Radiation monitoring method and system based on data processing

Abstract

The application provides a radiation monitoring method and system based on data processing. The method comprises the following steps: obtaining radiation detection values of each radiation detection sensor in an internal radiation detection sensor sequence to form an internal radiation detection value sequence, and obtaining radiation detection values of each radiation detection sensor in an external radiation detection sensor sequence to form an external radiation detection value sequence; then, determining an external radiation reference value sequence according to the internal radiation detection value sequence and a preset radiation attenuation model; and determining a radiation safety level of a space to be monitored according to the external radiation reference value sequence and the external radiation detection value sequence, and monitoring the radiation protection performance of the space to be monitored to ensure the protection reliability of the space to be monitored.

Description

Technical Field

[0001] This application relates to data processing technology, and more particularly to a radiation monitoring method and system based on data processing. Background Technology

[0002] Radiation monitoring is of great significance for human health, nuclear safety, environmental protection, radiation emergency response, and nuclear disarmament. It can provide accurate data and information to support scientific decision-making and effective risk management, thereby safeguarding social security and sustainable development.

[0003] By monitoring radiation levels, potential problems or accidents can be detected and identified in a timely manner, and necessary control measures can be taken to prevent the accident from escalating and radiation leakage from occurring. In existing technologies, radiation monitoring is typically conducted by deploying radiation detection sensors; when the detected radiation value is excessively high, a radiation accident is considered to have occurred.

[0004] However, in existing technologies, once a radiation accident is identified, it is usually assumed that the radiation source in the monitored space has gone out of control or that the monitored space has suffered a serious failure. This ignores the factor that the protective effect of the monitored space on the radiation source has been reduced due to long-term external environmental erosion. As a result, it is impossible to detect the initial failure of the monitored space in time, and thus to take timely remedial measures in the early stage when radiation exceeds the standard, so as to avoid the occurrence of a radiation accident. Summary of the Invention

[0005] This application provides a radiation monitoring method and system based on data processing to solve the technical problem of how to monitor the changes in the protective effect of the monitored space on radiation sources caused by long-term external environmental erosion.

[0006] In a first aspect, this application provides a radiation monitoring method based on data processing, applied to a radiation monitoring system. The system includes: an internal radiation detection sensor sequence, an external radiation detection sensor sequence, and a data processor. Each radiation detection sensor in the internal radiation detection sensor sequence and each radiation detector in the external radiation detection sensor sequence are respectively communicatively connected to the data processor. The internal radiation detection sensor sequence is distributed on the internal sidewall of the space to be monitored, and the external radiation detection sensor sequence is distributed on the external sidewall of the space to be monitored at positions corresponding to the radiation detectors in the internal radiation detection sensor sequence. The space to be monitored is used to place a radiation source. The method includes:

[0007] The radiation detection values ​​of each radiation detection sensor in the internal radiation detection sensor sequence are obtained to form an internal radiation detection value sequence.

[0008] Obtain the radiation detection values ​​of each radiation detection sensor in the external radiation detection sensor sequence to form an external radiation detection value sequence;

[0009] The external radiation reference value sequence is determined based on the internal radiation detection value sequence and the preset radiation attenuation model.

[0010] The radiation safety level of the space to be monitored is determined based on the external radiation reference value sequence and the external radiation detection value sequence.

[0011] Optionally, determining the external radiation reference value sequence based on the internal radiation detection value sequence and the preset radiation attenuation model includes:

[0012] According to the internal radiation detection numerical sequence The external radiation reference numerical sequence is determined by the preset radiation attenuation model. The preset radiation attenuation model includes Formula 1, which is:

[0013]

[0014] in, This represents the total number of radiation detection sensors in the internal radiation detection sensor sequence. The first in the internal radiation detection sensor sequence The radiation intensity value detected by each radiation detection sensor. This is the reference radiation intensity value after the rays penetrate the side wall of the space to be monitored. The mass absorption coefficient, The density of the material of the sidewall of the space to be monitored. The first on the side wall of the space to be monitored The thickness of the area where the radiation detection sensors are arranged.

[0015] Optionally, determining the radiation safety level of the space to be monitored based on the external radiation reference value sequence and the external radiation detection value sequence includes:

[0016] According to the external radiation reference value sequence and the external radiation detection numerical sequence Determine the numerical sequence of external radiation bias ,in, The determination is based on Formula 2, which is:

[0017]

[0018] According to the external radiation deviation numerical sequence And Formula 3 determines the value of the first characteristic. Formula 3 is:

[0019]

[0020] According to the external radiation deviation numerical sequence And Formula 4 determines the value of the second characteristic. Formula 4 is:

[0021]

[0022] in, The external radiation bias numerical sequence The total number of non-zero numerical elements in the neutron;

[0023] If the first feature value Less than or equal to a preset first feature threshold, and the second feature value If the radiation safety level of the space to be monitored is less than or equal to the preset second characteristic threshold, then the radiation safety level of the space to be monitored is the first radiation safety level.

[0024] If the first feature value The value is greater than a preset first feature threshold and less than a preset third feature threshold, and / or the value of the second feature. If the value is greater than or equal to the preset second feature threshold, then the equivalent feature value is determined according to Formula 5. Formula 5 is:

[0025]

[0026] in, , These are the first weight value and the second weight value, respectively. , All positive numbers ,and, The value is the same as the first feature value. The numerical values ​​are positively correlated;

[0027] If the equivalent characteristic value If the value of the equivalent feature is less than or equal to a preset fourth feature threshold, then the radiation safety level of the space to be monitored is the second radiation safety level; if the equivalent feature value is less than or equal to a preset fourth feature threshold, then the radiation safety level of the space to be monitored is the second radiation safety level. If the radiation level is greater than the preset fourth feature threshold, then the radiation safety level of the space to be monitored is the third radiation safety level.

[0028] If the first feature value If the radiation safety level of the space to be monitored is greater than or equal to the preset third characteristic threshold, then the radiation safety level of the space to be monitored is the fourth radiation safety level.

[0029] Optionally, if the radiation safety level of the space to be monitored is the fourth radiation safety level, then after determining the radiation safety level of the space to be monitored based on the external radiation reference value sequence and the external radiation detection value sequence, the method further includes:

[0030] Determine the subsequence of external radiation deviation values ​​that is greater than the preset third feature threshold in the external radiation deviation value sequence. The external radiation bias numerical subsequence The set of numerical elements belongs to the external radiation bias numerical sequence. The set of numerical elements, the external radiation bias numerical subsequence Including the external radiation deviation numerical sequence All numerical elements in the range that are greater than the preset third feature threshold;

[0031] According to the external radiation deviation numerical subsequence Determine the corresponding external radiation detection sensor subsequence;

[0032] The radiation protection level is determined based on the distribution of the external radiation detection sensor subsequence on the outer sidewall of the space to be monitored.

