Radiation measurement system and method

Abstract

The invention relates to the field of radiation detection, and provides a radiation measurement system and method, which is applied to a nuclear power station and comprises a plurality of monitoring devices and a monitoring platform, and the monitoring devices are used for detecting radiation information of each area of the nuclear power station; and the monitoring platform is in communication connection with the monitoring equipment, and the monitoring platform is used for storing and processing the radiation information. According to the scheme, the monitoring equipment can realize automatic transmission of measurement data, replaces manual weekly measurement of an existing nuclear power plant, reduces the workload and exposure dose of radiation protection workers, and meanwhile, reduces the problem of data storage errors caused by human errors. Therefore, the efficiency of measurement and data entry is improved.

Description

Technical Field

[0001] The present invention relates to the field of radiation detection, and in particular to a radiation measurement system and method. Background Art

[0002] In the operation and management of nuclear power plants, radiation monitoring and control are important links to ensure safety and environmental protection. In order to effectively monitor radiation levels and evaluate the conservatism of shielding design, nuclear power plants regularly implement a variety of measurements, including weekly measurements, shutdown measurements, and shielding design verification measurements during the first startup and first refueling phase of the unit. These measurements are designed to track and evaluate changes in radiation dose rates within nuclear power plants to ensure that they are always within the design and safety requirements.

[0003] In the prior art, measurements are usually performed manually by carrying portable devices, manually recording the measurement results during measurement, and then manually entering them into a database or archiving them on paper. This is time-consuming and labor-intensive, and is prone to mis-entry. Over the years, paper data is prone to loss, and the measurement data is scattered and cannot be effectively analyzed. Summary of the invention

[0004] In view of the above-mentioned shortcomings of the prior art, the object of the present invention is to provide a radiation measurement system and method to improve the efficiency of nuclear power plant measurement.

[0005] To achieve the above-mentioned and other related purposes, the present invention provides a radiation measurement system for use in a nuclear power plant, comprising:

[0006] Monitoring equipment, wherein a plurality of monitoring equipment are provided, and the monitoring equipment is used to detect radiation information of various areas of the nuclear power plant;

[0007] A monitoring platform is communicatively connected with the monitoring device, and the monitoring platform is used to store and process the radiation information.

[0008] In a specific embodiment of the present invention, the monitoring device includes a communication module for communicating with the monitoring platform, and the communication module includes a wireless communication unit.

[0009] In a specific embodiment of the present invention, the monitoring device includes a power module, and the power module includes a power interface and a battery.

[0010] In a specific embodiment of the present invention, the monitoring device includes a detection module, and the detection module is used to detect the dose rate of each area of ​​the nuclear power plant.

[0011] In a specific embodiment of the present invention, the monitoring device includes a clock module, and the monitoring device starts detection according to time information of the clock module.

[0012] In a specific embodiment of the present invention, the monitoring device includes a human-computer interaction module, and the monitoring device starts detection according to interaction information of the human-computer interaction module.

[0013] In a specific embodiment of the present invention, the monitoring device includes a storage module, and the storage module is used to store the radiation information.

[0014] In a specific embodiment of the present invention, the monitoring device comprises a switching module, and the switching module is used to switch the monitoring device between a detection mode and a standby mode, and the power of the standby mode is less than the power of the detection mode.

[0015] In a specific embodiment of the present invention, the detection mode is configured so that the monitoring device in the detection mode starts detection to obtain the radiation information and transmits it to the monitoring platform, and the standby mode is configured so that the monitoring device in the standby mode turns off the detection module and switches the communication module to a low power consumption mode.

[0016] In a specific embodiment of the present invention, it further comprises a strap or a bracket, wherein the strap is used to fix the monitoring device to the pipeline, and the bracket is used to fix the monitoring device and lift it off the ground, and the bracket has different heights.

[0017] The present invention also proposes a radiation measurement method, which is applied to the radiation measurement system as described above, wherein the monitoring device performs the following steps:

[0018] Get time information;

[0019] Initiate detection according to the time information to obtain the radiation information;

[0020] The radiation information is sent to the monitoring platform.

[0021] The present invention also proposes a radiation measurement method, which is applied to the radiation measurement system as described above, wherein the monitoring device is arranged in a hot spot area, and the monitoring device performs the following steps:

[0022] Get startup information;

[0023] Initiate detection according to the startup information to continuously obtain the radiation information;

[0024] The radiation information is sent to the monitoring platform.

[0025] The present invention also proposes a radiation measurement method, which is applied to the radiation measurement system as described above, wherein the monitoring device performs the following steps:

[0026] Obtaining control information sent by the monitoring platform;

[0027] Initiate detection according to the control information to obtain the radiation information;

[0028] The radiation information is sent to the monitoring platform.

