage dose data, data of the material type of the protective wall to be adopted, the first dose rate control value Hp, and the distance r between the first reference point and the radiation source, obtain the thickness x of the radiation protection wall for the nuclear medicine department.
[0093] Among them, the radionuclide category data can be used to indicate the radionuclide category used by the patient. For example, iodine-131, technetium-99, fluorine-18, etc. The radionuclide usage dose data can be the maximum activity A of the radiation source used. The numerical range of the maximum activity A of the radiation source used is generally provided by the nuclear medicine department, and the value of the maximum activity A of the radiation source used by the nuclear medicine department in different usage scenarios is different. The target nuclear parameters can include: TVL (tenth value layer thickness), Γ (ambient dose equivalent rate constant). The data of the material type of the proposed protective wall can include lead material, brick material, concrete, etc. Under different radionuclide categories, the target nuclear parameters corresponding to different material types of the protective wall are different.
[0094] In addition, the radiation protection wall design for the nuclear medicine department can also be carried out according to the thickness of the radiation protection wall used in the nuclear medicine department. Exemplarily, when the decoration of the radiation protection wall is completed, the radiation protection performance of the radiation protection wall can be tested according to the decorated radiation protection wall. Specifically as follows:
[0095] According to the target nuclear parameters, radionuclide category data, radionuclide usage dose data, data of the material type of the adopted protective wall, dose rate control value Hp, and the thickness x of the radiation protection wall of the nuclear medicine department, the distance r between the reference point and the radiation source is obtained; or,
[0096] According to the target nuclear parameters, radionuclide category data, radionuclide usage dose data, data of the material type of the adopted protective wall, the thickness x of the radiation protection wall of the nuclear medicine department, and the distance r between the reference point and the radiation source, the dose rate control value Hp is obtained.
[0097] Among them, the distance r between the reference point and the radiation source and the dose rate control value Hp can be used to verify whether the design of the radiation protection wall of the nuclear medicine department meets the national standard requirements.
[0098] Correspondingly, the above method for determining the thickness of the protective wall can be implemented depending on the thickness determination system of the protective wall. The thickness determination system of the protective wall can include:
[0099] User interface: used to provide a friendly graphical user interface, allowing users to input radiation protection design parameters, such as radionuclide category, usage dose, wall material type and other parameters, and display the calculation results;
[0100] Calculation engine: built-in calculation formulas, which can calculate according to the radiation protection design parameters input by the user to obtain the required thickness of the protective wall;
[0101] Verification module: supports the inspection unit to verify in reverse whether the protection measures meet the standard requirements according to the parameters and wall thickness provided by the user;
[0102] Database: It is used to store data on common nuclide types, usage dose ranges, wall material types, and their radiation shielding performance, facilitating user selection and reference.
[0103] The operation process of the thickness determination system for the protective wall is briefly described as follows:
[0104] The user inputs the radiation protection design parameters mainly used in the nuclear medicine department through the user interface, such as parameters like nuclide category, usage dose, and the material type of the proposed protective wall.
[0105] The calculation engine calls the built-in complex calculation formula for calculation based on the parameters input by the user.
[0106] The calculation result is displayed to the user through the user interface, including the required thickness of the protective wall.
[0107] The inspection unit can use the verification module to perform reverse verification based on the parameters and wall thickness provided by the user.
[0108] The specific implementation and technical effects of each step in this embodiment are similar to those in the above method embodiment, and will not be elaborated here.
[0109] Based on the same inventive concept, the embodiments of the present disclosure also provide a device for determining the thickness of a protective wall. As Figure 2 shown, the device 200 for determining the thickness of the protective wall includes:
[0110] A data acquisition module 210, configured to acquire the radiation protection design parameters of the area to be monitored; wherein, the radiation protection design parameters include data on the material type of the proposed protective wall and nuclide category data;
[0111] A corresponding relationship acquisition module 220, configured to acquire the corresponding relationship between preset protection parameters and nuclear parameters;
[0112] A nuclear parameter determination module 230, configured to determine the target nuclear parameters corresponding to the data on the material type of the proposed protective wall and nuclide category data according to the corresponding relationship between the preset protection parameters and nuclear parameters;
[0113] A thickness calculation module 240, configured to calculate the thickness of the protective wall of the area to be monitored based on the radiation protection design parameters and the target nuclear parameters;
[0114] A thickness output module 250, configured to output the thickness of the protective wall of the area to be monitored.
[0115] In a possible implementation manner, the radiation protection design parameters further include nuclide usage dose data, and the nuclide usage dose data includes the maximum activity of the radiation source used; the target nuclear parameters include the tenth-value layer thickness TVL and the ambient dose equivalent rate constant Γ.