[0033] Optionally, determining the radiation protection level based on the distribution of the external radiation detection sensor sub-sequence on the outer sidewall of the space to be monitored includes:

[0034] If more than a preset proportion threshold of radiation detection sensors in the external radiation detection sensor subsequence are distributed on the outer sidewall of the target in the space to be monitored, then the radiation protection level is determined to be the first radiation protection level. The first radiation protection level is used to indicate that radiation protection enhancement is applied to the outer sidewall of the target.

[0035] If the distribution ratio of the external radiation detection sensor subsequence on each external sidewall is less than the preset ratio threshold, then the number of radiation detection sensors of the external radiation detection sensor subsequence on each external sidewall of the space to be monitored is determined, and the abnormal radiation detection sensor distribution sequence constituted by the number of radiation detection sensors of the external radiation detection sensor subsequence on each external sidewall of the space to be monitored is defined. ,in, For the external radiation detection sensor sub-sequence in the 1st... The number of radiation detection sensors distributed on the outer sidewalls, The number of external sidewalls of the space to be monitored;

[0036] Based on Formula 5 and the distribution sequence of abnormal radiation detection sensors Determine the characteristic value of the deviation in radiation anomaly distribution Formula 5 is:

[0037]

[0038] If the number of radiation detection sensors in the external radiation detection sensor sub-sequence exceeds a preset threshold, and the radiation anomaly distribution deviation characteristic value If the radiation protection level is less than or equal to a preset distribution deviation threshold, then the radiation protection level is determined to be the second radiation protection level. The second radiation protection level is used to indicate that all external sidewalls of the space to be monitored are subjected to overall radiation protection enhancement.

[0039] Optionally, after obtaining the radiation detection values ​​of each radiation detection sensor in the internal radiation detection sensor sequence to form an internal radiation detection value sequence, the method further includes:

[0040] According to the internal radiation detection numerical sequence And Formula 6 determines the internal radiation characteristic value. Formula 6 is:

[0041]

[0042] in, , These are the third and fourth weight values, respectively. , All positive numbers ,and, The value is the same as the stated The numerical values ​​are positively correlated;

[0043] If the internal radiation characteristic value If the radiation distribution deviation characteristic value is greater than the preset internal radiation threshold, the number of radiation detection sensors in the external radiation detection sensor sub-sequence exceeds the preset number threshold, and the radiation distribution deviation characteristic value is greater than the preset internal radiation threshold. If the radiation protection level is less than or equal to the preset distribution deviation threshold, then the radiation protection level is determined to be the third radiation protection level. The third radiation protection level is used to indicate that the overall radiation protection enhancement is carried out on each internal sidewall and each external sidewall of the space to be monitored.

[0044] Optionally, the system further includes: an indicator light, which is communicatively connected to the data processor; after determining the radiation safety level of the space to be monitored based on the external radiation reference value sequence and the external radiation detection value sequence, the system further includes:

[0045] The indicator light is controlled to display according to the corresponding color based on the radiation safety level, wherein the first radiation safety level corresponds to the first color, the second radiation safety level corresponds to the second color, the third radiation safety level corresponds to the third color, and the fourth radiation safety level corresponds to the fourth color.

[0046] Secondly, this application provides a radiation monitoring system, including: an internal radiation detection sensor sequence, an external radiation detection sensor sequence, and a data processor. Each radiation detection sensor in the internal radiation detection sensor sequence and each radiation detector in the external radiation detection sensor sequence are respectively communicatively connected to the data processor. The internal radiation detection sensor sequence is distributed on the internal sidewall of the space to be monitored, and the external radiation detection sensor sequence is distributed on the external sidewall of the space to be monitored at positions corresponding to each radiation detector in the internal radiation detection sensor sequence. A radiation source is placed in the space to be monitored.

[0047] The data processor is used to acquire the radiation detection values ​​of each radiation detection sensor in the internal radiation detection sensor sequence to form an internal radiation detection value sequence.

[0048] The data processor is also used to acquire the radiation detection values ​​of each radiation detection sensor in the external radiation detection sensor sequence to form an external radiation detection value sequence.

[0049] The data processor is also used to determine an external radiation reference value sequence based on the internal radiation detection value sequence and a preset radiation attenuation model.

[0050] The data processor is further configured to determine the radiation safety level of the space to be monitored based on the external radiation reference value sequence and the external radiation detection value sequence.

[0051] Optionally, the data processor is specifically used for:

[0052] According to the internal radiation detection numerical sequence The external radiation reference numerical sequence is determined by the preset radiation attenuation model. The preset radiation attenuation model includes Formula 1, which is:

[0053]

[0054] in, This represents the total number of radiation detection sensors in the internal radiation detection sensor sequence. The first in the internal radiation detection sensor sequence The radiation intensity value detected by each radiation detection sensor. This is the reference radiation intensity value after the rays penetrate the side wall of the space to be monitored. The mass absorption coefficient, The density of the material of the sidewall of the space to be monitored. The first on the side wall of the space to be monitored The thickness of the area where the radiation detection sensors are arranged.

[0055] Optionally, the data processor is specifically used for:

[0056] According to the external radiation reference value sequence and the external radiation detection numerical sequence Determine the numerical sequence of external radiation bias ,in, The determination is based on Formula 2, which is:

[0057]

[0058] According to the external radiation deviation numerical sequence And Formula 3 determines the value of the first characteristic. Formula 3 is:

[0059]

[0060] According to the external radiation deviation numerical sequence And Formula 4 determines the value of the second characteristic. Formula 4 is:

[0061]

[0062] in, The external radiation bias numerical sequence The total number of non-zero numerical elements in the neutron;

[0063] If the first feature value Less than or equal to a preset first feature threshold, and the second feature value If the radiation safety level of the space to be monitored is less than or equal to the preset second characteristic threshold, then the radiation safety level of the space to be monitored is the first radiation safety level.

[0064] If the first feature value The value is greater than a preset first feature threshold and less than a preset third feature threshold, and / or the value of the second feature. If the value is greater than or equal to the preset second feature threshold, then the equivalent feature value is determined according to Formula 5. Formula 5 is:

[0065]

[0066] in, , These are the first weight value and the second weight value, respectively. , All positive numbers ,and, The value is the same as the first feature value. The numerical values ​​are positively correlated;

[0067] If the equivalent characteristic value If the value of the equivalent feature is less than or equal to a preset fourth feature threshold, then the radiation safety level of the space to be monitored is the second radiation safety level; if the equivalent feature value is less than or equal to a preset fourth feature threshold, then the radiation safety level of the space to be monitored is the second radiation safety level. If the radiation level is greater than the preset fourth feature threshold, then the radiation safety level of the space to be monitored is the third radiation safety level.

[0068] If the first feature value If the radiation safety level of the space to be monitored is greater than or equal to the preset third characteristic threshold, then the radiation safety level of the space to be monitored is the fourth radiation safety level.