[0029] The present invention proposes a radiation measurement system and method. In the above scheme, the monitoring equipment can realize automatic transmission of measurement data, replacing the manual weekly measurement of existing nuclear power plants, reducing the workload and exposure dose of radiation protection workers, and reducing the problem of data saving errors caused by human errors, thereby improving the efficiency of measurement and data entry. BRIEF DESCRIPTION OF THE DRAWINGS

[0030] In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the accompanying drawings required for describing the embodiments will be briefly introduced below. Obviously, the accompanying drawings described below are only some embodiments of the present invention. For ordinary technicians in this field, other accompanying drawings can be obtained based on these accompanying drawings without paying creative work.

[0031] Figure 1 A simplified structural diagram of a radiation measurement system in a specific embodiment of the present invention;

[0032] Figure 2 It is a schematic diagram of the structure of a monitoring device of a radiation measurement system in a specific embodiment of the present invention.

[0033] Explanation of the accompanying drawings: 10. Monitoring platform; 20. Monitoring equipment; 21. Communication module; 22. Power module; 23. Detection module; 24. Clock module; 25. Human-computer interaction module; 26. Storage module; 27. Switching module; 28. Processing control module; 30. Background control module; 40. Power plant server; 50. Control cabinet. DETAILED DESCRIPTION

[0034] The following describes the embodiments of the present invention by specific examples, and those skilled in the art can easily understand other advantages and effects of the present invention from the contents disclosed in this specification. The present invention can also be implemented or applied through other different specific embodiments, and the details in this specification can also be modified or changed in various ways based on different viewpoints and applications without departing from the spirit of the present invention. It should be noted that the following embodiments and features in the embodiments can be combined with each other without conflict.

[0035] It should be noted that the illustrations provided in the following embodiments are only used to illustrate the basic concept of the present invention in a schematic manner, and thus the illustrations only show components related to the present invention rather than being drawn according to the number, shape and size of components in actual implementation. In actual implementation, the type, quantity and proportion of each component may be changed arbitrarily, and the component layout may also be more complicated.

[0036] In the daily operation of nuclear power plants, changes in the status of the units and the accumulation of activated corrosion products will cause fluctuations in the radiation status of various areas within the radiation control area. In order to promptly detect areas where the dose rate increases abnormally, radiation protection workers need to measure the dose rate in fixed areas every week. By analyzing the data, abnormal situations can be identified and corresponding measures can be taken, such as reminding power plant workers not to enter high-radiation areas, thereby ensuring the safety of workers.

[0037] During the shutdown process of the unit, the concentration of activated corrosion products may have transient peaks, especially during the oxidation purification stage, when a large number of corrosion products in the core are taken out and deposited in various areas of the primary circuit. Changes in this process directly affect the radiation level. Therefore, radiation protection personnel need to conduct detailed dose rate measurements in fixed areas of the primary circuit of the nuclear power plant during each shutdown. These measurements provide important data support for the formulation of water chemistry and decontamination plans, helping to optimize subsequent maintenance and operation measures.

[0038] During the first startup of a new unit, the effectiveness of the shielding design is crucial. Radiation protection workers need to repeatedly perform dose rate measurements (RAD measurements) in fixed areas at different power platforms to confirm whether the measured values ​​meet the design requirements. This not only involves monitoring under normal operating conditions, but also includes the highly radioactive spent fuel transfer process during the first refueling of the unit. During this process, the dose rate of the area passed by the transfer route must be measured in real time and compared with the design requirements to ensure the correctness of the shielding design and reduce potential radiation risks.

[0039] Regular radiation dose measurement in nuclear power plants is a key link in ensuring nuclear safety and environmental protection. Through weekly measurements, shutdown measurements, and shielding design verification measurements during the initial startup and refueling phases, nuclear power plants can effectively monitor radiation levels, identify potential risks in a timely manner, and take appropriate protective measures. These measures not only protect the safety of workers, but also lay a solid foundation for the safe operation of nuclear power plants.

[0040] Portable monitoring equipment in the prior art, such as portable gamma dose rate meters, long-rod dose rate meters, and neutron dose equivalent rate meters, can be carried by radiation protection personnel to designated areas for measurement according to measurement requirements. This method is highly flexible and can accurately monitor specific areas and time periods.

[0041] However, the measurement results need to be manually recorded and entered into a database or paper file, which increases the possibility of human error. At the same time, paper data is easily lost, resulting in the dispersion of information and inability to effectively analyze. Due to the dangers of the radiation field, the measurement time of staff in the radiation area is limited, resulting in the inability to guarantee the stability and accuracy of the data. Frequent measurements also increase the radiation dose of staff. The staff's measurement operations in the radiation plant are not standardized, the measurement time does not meet the accuracy requirements, and the data stability and accuracy are poor. Various types of radiation measurement data are stored in a variety of ways and in scattered locations. Various types of radiation measurement data have not been digitally centralized and effectively utilized.