[0116] In a possible implementation manner, the thickness determination device 200 of the protective wall further includes at least one of the following:
[0117] The first verification module is configured to calculate the distance between the second reference point and the radiation source according to the thickness of the protective wall in the area to be monitored; and verify whether the thickness of the protective wall in the area to be monitored meets the requirements based on the distance between the second reference point and the radiation source.
[0118] The second verification module is configured to calculate a second dose rate control value according to the distance between the second reference point and the radiation source and the thickness of the protective wall in the area to be monitored; and verify whether the thickness of the protective wall in the area to be monitored meets the requirements based on the second dose rate control value.
[0119] In a possible implementation manner, the radiation protection design parameters further include a first dose rate control value;
[0120] The first verification module includes:
[0121] The first calculation unit is configured to calculate the distance between the second reference point and the radiation source according to the target nuclear parameters, the nuclide category data, the nuclide usage dose data, the material type data of the protective wall to be adopted, the first dose rate control value, and the thickness of the protective wall in the area to be monitored.
[0122] The second verification module includes:
[0123] The second calculation unit is configured to calculate the second dose rate control value according to the target nuclear parameters, the nuclide category data, the nuclide usage dose data, the material type data of the protective wall to be adopted, the thickness of the protective wall in the area to be monitored, and the distance between the second reference point and the radiation source.
[0124] In a possible implementation manner, the radiation protection design parameters further include the distance between the first reference point and the radiation source;
[0125] The first verification module includes:
[0126] The third calculation unit is configured to calculate the distance difference between the distance between the second reference point and the radiation source and the distance between the first reference point and the radiation source.
[0127] The first verification unit is configured to determine that the thickness of the protective wall of the area to be monitored meets the requirements when the distance difference belongs to a first preset range.
[0128] In a possible implementation manner, the second verification module includes:
[0129] The fourth calculation unit is configured to calculate the dose rate difference between the second dose rate control value and the first dose rate control value;
[0130] The second verification unit is configured to determine that the thickness of the protective wall of the area to be monitored meets the requirements when the dose rate difference belongs to a second preset range.
[0131] The specific implementation manners and technical effects of the device provided by the embodiments of the present disclosure are similar to those of the above method embodiments, and will not be elaborated herein.
[0132] According to the embodiments of the present disclosure, the present disclosure also discloses an electronic device, a computer-readable storage medium, and a computer program product.
[0133] Figure 3 FIG. shows a schematic block diagram of an exemplary electronic device 300 that can be used to implement the embodiments of the present disclosure. The electronic device 300 is intended to represent various forms of digital computers, such as, a laptop computer, a desktop computer, a workbench, a personal digital assistant, a server, a blade server, a mainframe computer, and other suitable computers. The electronic device can also represent various forms of mobile devices, such as, a personal digital processor, a cellular phone, a smart phone, a wearable device, and other similar computing devices. The components shown herein, their connections and relationships, and their functions are merely exemplary and are not intended to limit the implementation of the present disclosure described and / or claimed herein.
[0134] As Figure 3 shown, the electronic device 300 includes a computing unit 301, which can perform various appropriate actions and processes according to the computer program stored in the read-only memory (ROM) 302 or the computer program loaded from the storage unit 308 into the random access memory (RAM) 303. In the RAM 303, various programs and data required for the operation of the device 300 can also be stored. The computing unit 301, the ROM 302, and the RAM 303 are connected to each other through a bus 304. The input / output (I / O) interface 305 is also connected to the bus 304.
[0135] Multiple components in the electronic device 300 are connected to the I / O interface 305, including: an input unit 306, such as a keyboard, a mouse, etc.; an output unit 307, such as various types of displays, speakers, etc.; a storage unit 308, such as a disk, an optical disc, etc.; and a communication unit 309, such as a network card, a modem, a wireless communication transceiver, etc. The communication unit 309 allows the electronic device 300 to exchange information / data with other devices via a computer network such as the Internet and / or various telecommunication networks.
[0136] The computing unit 301 can be various general-purpose and / or special-purpose processing components with processing and computing capabilities. Some examples of the computing unit 301 include but are not limited to a central processing unit (CPU), a graphics processing unit (GPU), various dedicated artificial intelligence (AI) computing chips, various computing units running machine learning model algorithms, a digital signal processor (DSP), and any suitable processor, controller, microcontroller, etc. The computing unit 301 executes the various methods and processes described above, such as the method for determining the thickness of the protective wall. For example, in some embodiments, the method for determining the thickness of the protective wall can be implemented as a computer software program, which is tangibly contained in a machine-readable medium, such as the storage unit 308. In some embodiments, part or all of the computer program can be loaded and / or installed onto the electronic device 300 via the ROM 302 and / or the communication unit 309. When the computer program is loaded into the RAM 303 and executed by the computing unit 301, one or more steps of the method for determining the thickness of the protective wall described above can be executed. Alternatively, in other embodiments, the computing unit 301 can be configured to execute the method for determining the thickness of the protective wall in any other suitable manner (e.g., by means of firmware).