[0069] Optionally, the data processor is specifically used for:

[0070] Determine the subsequence of external radiation deviation values ​​that is greater than the preset third feature threshold in the external radiation deviation value sequence. The external radiation bias numerical subsequence The set of numerical elements belongs to the external radiation bias numerical sequence. The set of numerical elements, the external radiation bias numerical subsequence Including the external radiation deviation numerical sequence All numerical elements in the range that are greater than the preset third feature threshold;

[0071] According to the external radiation deviation numerical subsequence Determine the corresponding external radiation detection sensor subsequence;

[0072] The radiation protection level is determined based on the distribution of the external radiation detection sensor subsequence on the outer sidewall of the space to be monitored.

[0073] Optionally, the data processor is specifically used for:

[0074] If more than a preset proportion threshold of radiation detection sensors in the external radiation detection sensor subsequence are distributed on the outer sidewall of the target in the space to be monitored, then the radiation protection level is determined to be the first radiation protection level. The first radiation protection level is used to indicate that radiation protection enhancement is applied to the outer sidewall of the target.

[0075] If the distribution ratio of the external radiation detection sensor subsequence on each external sidewall is less than the preset ratio threshold, then the number of radiation detection sensors of the external radiation detection sensor subsequence on each external sidewall of the space to be monitored is determined, and the abnormal radiation detection sensor distribution sequence constituted by the number of radiation detection sensors of the external radiation detection sensor subsequence on each external sidewall of the space to be monitored is defined. ,in, For the external radiation detection sensor sub-sequence in the 1st... The number of radiation detection sensors distributed on the outer sidewalls, The number of external sidewalls of the space to be monitored;

[0076] Based on Formula 5 and the distribution sequence of abnormal radiation detection sensors Determine the characteristic value of the deviation in radiation anomaly distribution Formula 5 is:

[0077]

[0078] If the number of radiation detection sensors in the external radiation detection sensor sub-sequence exceeds a preset threshold, and the radiation anomaly distribution deviation characteristic value If the radiation protection level is less than or equal to a preset distribution deviation threshold, then the radiation protection level is determined to be the second radiation protection level. The second radiation protection level is used to indicate that all external sidewalls of the space to be monitored are subjected to overall radiation protection enhancement.

[0079] Optionally, the data processor is specifically used for:

[0080] According to the internal radiation detection numerical sequence And Formula 6 determines the internal radiation characteristic value. Formula 6 is:

[0081]

[0082] in, , These are the third and fourth weight values, respectively. , All positive numbers ,and, The value is the same as the stated The numerical values ​​are positively correlated;

[0083] If the internal radiation characteristic value If the radiation distribution deviation characteristic value is greater than the preset internal radiation threshold, the number of radiation detection sensors in the external radiation detection sensor sub-sequence exceeds the preset number threshold, and the radiation distribution deviation characteristic value is greater than the preset internal radiation threshold. If the radiation protection level is less than or equal to the preset distribution deviation threshold, then the radiation protection level is determined to be the third radiation protection level. The third radiation protection level is used to indicate that the overall radiation protection enhancement is carried out on each internal sidewall and each external sidewall of the space to be monitored.

[0084] Optionally, the system further includes: an indicator light, which is communicatively connected to the data processor; optionally, the data processor is specifically used for:

[0085] The indicator light is controlled to display according to the corresponding color based on the radiation safety level, wherein the first radiation safety level corresponds to the first color, the second radiation safety level corresponds to the second color, the third radiation safety level corresponds to the third color, and the fourth radiation safety level corresponds to the fourth color.

[0086] Thirdly, this application provides an electronic device, comprising:

[0087] Processor; and,

[0088] Memory for storing the executable instructions of the processor;

[0089] The processor is configured to perform any of the possible methods described in the first aspect by executing the executable instructions.

[0090] Fourthly, this application provides a computer-readable storage medium storing computer-executable instructions, which, when executed by a processor, are used to implement any of the possible methods described in the first aspect.

[0091] The radiation monitoring method and system based on data processing provided in this application acquires the radiation detection values ​​of each radiation detection sensor in the internal radiation detection sensor sequence to form an internal radiation detection value sequence, and acquires the radiation detection values ​​of each radiation detection sensor in the external radiation detection sensor sequence to form an external radiation detection value sequence. Then, the external radiation reference value sequence is determined based on the internal radiation detection value sequence and a preset radiation attenuation model. The radiation safety level of the space to be monitored is determined based on the external radiation reference value sequence and the external radiation detection value sequence, thereby monitoring the radiation protection performance of the space to be monitored to ensure the reliability of the protection of the space to be monitored. Attached Figure Description

[0092] The accompanying drawings, which are incorporated in and form part of this specification, illustrate embodiments consistent with this application and, together with the description, serve to explain the principles of this application.

[0093] Figure 1 This is a schematic flowchart illustrating a data processing-based radiation monitoring method according to an example embodiment of this application;

[0094] Figure 2 This is a schematic flowchart illustrating a data processing-based radiation monitoring method according to another exemplary embodiment of this application;

[0095] Figure 3 This is a schematic diagram of the structure of a radiation monitoring system according to an example embodiment of this application;

[0096] Figure 4 This is a schematic diagram of the structure of an electronic device according to an example embodiment of this application.

[0097] The accompanying drawings have illustrated specific embodiments of this application, which will be described in more detail below. These drawings and descriptions are not intended to limit the scope of the concept in any way, but rather to illustrate the concept of this application to those skilled in the art through reference to specific embodiments. Detailed Implementation

[0098] Exemplary embodiments will now be described in detail, examples of which are illustrated in the accompanying drawings. When the following description relates to the drawings, unless otherwise indicated, the same numbers in different drawings denote the same or similar elements. The embodiments described in the following exemplary embodiments do not represent all embodiments consistent with this application. Rather, they are merely examples of apparatuses and methods consistent with some aspects of this application as detailed in the appended claims.

[0099] Figure 1 This is a schematic flowchart illustrating a data processing-based radiation monitoring method according to an example embodiment of this application. Figure 1 As shown, the method provided in this embodiment includes:

[0100] S101. Obtain the radiation detection values ​​of each radiation detection sensor in the internal radiation detection sensor sequence to form an internal radiation detection value sequence.

[0101] The method provided in this embodiment is applied to a radiation monitoring system, which includes: an internal radiation detection sensor sequence, an external radiation detection sensor sequence, and a data processor. Each radiation detection sensor in the internal sequence and each radiation detector in the external sequence are communicatively connected to the data processor. The internal radiation detection sensor sequence is distributed on the inner sidewall of the space to be monitored, and the external radiation detection sensor sequence is distributed on the outer sidewall of the space to be monitored at positions corresponding to the radiation detectors in the internal sequence. The space to be monitored is used to house radiation sources. In one possible application scenario, the space to be monitored can be a mobile protective vehicle used for transporting radiation sources; in this case, the internal radiation detection sensor sequence is arranged inside the mobile protective vehicle, and the external radiation detection sensor sequence is arranged outside the vehicle. In another possible application scenario, the space to be monitored can also be a warehouse used for storing radiation sources; in this case, the internal radiation detection sensor sequence is arranged inside the warehouse, and the external radiation detection sensor sequence is arranged outside the warehouse.