[0042] To solve the above technical problems, Figure 1 As shown, the present invention provides a radiation measurement system, which is applied to a nuclear power plant and includes a monitoring platform 10 and a monitoring device 20 .

[0043] The monitoring platform 10 is in communication connection with the monitoring equipment 20, and is used to store and process the radiation information. The monitoring platform 10 is used to collect real-time measurement data of each monitoring equipment 20, and has a data storage module 26, a data analysis module and a display module.

[0044] The data storage module 26 collects and stores data from different monitoring devices 20 .

[0045] The data types include:

[0046] Measurement data: real-time dose rate, historical data.

[0047] Measurement point information: including room number, equipment code, etc., to facilitate data tracking and positioning.

[0048] Measurement time: Record the specific time of each measurement to support timing analysis of data.

[0049] Storage method: It is recommended to use a database (such as SQL or NoSQL) for efficient data management to ensure fast retrieval and persistence of data.

[0050] Data analysis module, used to analyze and process the collected measurement data.

[0051] The analysis includes:

[0052] Basic statistics: calculate maximum, minimum, average, etc.

[0053] Trend analysis: Compare current measurement data with historical data (such as averages over the past few days or weeks) to identify abnormal fluctuations.

[0054] Alarm mechanism: Set a threshold value, and when the measured value exceeds the set range, an alarm will be automatically issued to notify relevant personnel to conduct investigation.

[0055] Data visualization: Generate charts (such as line charts and bar charts) to help users understand data trends and changes.

[0056] User customization: Allows users to define alarm conditions and analysis time periods, enhancing flexibility.

[0057] Display module, used to graphically display data analysis results.

[0058] The exhibition content includes:

[0059] Real-time data monitoring: Display the dose rate of each measuring point and reflect the status in time.

[0060] Historical data trend: Display the dose rate change trend of different measurement points in the form of a chart, which is convenient for users to observe and compare over a long period of time.

[0061] Alarm information: Clearly identify abnormal conditions to ensure that relevant personnel can respond quickly.

[0062] User interface: Design a simple and intuitive user interface that supports multiple information display methods (such as dashboards, charts, etc.) and allows users to customize the displayed content.

[0063] Monitoring equipment 20, wherein a plurality of monitoring equipment 20 are provided, and the monitoring equipment 20 is used to detect radiation information of each area of ​​the nuclear power plant. The monitoring equipment 20 is used to monitor the radiation information of each area in real time to ensure personnel safety and environmental protection. The monitoring equipment 20 may include:

[0064] Radiation detectors: such as Geiger counters, scintillation counters, semiconductor detectors and neutron detectors (He-3 tubes, etc.), which can measure alpha, beta, gamma radiation and neutron radiation.

[0065] The monitoring equipment 20 should be evenly distributed in key areas of the nuclear power plant, such as the reactor area and storage area, so as to fully cover radiation monitoring. By installing and using a variety of monitoring equipment 20, the nuclear power plant can effectively monitor the radiation level and ensure the safety of employees. Real-time monitoring and data processing capabilities enable the nuclear power plant to respond quickly to potential radiation risks and ensure safe operation. The monitoring equipment 20 can automatically transmit measurement data, replacing the manual weekly measurement of existing nuclear power plants, reducing the workload and exposure dose of radiation protection workers, and reducing the problem of data storage errors caused by human errors.

[0066] like Figure 2 The monitoring device 20 comprises:

[0067] The communication module 21 is used to communicate with the monitoring platform 10, and the communication module 21 includes a wireless communication unit. The module supports wireless communication methods such as 4G, 5G, WIFI and Bluetooth, and has a serial communication function of a USB interface. This diversity ensures that data can be effectively transmitted in different environments, especially in areas without data line interfaces. The monitoring device 20 uploads the detection data to the control cabinet 50 in real time via a wireless network to ensure the timeliness and reliability of data transmission. Using a mobile network or WIFI connection, real-time data transmission can be achieved in any network coverage area. The control cabinet 50 serves as a data aggregation center, receiving and collating data from multiple monitoring devices 20, and then transmitting it to the power plant server 40. This process ensures centralized management and analysis of data. The background control module 30 can uniformly manage all monitoring devices 20, facilitate real-time modification of parameters such as alarm thresholds and regular measurement times, and improve the flexibility and responsiveness of the system.