[0137] The various embodiments of the systems and technologies described above in this document can be implemented in digital electronic circuit systems, integrated circuit systems, field-programmable gate arrays (FPGAs), application-specific integrated circuits (ASICs), application-specific standard products (ASSPs), systems-on-a-chip (SOCs), complex programmable logic devices (CPLDs), computer hardware, firmware, software, and / or combinations thereof. These various embodiments can include: being implemented in one or more computer programs, which can be executed and / or interpreted on a programmable system including at least one programmable processor, and the programmable processor can be a special or general-purpose programmable processor, and can receive data and instructions from a storage system, at least one input device, and at least one output device, and transmit the data and instructions to the storage system, the at least one input device, and the at least one output device.
[0138] The program code of a computer program product for implementing the methods of the present disclosure may be written in any combination of one or more programming languages. These program codes may be provided to a processor or controller of a general-purpose computer, a special-purpose computer, or other programmable data processing device, such that when executed by the processor or controller, the program codes cause the functions / operations specified in the flowchart and / or block diagram to be implemented. The program code may be executed entirely on the machine, partially on the machine, as a stand-alone software package partially on the machine and partially on a remote machine, or entirely on a remote machine or server.
[0139] In the context of the present disclosure, a computer-readable storage medium may be a tangible medium that can contain or store a program for use by or in connection with an instruction execution system, apparatus, or device. A computer-readable storage medium may be a machine-readable signal medium or a machine-readable storage medium. A computer-readable storage medium may include, but is not limited to, electronic, magnetic, optical, electromagnetic, infrared, or semiconductor systems, apparatus, or devices, or any suitable combination of the foregoing. More specific examples of a computer-readable storage medium would include an electrical connection based on one or more wires, a portable computer disk, a hard disk, a random access memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or Flash memory), an optical fiber, a portable compact disc read-only memory (CD-ROM), an optical storage device, a magnetic storage device, or any suitable combination of the foregoing.
[0140] In order to provide interaction with a user, the systems and techniques described herein may be implemented on a computer having: a display device for displaying information to the user (e.g., a CRT (cathode ray tube) or LCD (liquid crystal display) monitor); and a keyboard and a pointing device (e.g., a mouse or a trackball) through which the user can provide input to the computer. Other kinds of devices may also be used to provide interaction with the user; for example, the feedback provided to the user may be any form of sensory feedback (e.g., visual feedback, auditory feedback, or tactile feedback); and input from the user may be received in any form (including acoustic input, voice input, or tactile input).
[0141] The systems and techniques described herein can be implemented in a computing system including backend components (e.g., as a data server), or a computing system including middleware components (e.g., an application server), or a computing system including frontend components (e.g., a user computer having a graphical user interface or a web browser through which a user can interact with an implementation of the systems and techniques described herein), or a computing system including any combination of such backend components, middleware components, or frontend components. The components of the system can be interconnected with each other by digital data communication in any form or medium (e.g., a communication network). Examples of communication networks include: local area network (LAN), wide area network (WAN), the Internet, and blockchain networks.
[0142] A computer system can include a client and a server. The client and the server are generally remote from each other and typically interact through a communication network. The client-server relationship is created by computer programs running on respective computers and having a client-server relationship with each other. The server can be a cloud server, also known as a cloud computing server or a cloud host, which is a host product in the cloud computing service system, solving the defects of difficult management and weak business scalability existing in traditional physical hosts and VPS services ("Virtual Private Server", or simply "VPS" for short). The server can also be a server of a distributed system, or a server combined with blockchain.
[0143] It should be understood that various forms of the processes shown above can be used, with steps reordered, added, or deleted. For example, the steps recited in this disclosure can be executed in parallel, sequentially, or in a different order, as long as the desired results of the technical solutions disclosed in this disclosure can be achieved, and no limitation is imposed herein.
[0144] The above specific embodiments do not constitute a limitation on the protection scope of this disclosure. Those skilled in the art should understand that various modifications, combinations, sub-combinations, and substitutions can be made according to design requirements and other factors. Any modifications, equivalent substitutions, and improvements made within the spirit and principles of this disclosure shall be included within the protection scope of this disclosure.