[0102] In this step, the radiation detection values ​​of each radiation detection sensor in the internal radiation detection sensor sequence are acquired to form an internal radiation detection value sequence. A radiation detection sensor is a device used to measure and detect the radiation level in the environment, capable of monitoring various types of radiation, including ionizing radiation (such as gamma rays, X-rays, and beta particles) and non-ionizing radiation (such as ultraviolet and visible light). Furthermore, the aforementioned radiation detection sensors can be Geiger-Muller counters, ionization chamber sensors, and electron detectors, etc. A Geiger-Muller counter is a commonly used radiation detection sensor, primarily used to measure gamma rays, beta particles, and some higher-energy alpha particles. It measures the radiation value by counting the ionization phenomena produced by the irradiated body. An ionization chamber sensor utilizes the ionization phenomenon in a gas to measure radiation. When radiation passes through the ionization chamber, it generates ionization pairs, forming a current, and the radiation dose can be determined by measuring the magnitude of the current. An electron detector is a sensor used to measure low-energy radiation (such as beta particles). It measures the radiation level by measuring the electrons or charges generated when radiation interacts with the sensor's internal material. The aforementioned radiation detection sensors are widely used in nuclear industry, medical radiology, environmental monitoring, and radiation safety. Appropriate sensors can be selected based on specific application requirements and radiation types.

[0103] S102. Obtain the radiation detection values ​​of each radiation detection sensor in the external radiation detection sensor sequence to form an external radiation detection value sequence.

[0104] In this step, the radiation detection values ​​of each radiation detection sensor in the external radiation detection sensor sequence are obtained to form an external radiation detection value sequence. It is worth noting that the radiation detection sensors in the external radiation detection sensor sequence can be of the same type as those in the internal radiation detection sensor sequence, or they can be of different types.

[0105] S103. Determine the external radiation reference value sequence based on the internal radiation detection value sequence and the preset radiation attenuation model.

[0106] In this step, the external radiation reference value sequence can be determined based on the internal radiation detection value sequence and the preset radiation attenuation model.

[0107] Specifically, it could be based on a sequence of internal radiation detection values. And a preset radiation attenuation model to determine the external radiation reference numerical sequence. The preset radiation attenuation model includes Formula 1, which is:

[0108]

[0109] in, This represents the total number of radiation detection sensors in the internal radiation detection sensor sequence. The first in the internal radiation detection sensor sequence The radiation intensity value detected by each radiation detection sensor. This is the reference radiation intensity value after the rays penetrate the side wall of the space to be monitored. The mass absorption coefficient, The material density of the sidewall of the space to be monitored. The first on the side wall of the space to be monitored The thickness of the area where each radiation detection sensor is deployed. It is worth noting that... It can be the first on the side wall of the space to be monitored. The preset thickness of the area where each radiation detection sensor is deployed, that is, the thickness used during construction or design.

[0110] S104. Determine the radiation safety level of the space to be monitored based on the external radiation reference value sequence and the external radiation detection value sequence.

[0111] In this step, the radiation safety level of the space to be monitored can be determined based on the external radiation reference value sequence and the external radiation detection value sequence.

[0112] Specifically, it can be based on an external radiation reference value sequence. and external radiation detection numerical sequence Determine the numerical sequence of external radiation bias ,in, The determination is based on Formula 2, which is:

[0113]

[0114] Based on the numerical sequence of external radiation deviation And Formula 3 determines the value of the first characteristic. Formula 3 is:

[0115]

[0116] Based on the numerical sequence of external radiation deviation And Formula 4 determines the value of the second characteristic. Formula 4 is:

[0117]

[0118] in, Numerical sequence of external radiation bias The total number of non-zero numerical elements in the neutron;

[0119] If the first characteristic value Less than or equal to a preset first feature threshold, and the second feature value If the radiation safety level of the space to be monitored is less than or equal to the preset second characteristic threshold, then the radiation safety level of the space to be monitored is the first radiation safety level.

[0120] If the first characteristic value The value is greater than a preset first feature threshold and less than a preset third feature threshold, and / or the value of the second feature. If the value is greater than or equal to the preset second feature threshold, then the equivalent feature value is determined according to Formula 5. Formula 5 is:

[0121]

[0122] in, , These are the first weight value and the second weight value, respectively. , All positive numbers ,and, Value and the value of the first feature The numerical values ​​are positively correlated;

[0123] If the equivalent characteristic value If the value is less than or equal to the preset fourth characteristic threshold, the radiation safety level of the space to be monitored is the second radiation safety level; if the equivalent characteristic value is less than or equal to the preset fourth characteristic threshold, the radiation safety level of the space to be monitored is the second radiation safety level. If the radiation level is greater than the preset fourth characteristic threshold, the radiation safety level of the space to be monitored is the third radiation safety level.

[0124] If the first characteristic value If the radiation safety level of the space to be monitored is greater than or equal to the preset third characteristic threshold, then the radiation safety level of the space to be monitored is the fourth radiation safety level.

[0125] In this embodiment, the radiation detection values ​​of each radiation detection sensor in the internal radiation detection sensor sequence are obtained to form an internal radiation detection value sequence, and the radiation detection values ​​of each radiation detection sensor in the external radiation detection sensor sequence are obtained to form an external radiation detection value sequence. Then, the external radiation reference value sequence is determined based on the internal radiation detection value sequence and a preset radiation attenuation model. Thus, the radiation safety level of the space to be monitored is determined based on the external radiation reference value sequence and the external radiation detection value sequence, and the radiation protection performance of the space to be monitored is monitored to ensure the reliability of the protection of the space to be monitored.

[0126] Therefore, through the above monitoring methods, the changes in the protective effect of the monitored space on the radiation source caused by long-term external environmental erosion can be monitored, so as to take timely remedial measures in the early stage of radiation exceeding the standard and avoid radiation accidents.

[0127] Figure 2 This is a schematic flowchart illustrating a data processing-based radiation monitoring method according to another exemplary embodiment of this application. Figure 2 As shown, the method provided in this embodiment includes:

[0128] S201. Obtain the radiation detection values ​​of each radiation detection sensor in the internal radiation detection sensor sequence to form an internal radiation detection value sequence.

[0129] In this step, the radiation detection values ​​of each radiation detection sensor in the internal radiation detection sensor sequence can be obtained to form an internal radiation detection value sequence.

[0130] S202. Obtain the radiation detection values ​​of each radiation detection sensor in the external radiation detection sensor sequence to form an external radiation detection value sequence.

[0131] In this step, the radiation detection values ​​of each radiation detection sensor in the external radiation detection sensor sequence are obtained to form an external radiation detection value sequence. It is worth noting that the radiation detection sensors in the external radiation detection sensor sequence can be of the same type as those in the internal radiation detection sensor sequence, or they can be of different types.

[0132] S203. Determine the external radiation reference value sequence based on the internal radiation detection value sequence and the preset radiation attenuation model.

[0133] In this step, the external radiation reference value sequence can be determined based on the internal radiation detection value sequence and the preset radiation attenuation model.

[0134] Specifically, it could be based on a sequence of internal radiation detection values. And a preset radiation attenuation model to determine the external radiation reference numerical sequence. The preset radiation attenuation model includes Formula 1, which is:

[0135]

[0136] in, This represents the total number of radiation detection sensors in the internal radiation detection sensor sequence. The first in the internal radiation detection sensor sequence The radiation intensity value detected by each radiation detection sensor. This is the reference radiation intensity value after the rays penetrate the side wall of the space to be monitored. The mass absorption coefficient, The material density of the sidewall of the space to be monitored. The first on the side wall of the space to be monitored The thickness of the area where the radiation detection sensors are arranged.

[0137] S204. Determine the radiation safety level of the space to be monitored based on the external radiation reference value sequence and the external radiation detection value sequence.

[0138] In this step, the radiation safety level of the space to be monitored can be determined based on the external radiation reference value sequence and the external radiation detection value sequence.

[0139] Specifically, it can be based on an external radiation reference value sequence. and external radiation detection numerical sequence Determine the numerical sequence of external radiation bias ,in, The determination is based on Formula 2, which is:

[0140]

[0141] Based on the numerical sequence of external radiation deviation And Formula 3 determines the value of the first characteristic. Formula 3 is:

[0142]

[0143] Based on the numerical sequence of external radiation deviation And Formula 4 determines the value of the second characteristic. Formula 4 is:

[0144]

[0145] in, Numerical sequence of external radiation bias The total number of non-zero numerical elements in the neutron;

[0146] If the first characteristic value Less than or equal to a preset first feature threshold, and the second feature value If the radiation safety level of the space to be monitored is less than or equal to the preset second characteristic threshold, then the radiation safety level of the space to be monitored is the first radiation safety level.

[0147] If the first characteristic value The value is greater than a preset first feature threshold and less than a preset third feature threshold, and / or the value of the second feature. If the value is greater than or equal to the preset second feature threshold, then the equivalent feature value is determined according to Formula 5. Formula 5 is:

[0148]

[0149] in, , These are the first weight value and the second weight value, respectively. , All positive numbers ,and, Value and the value of the first feature The numerical values ​​are positively correlated;

[0150] If the equivalent characteristic value If the value is less than or equal to the preset fourth characteristic threshold, the radiation safety level of the space to be monitored is the second radiation safety level; if the equivalent characteristic value is less than or equal to the preset fourth characteristic threshold, the radiation safety level of the space to be monitored is the second radiation safety level. If the radiation level is greater than the preset fourth characteristic threshold, the radiation safety level of the space to be monitored is the third radiation safety level.

[0151] If the first characteristic value If the radiation safety level of the space to be monitored is greater than or equal to the preset third characteristic threshold, then the radiation safety level of the space to be monitored is the fourth radiation safety level.

[0152] Furthermore, if the radiation safety level of the space to be monitored is the fourth radiation safety level, then after determining the radiation safety level of the space to be monitored based on the external radiation reference value sequence and the external radiation detection value sequence, the process also includes:

[0153] Identify the subsequence of external radiation deviation values ​​that are greater than a preset third feature threshold in the external radiation deviation numerical sequence. External radiation bias numerical subsequence The set of numerical elements belongs to the external radiation bias numerical sequence. The set of numerical elements, the numerical subsequence of external radiation bias. Including external radiation bias numerical series All numerical elements in the array that are greater than the preset third feature threshold;

[0154] Based on the numerical subsequence of external radiation deviation Determine the corresponding external radiation detection sensor subsequence;

[0155] The radiation protection level is determined based on the distribution of the external radiation detection sensor subsequence on the outer sidewall of the space to be monitored.

[0156] Optionally, determining the radiation protection level based on the distribution of the external radiation detection sensor sub-sequence on the outer sidewall of the space to be monitored may include:

[0157] If more than a preset proportion threshold of radiation detection sensors in the external radiation detection sensor subsequence are distributed on the outer sidewall of the target in the space to be monitored, then the radiation protection level is determined to be the first radiation protection level. The first radiation protection level is used to indicate that radiation protection enhancement is applied to the outer sidewall of the target.

[0158] If the distribution ratio of the external radiation detection sensor subsequence on each external sidewall is less than a preset ratio threshold, then the number of radiation detection sensors on each external sidewall of the space to be monitored is determined, and the abnormal radiation detection sensor distribution sequence is formed by the number of radiation detection sensors on each external sidewall of the space to be monitored. ,in, For the external radiation detection sensor subsequence in the first... The number of radiation detection sensors distributed on the outer sidewalls, The number of external sidewalls of the space to be monitored;

[0159] Based on Formula 5 and the distribution sequence of abnormal radiation detection sensors Determine the characteristic value of the deviation in radiation anomaly distribution Formula 5 is:

[0160]

[0161] If the number of radiation detection sensors in the external radiation detection sensor subsequence exceeds a preset threshold, and the radiation abnormal distribution deviation characteristic value... If the value is less than or equal to the preset distribution deviation threshold, the radiation protection level is determined to be the second radiation protection level. The second radiation protection level is used to indicate that all external sidewalls of the space to be monitored should be enhanced with overall radiation protection.

[0162] Optionally, after obtaining the radiation detection values ​​of each radiation detection sensor in the internal radiation detection sensor sequence to form an internal radiation detection value sequence, the process may further include:

[0163] Based on the internal radiation detection numerical sequence And Formula 6 determines the internal radiation characteristic value. Formula 6 is:

[0164]

[0165] in, , These are the third and fourth weight values, respectively. , All positive numbers ,and, Values ​​and The numerical values ​​are positively correlated;

[0166] If the internal radiation characteristic value If the radiation exceeds a preset internal radiation threshold, the number of radiation detection sensors in the external radiation detection sensor subsequence exceeds a preset number threshold, and the radiation abnormal distribution deviation characteristic value is greater than the preset internal radiation threshold. If the value is less than or equal to the preset distribution deviation threshold, the radiation protection level is determined to be the third radiation protection level. The third radiation protection level is used to indicate that the overall radiation protection enhancement is carried out on each internal sidewall and each external sidewall of the space to be monitored.

[0167] S205. Control the indicator lights to display according to the corresponding colors based on the radiation safety level.

[0168] In this step, the indicator lights can be controlled to display according to the corresponding colors based on the radiation safety level. The first radiation safety level corresponds to the first color, the second radiation safety level corresponds to the second color, the third radiation safety level corresponds to the third color, and the fourth radiation safety level corresponds to the fourth color.