Claims
1. A method for determining the thickness of a protective wall, characterized in that, Including: Obtain the radiation protection design parameters of the area to be monitored; wherein, the radiation protection design parameters include the material type data of the proposed shielding wall and the nuclide category data; Obtain the corresponding relationship between the preset protection parameters and the nuclear parameters; According to the corresponding relationship between the preset protection parameters and the nuclear parameters, determine the target nuclear parameters corresponding to the material type data of the proposed shielding wall and the nuclide category data; Based on the radiation protection design parameters and the target nuclear parameters, calculate the thickness of the shielding wall of the area to be monitored; Output the thickness of the shielding wall of the area to be monitored.
2. The method for determining the thickness of the protective wall according to claim 1, characterized in that The radiation protection design parameters further include nuclide usage dose data, and the nuclide usage dose data includes the maximum activity of the radiation source used; the target nuclear parameters include the tenth value layer thickness TVL and the ambient dose equivalent rate constant Γ.
3. The method for determining the thickness of the protective wall according to claim 1, characterized in that After outputting the thickness of the shielding wall of the area to be monitored, at least one of the following is further included: Calculate the distance between the second reference point and the radiation source according to the thickness of the shielding wall of the area to be monitored; based on the distance between the second reference point and the radiation source, verify whether the thickness of the shielding wall of the area to be monitored meets the requirements; Calculate the second dose rate control value according to the distance between the second reference point and the radiation source and the thickness of the shielding wall of the area to be monitored; based on the second dose rate control value, verify whether the thickness of the shielding wall of the area to be monitored meets the requirements.
4. The method for determining the thickness of the protective wall according to claim 3, characterized in that, The radiation protection design parameters further include a first dose rate control value; The calculating the distance between the second reference point and the radiation source according to the thickness of the shielding wall of the area to be monitored includes: Calculate the distance between the second reference point and the radiation source according to the target nuclear parameters, the nuclide category data, the nuclide usage dose data, the material type data of the proposed shielding wall, the first dose rate control value, and the thickness of the shielding wall of the area to be monitored; The calculating the second dose rate control value according to the distance between the second reference point and the radiation source and the thickness of the shielding wall of the area to be monitored includes: Calculate the second dose rate control value according to the target nuclear parameters, the nuclide category data, the nuclide usage dose data, the material type data of the proposed shielding wall, the thickness of the shielding wall of the area to be monitored, and the distance between the second reference point and the radiation source.
5. The method for determining the thickness of the protective wall according to claim 3 or 4, characterized in that The radiation protection design parameters further include the distance between the first reference point and the radiation source; The verifying whether the thickness of the shielding wall of the area to be monitored meets the requirements based on the distance between the second reference point and the radiation source includes: Calculate the distance difference between the distance between the second reference point and the radiation source and the distance between the first reference point and the radiation source; When the distance difference is within the first preset range, determine that the thickness of the shielding wall of the area to be monitored meets the requirements.
6. The method for determining the thickness of the protective wall according to claim 3 or 4, characterized in that, The verifying whether the thickness of the shielding wall of the area to be monitored meets the requirements based on the second dose rate control value includes: Calculate the dose rate difference between the second dose rate control value and the first dose rate control value; When the difference in dose rates belongs to the second preset range, it is determined that the thickness of the protective wall of the area to be monitored meets the requirements.
7. A device for determining the thickness of a protective wall, characterized in that It includes: A data acquisition module, configured to acquire radiation protection design parameters of the area to be monitored; wherein, the radiation protection design parameters include data on the material type of the protective wall to be used and data on nuclide categories; A correspondence acquisition module, configured to acquire the correspondence between preset protection parameters and nuclear parameters; A nuclear parameter determination module, configured to determine the target nuclear parameters corresponding to the data on the material type of the protective wall to be used and the data on nuclide categories according to the correspondence between the preset protection parameters and the nuclear parameters; A thickness calculation module, configured to calculate the thickness of the protective wall of the area to be monitored based on the radiation protection design parameters and the target nuclear parameters; A thickness output module, configured to output the thickness of the protective wall of the area to be monitored.
8. An electronic device, characterized in that, It includes: A processor; A memory for storing instructions executable by the processor; Wherein, the processor is configured to execute the instructions to implement the method for determining the thickness of the protective wall according to any one of claims 1-6.
9. A computer-readable storage medium having a computer program stored thereon, characterized in that, When the computer program is executed by the processor, it implements the method for determining the thickness of the protective wall according to any one of claims 1-6.
10. A computer program product comprising a computer program / instructions, characterized in that, When the computer program / instructions are executed by the processor, it implements the method for determining the thickness of the protective wall according to any one of claims 1-6.