[0169] Figure 3 This is a schematic diagram of the structure of a radiation monitoring system according to an example embodiment of this application. For example... Figure 3As shown, the radiation monitoring system 300 provided in this embodiment includes: an internal radiation detection sensor sequence 310, an external radiation detection sensor sequence 320, and a data processor 330. Each radiation detection sensor in the internal radiation detection sensor sequence 310 and each radiation detector in the external radiation detection sensor sequence 320 are respectively communicatively connected to the data processor 330. The internal radiation detection sensor sequence 310 is distributed on the internal sidewall of the space to be monitored, and the external radiation detection sensor sequence 320 is distributed on the external sidewall of the space to be monitored at positions corresponding to the radiation detectors in the internal radiation detection sensor sequence 310. A radiation source is placed in the space to be monitored.

[0170] The data processor 330 is used to acquire the radiation detection values ​​of each radiation detection sensor in the internal radiation detection sensor sequence 310 to form an internal radiation detection value sequence.

[0171] The data processor 330 is also used to acquire the radiation detection values ​​of each radiation detection sensor in the external radiation detection sensor sequence 320 to form an external radiation detection value sequence.

[0172] The data processor 330 is also used to determine an external radiation reference value sequence based on the internal radiation detection value sequence and a preset radiation attenuation model.

[0173] The data processor 330 is also used to determine the radiation safety level of the space to be monitored based on the external radiation reference value sequence and the external radiation detection value sequence.

[0174] Optionally, the data processor 330 is specifically used for:

[0175] According to the internal radiation detection numerical sequence The external radiation reference numerical sequence is determined by the preset radiation attenuation model. The preset radiation attenuation model includes Formula 1, which is:

[0176]

[0177] in, This represents the total number of radiation detection sensors in the internal radiation detection sensor sequence 310. The first of the internal radiation detection sensor sequence 310 The radiation intensity value detected by each radiation detection sensor. This is the reference radiation intensity value after the rays penetrate the side wall of the space to be monitored. The mass absorption coefficient, The density of the material of the sidewall of the space to be monitored. The first on the side wall of the space to be monitored The thickness of the area where the radiation detection sensors are arranged.

[0178] Optionally, the data processor 330 is specifically used for:

[0179] According to the external radiation reference value sequence and the external radiation detection numerical sequence Determine the numerical sequence of external radiation bias ,in, The determination is based on Formula 2, which is:

[0180]

[0181] According to the external radiation deviation numerical sequence And Formula 3 determines the value of the first characteristic. Formula 3 is:

[0182]

[0183] According to the external radiation deviation numerical sequence And Formula 4 determines the value of the second characteristic. Formula 4 is:

[0184]

[0185] in, The external radiation bias numerical sequence The total number of non-zero numerical elements in the neutron;

[0186] If the first feature value Less than or equal to a preset first feature threshold, and the second feature value If the radiation safety level of the space to be monitored is less than or equal to the preset second characteristic threshold, then the radiation safety level of the space to be monitored is the first radiation safety level.

[0187] If the first feature value The value is greater than a preset first feature threshold and less than a preset third feature threshold, and / or the value of the second feature. If the value is greater than or equal to the preset second feature threshold, then the equivalent feature value is determined according to Formula 5. Formula 5 is:

[0188]

[0189] in, , These are the first weight value and the second weight value, respectively. , All positive numbers ,and, The value is the same as the first feature value. The numerical values ​​are positively correlated;

[0190] If the equivalent characteristic value If the value of the equivalent feature is less than or equal to a preset fourth feature threshold, then the radiation safety level of the space to be monitored is the second radiation safety level; if the equivalent feature value is less than or equal to a preset fourth feature threshold, then the radiation safety level of the space to be monitored is the second radiation safety level. If the radiation level is greater than the preset fourth feature threshold, then the radiation safety level of the space to be monitored is the third radiation safety level.

[0191] If the first feature value If the radiation safety level of the space to be monitored is greater than or equal to the preset third characteristic threshold, then the radiation safety level of the space to be monitored is the fourth radiation safety level.

[0192] Optionally, the data processor 330 is specifically used for:

[0193] Determine the subsequence of external radiation deviation values ​​that is greater than the preset third feature threshold in the external radiation deviation value sequence. The external radiation bias numerical subsequence The set of numerical elements belongs to the external radiation bias numerical sequence. The set of numerical elements, the external radiation bias numerical subsequence Including the external radiation deviation numerical sequence All numerical elements in the range that are greater than the preset third feature threshold;

[0194] According to the external radiation deviation numerical subsequence Determine the corresponding external radiation detection sensor subsequence;

[0195] The radiation protection level is determined based on the distribution of the external radiation detection sensor subsequence on the outer sidewall of the space to be monitored.

[0196] Optionally, the data processor 330 is specifically used for:

[0197] If more than a preset proportion threshold of radiation detection sensors in the external radiation detection sensor subsequence are distributed on the outer sidewall of the target in the space to be monitored, then the radiation protection level is determined to be the first radiation protection level. The first radiation protection level is used to indicate that radiation protection enhancement is applied to the outer sidewall of the target.

[0198] If the distribution ratio of the external radiation detection sensor subsequence on each external sidewall is less than the preset ratio threshold, then the number of radiation detection sensors of the external radiation detection sensor subsequence on each external sidewall of the space to be monitored is determined, and the abnormal radiation detection sensor distribution sequence constituted by the number of radiation detection sensors of the external radiation detection sensor subsequence on each external sidewall of the space to be monitored is defined. ,in, For the external radiation detection sensor sub-sequence in the 1st... The number of radiation detection sensors distributed on the outer sidewalls, The number of external sidewalls of the space to be monitored;

[0199] Based on Formula 5 and the distribution sequence of abnormal radiation detection sensors Determine the characteristic value of the deviation in radiation anomaly distribution Formula 5 is:

[0200]

[0201] If the number of radiation detection sensors in the external radiation detection sensor sub-sequence exceeds a preset threshold, and the radiation anomaly distribution deviation characteristic value If the radiation protection level is less than or equal to a preset distribution deviation threshold, then the radiation protection level is determined to be the second radiation protection level. The second radiation protection level is used to indicate that all external sidewalls of the space to be monitored are subjected to overall radiation protection enhancement.

[0202] Optionally, the data processor 330 is specifically used for:

[0203] According to the internal radiation detection numerical sequence And Formula 6 determines the internal radiation characteristic value. Formula 6 is:

[0204]

[0205] in, , These are the third and fourth weight values, respectively. , All positive numbers ,and, The value is the same as the stated The numerical values ​​are positively correlated;

[0206] If the internal radiation characteristic value If the radiation distribution deviation characteristic value is greater than the preset internal radiation threshold, the number of radiation detection sensors in the external radiation detection sensor sub-sequence exceeds the preset number threshold, and the radiation distribution deviation characteristic value is greater than the preset internal radiation threshold. If the radiation protection level is less than or equal to the preset distribution deviation threshold, then the radiation protection level is determined to be the third radiation protection level. The third radiation protection level is used to indicate that the overall radiation protection enhancement is carried out on each internal sidewall and each external sidewall of the space to be monitored.

[0207] Optionally, the system further includes: an indicator light 340, which is communicatively connected to the data processor 330; optionally, the data processor 330 is specifically used for:

[0208] The indicator light 340 is controlled to display according to the corresponding color based on the radiation safety level, wherein the first radiation safety level corresponds to the first color, the second radiation safety level corresponds to the second color, the third radiation safety level corresponds to the third color, and the fourth radiation safety level corresponds to the fourth color.

[0209] Figure 4 This is a schematic diagram of the structure of an electronic device according to an example embodiment of this application. For example... Figure 4 As shown, the electronic device 400 provided in this embodiment includes: a processor 401 and a memory 402; wherein:

[0210] Memory 402 is used to store computer programs, and the memory may also be flash memory.

[0211] Processor 401 is used to execute the execution instructions stored in the memory to implement the various steps in the above method. For details, please refer to the relevant descriptions in the preceding method embodiments.

[0212] Alternatively, the memory 402 can be either standalone or integrated with the processor 401.

[0213] When the memory 402 is a device independent of the processor 401, the electronic device 400 may further include:

[0214] Bus 403 is used to connect the memory 402 and the processor 401.

[0215] This embodiment also provides a readable storage medium storing a computer program, which, when executed by at least one processor of an electronic device, enables the electronic device to perform the methods provided in the various embodiments described above.

[0216] This embodiment also provides a program product including a computer program stored in a readable storage medium. At least one processor of an electronic device can read the computer program from the readable storage medium, and the at least one processor executes the computer program to cause the electronic device to perform the methods provided in the various embodiments described above.

[0217] Other embodiments of this application will readily occur to those skilled in the art upon consideration of the specification and practice of the invention disclosed herein. This application is intended to cover any variations, uses, or adaptations of this application that follow the general principles of this application and include common knowledge or customary techniques in the art not disclosed herein. The specification and examples are to be considered exemplary only, and the true scope and spirit of this application are indicated by the following claims.

[0218] It should be understood that this application is not limited to the precise structure described above and shown in the accompanying drawings, and various modifications and changes can be made without departing from its scope. The scope of this application is limited only by the appended claims.

Claims

1. A radiation monitoring method based on data processing, characterized in that, An application is made in a radiation monitoring system, the system comprising: an internal radiation detection sensor sequence, an external radiation detection sensor sequence, and a data processor. Each radiation detection sensor in the internal radiation detection sensor sequence and each radiation detector in the external radiation detection sensor sequence are communicatively connected to the data processor. The internal radiation detection sensor sequence is distributed on the internal sidewall of the space to be monitored, and the external radiation detection sensor sequence is distributed on the external sidewall of the space to be monitored at positions corresponding to the radiation detectors in the internal radiation detection sensor sequence. The space to be monitored is used to place a radiation source. The method includes: The radiation detection values ​​of each radiation detection sensor in the internal radiation detection sensor sequence are obtained to form an internal radiation detection value sequence. Obtain the radiation detection values ​​of each radiation detection sensor in the external radiation detection sensor sequence to form an external radiation detection value sequence; The external radiation reference value sequence is determined based on the internal radiation detection value sequence and the preset radiation attenuation model. The radiation safety level of the space to be monitored is determined based on the external radiation reference value sequence and the external radiation detection value sequence. The step of determining the external radiation reference value sequence based on the internal radiation detection value sequence and the preset radiation attenuation model includes: According to the internal radiation detection numerical sequence The external radiation reference numerical sequence is determined by the preset radiation attenuation model. The preset radiation attenuation model includes Formula 1, which is: ； in, This represents the total number of radiation detection sensors in the internal radiation detection sensor sequence. The first in the internal radiation detection sensor sequence The radiation intensity value detected by each radiation detection sensor. This is the reference radiation intensity value after the rays penetrate the side wall of the space to be monitored. The mass absorption coefficient, The density of the material of the sidewall of the space to be monitored. The first on the side wall of the space to be monitored The thickness of the area where the radiation detection sensors are arranged; Determining the radiation safety level of the space to be monitored based on the external radiation reference value sequence and the external radiation detection value sequence includes: According to the external radiation reference value sequence and the external radiation detection numerical sequence Determine the numerical sequence of external radiation bias ,in, The determination is based on Formula 2, which is: ； According to the external radiation deviation numerical sequence And Formula 3 determines the value of the first characteristic. Formula 3 is: ； According to the external radiation deviation numerical sequence And Formula 4 determines the value of the second characteristic. Formula 4 is: ； in, The external radiation bias numerical sequence The total number of non-zero numerical elements in the neutron; If the first feature value Less than or equal to a preset first feature threshold, and the second feature value If the radiation safety level of the space to be monitored is less than or equal to the preset second characteristic threshold, then the radiation safety level of the space to be monitored is the first radiation safety level. If the first feature value The value is greater than a preset first feature threshold and less than a preset third feature threshold, and / or the value of the second feature. If the value is greater than or equal to the preset second feature threshold, then the equivalent feature value is determined according to Formula 5. Formula 5 is: ； in, , These are the first weight value and the second weight value, respectively. , All positive numbers ,and, The value is the same as the first feature value. The numerical values ​​are positively correlated; If the equivalent characteristic value If the value of the equivalent feature is less than or equal to a preset fourth feature threshold, then the radiation safety level of the space to be monitored is the second radiation safety level; if the equivalent feature value is less than or equal to a preset fourth feature threshold, then the radiation safety level of the space to be monitored is the second radiation safety level. If the radiation level is greater than the preset fourth feature threshold, then the radiation safety level of the space to be monitored is the third radiation safety level. If the first feature value If the radiation safety level of the space to be monitored is greater than or equal to the preset third characteristic threshold, then the radiation safety level of the space to be monitored is the fourth radiation safety level.

2. The radiation monitoring method based on data processing according to claim 1, characterized in that, If the radiation safety level of the space to be monitored is the fourth radiation safety level, then after determining the radiation safety level of the space to be monitored based on the external radiation reference value sequence and the external radiation detection value sequence, the method further includes: Determine the subsequence of external radiation deviation values ​​that is greater than the preset third feature threshold in the external radiation deviation value sequence. The external radiation bias numerical subsequence The set of numerical elements belongs to the external radiation bias numerical sequence. The set of numerical elements, the external radiation bias numerical subsequence Including the external radiation deviation numerical sequence All numerical elements in the range that are greater than the preset third feature threshold; According to the external radiation deviation numerical subsequence Determine the corresponding external radiation detection sensor subsequence; The radiation protection level is determined based on the distribution of the external radiation detection sensor subsequence on the outer sidewall of the space to be monitored.

3. The radiation monitoring method based on data processing according to claim 2, characterized in that, The step of determining the radiation protection level based on the distribution of the external radiation detection sensor sub-sequence on the outer sidewall of the space to be monitored includes: If more than a preset proportion threshold of radiation detection sensors in the external radiation detection sensor subsequence are distributed on the outer sidewall of the target in the space to be monitored, then the radiation protection level is determined to be the first radiation protection level. The first radiation protection level is used to indicate that radiation protection enhancement is applied to the outer sidewall of the target. If the distribution ratio of the external radiation detection sensor subsequence on each external sidewall is less than the preset ratio threshold, then the number of radiation detection sensors of the external radiation detection sensor subsequence on each external sidewall of the space to be monitored is determined, and the abnormal radiation detection sensor distribution sequence constituted by the number of radiation detection sensors of the external radiation detection sensor subsequence on each external sidewall of the space to be monitored is defined. ,in, For the external radiation detection sensor sub-sequence in the 1st... The number of radiation detection sensors distributed on the outer sidewalls, The number of external sidewalls of the space to be monitored; Based on Formula 5 and the distribution sequence of abnormal radiation detection sensors Determine the characteristic value of the deviation in radiation anomaly distribution Formula 5 is: ； If the number of radiation detection sensors in the external radiation detection sensor sub-sequence exceeds a preset threshold, and the radiation anomaly distribution deviation characteristic value If the radiation protection level is less than or equal to a preset distribution deviation threshold, then the radiation protection level is determined to be the second radiation protection level. The second radiation protection level is used to indicate that all external sidewalls of the space to be monitored are subjected to overall radiation protection enhancement.

4. The radiation monitoring method based on data processing according to claim 3, characterized in that, After acquiring the radiation detection values ​​of each radiation detection sensor in the internal radiation detection sensor sequence to form an internal radiation detection value sequence, the method further includes: According to the internal radiation detection numerical sequence And Formula 6 determines the internal radiation characteristic value. Formula 6 is: ； in, , These are the third and fourth weight values, respectively. , All positive numbers ,and, The value is the same as the stated The numerical values ​​are positively correlated; If the internal radiation characteristic value If the radiation distribution deviation characteristic value is greater than the preset internal radiation threshold, the number of radiation detection sensors in the external radiation detection sensor sub-sequence exceeds the preset number threshold, and the radiation distribution deviation characteristic value is greater than the preset internal radiation threshold. If the radiation protection level is less than or equal to the preset distribution deviation threshold, then the radiation protection level is determined to be the third radiation protection level. The third radiation protection level is used to indicate that the overall radiation protection enhancement is carried out on each internal sidewall and each external sidewall of the space to be monitored.

5. The radiation monitoring method based on data processing according to any one of claims 1-4, characterized in that, The system further includes: indicator lights, which are communicatively connected to the data processor; after determining the radiation safety level of the space to be monitored based on the external radiation reference value sequence and the external radiation detection value sequence, the system further includes: The indicator light is controlled to display according to the corresponding color based on the radiation safety level, wherein the first radiation safety level corresponds to the first color, the second radiation safety level corresponds to the second color, the third radiation safety level corresponds to the third color, and the fourth radiation safety level corresponds to the fourth color.

6. A radiation monitoring system, characterized in that, include: The system comprises an internal radiation detection sensor sequence, an external radiation detection sensor sequence, and a data processor. Each radiation detection sensor in the internal radiation detection sensor sequence and each radiation detector in the external radiation detection sensor sequence are communicatively connected to the data processor. The internal radiation detection sensor sequence is distributed on the internal sidewall of the space to be monitored, and the external radiation detection sensor sequence is distributed on the external sidewall of the space to be monitored at positions corresponding to the radiation detectors in the internal radiation detection sensor sequence. A radiation source is placed in the space to be monitored. The data processor is used to acquire the radiation detection values ​​of each radiation detection sensor in the internal radiation detection sensor sequence to form an internal radiation detection value sequence. The data processor is also used to acquire the radiation detection values ​​of each radiation detection sensor in the external radiation detection sensor sequence to form an external radiation detection value sequence. The data processor is also used to determine an external radiation reference value sequence based on the internal radiation detection value sequence and a preset radiation attenuation model. The data processor is further configured to determine the radiation safety level of the space to be monitored based on the external radiation reference value sequence and the external radiation detection value sequence. The data processor is specifically used for: According to the internal radiation detection numerical sequence The external radiation reference numerical sequence is determined by the preset radiation attenuation model. The preset radiation attenuation model includes Formula 1, which is: ； in, This represents the total number of radiation detection sensors in the internal radiation detection sensor sequence. The first in the internal radiation detection sensor sequence The radiation intensity value detected by each radiation detection sensor. This is the reference radiation intensity value after the rays penetrate the side wall of the space to be monitored. The mass absorption coefficient, The density of the material of the sidewall of the space to be monitored. The first on the side wall of the space to be monitored The thickness of the area where the radiation detection sensors are arranged; The data processor is specifically used for: According to the external radiation reference value sequence and the external radiation detection numerical sequence Determine the numerical sequence of external radiation bias ,in, The determination is based on Formula 2, which is: ； According to the external radiation deviation numerical sequence And Formula 3 determines the value of the first characteristic. Formula 3 is: ； According to the external radiation deviation numerical sequence And Formula 4 determines the value of the second characteristic. Formula 4 is: ； in, The external radiation bias numerical sequence The total number of non-zero numerical elements in the neutron; If the first feature value Less than or equal to a preset first feature threshold, and the second feature value If the radiation safety level of the space to be monitored is less than or equal to the preset second characteristic threshold, then the radiation safety level of the space to be monitored is the first radiation safety level. If the first feature value The value is greater than a preset first feature threshold and less than a preset third feature threshold, and / or the value of the second feature. If the value is greater than or equal to the preset second feature threshold, then the equivalent feature value is determined according to Formula 5. Formula 5 is: ； in, , These are the first weight value and the second weight value, respectively. , All positive numbers ,and, The value is the same as the first feature value. The numerical values ​​are positively correlated; If the equivalent characteristic value If the value of the equivalent feature is less than or equal to a preset fourth feature threshold, then the radiation safety level of the space to be monitored is the second radiation safety level; if the equivalent feature value is less than or equal to a preset fourth feature threshold, then the radiation safety level of the space to be monitored is the second radiation safety level. If the radiation level is greater than the preset fourth feature threshold, then the radiation safety level of the space to be monitored is the third radiation safety level. If the first feature value If the radiation safety level of the space to be monitored is greater than or equal to the preset third characteristic threshold, then the radiation safety level of the space to be monitored is the fourth radiation safety level.

7. An electronic device, characterized in that, include: processor; as well as, Memory for storing the executable instructions of the processor; The processor is configured to execute the method of any one of claims 1 to 5 by executing the executable instructions.

8. A computer-readable storage medium, characterized in that, The computer-readable storage medium stores computer-executable instructions, which, when executed by a processor, are used to implement the method as described in any one of claims 1 to 5.

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