[0068] The power module 22 includes a power interface and a battery. The power module 22 includes a multifunctional power interface that can be connected to a fixed power source and a rechargeable battery. This design allows the monitoring device 20 to flexibly switch power supply modes under different circumstances to ensure the continuous operation of the device in various environments. The power acquisition function is one of the core functions of the module. This function can monitor the remaining power of the battery in real time and transmit this information to the control processing module. Relevant information will be displayed on the user interface to facilitate the operator to understand the power status of the device in a timely manner and take appropriate measures. The charging management unit uses an integrated charging management device to provide the following functions:

[0069] Charging mode selection: You can select the appropriate charging mode according to different types of batteries (such as lithium batteries, nickel-metal hydride batteries, etc.) to improve charging efficiency and extend battery life.

[0070] Charging time management: Automatically adjust charging time according to battery status to avoid overcharging and over-discharging.

[0071] Temperature control: Real-time monitoring of battery temperature to ensure charging within a safe range and prevent battery damage or safety hazards caused by overtemperature.

[0072] The voltage conversion function can convert the input voltage of the rechargeable battery pack or fixed power supply into the voltage required by each functional module. This function ensures that different modules can operate under stable voltage conditions and improves the overall reliability of the system.

[0073] Detection module 23, the detection module 23 is used to detect the dose rate of each area of ​​the nuclear power plant. The dose rate refers to the energy deposited on a unit mass object per unit time, which is usually used to indicate the strength of the radiation field. The unit is gray / hour (Gy / h) or rad / hour (rad / h), and can also be converted into an effective dose rate sievert / hour (Sv / h) taking into account the radiation weight factor of human tissues and organs. In general, the larger the dose rate, the more significant the radiation effect. The detection module 23 is composed of two Geiger tube detectors with high and low ranges. By using the two Geiger tube detectors with high and low ranges, the system can automatically switch the range according to the dose rate in different areas. This design ensures that accurate measurement data can be obtained at different radiation levels, avoiding data distortion caused by improper range. In addition to the detector, the radiation unit module is also equipped with a probe main control circuit and a high-voltage circuit. The probe main control circuit is responsible for reading the working status and parameter settings of the probe, such as sensitivity, measurement range, etc. It ensures that the detector works in the best state and can monitor the operation of the detector in real time. The high-voltage circuit provides a stable high-voltage power supply for the Geiger tube detector. Geiger tube detectors require high voltage to produce a measurable ionization signal, so the design and stability of the high voltage circuit are critical.

[0074] The clock module 24, the monitoring device 20 starts the detection according to the time information of the clock module 24. The clock module 24 is mainly used to provide a clock signal to the processing control module 28 for sending start and stop signals and obtaining timestamps when transmitting data. The clock module 24 can be built into the processing control module 28. The clock module 24 is used to realize the periodic measurement function, which can be realized by the internal electronics module of the measuring device, or a timed start module can be added to the existing measuring device, and the timed start module provides a power-on signal to the original device, or a physical function of timed start is added, that is, the function of the physical switch is realized by using a circuit to control the mechanical structure.

[0075] The human-computer interaction module 25, the monitoring device 20 starts detection according to the interaction information of the human-computer interaction module 25. The human-computer interaction module 25 is mainly the key interaction, screen touch exchange, alarm control and display unit of the device, and its main functions are information input and information reading. The user inputs commands or sets parameters through physical buttons. These buttons can be used to start or stop monitoring, or adjust the working mode of the device. For devices equipped with a touch screen, users can intuitively select functions and input data through gestures such as touch and slide. This interaction method is usually more flexible and convenient.

[0076] Storage module 26, the storage module 26 is used to store the radiation information. The measured radiation data is recorded in real time to ensure that all information is accurately saved. When the external communication network fails, the data can be saved in the device to avoid data loss. The data is backed up regularly so that it can be restored and analyzed when necessary to ensure the security and integrity of the data. After the network is restored, the storage module 26 can automatically upload the stored data to the monitoring platform 10 to ensure the real-time nature of the information. The user can also choose to manually export the data for further analysis and recording.

[0077] The switching module 27 is used to switch the monitoring device 20 between the detection mode and the standby mode, and the power of the standby mode is less than the power of the detection mode. After the current measurement is completed, it enters the low power consumption mode to save power and wait for the next measurement start signal. The switching module 27 can be set in the communication module 21. The detection mode device runs to perform radiation monitoring and provide real-time data. The standby mode reduces power consumption, keeps the device in a low energy state, and extends the usable time. After each measurement, the device automatically switches to a low power consumption state and waits for the start signal of the next measurement, thereby saving power. The switching module 27 can be combined with the communication module 21 to ensure that the device can effectively manage data upload and network connection when switching modes.

[0078] The detection mode is configured so that the monitoring device 20 in the detection mode starts detection to obtain the radiation information and transmits it to the monitoring platform 10, and the standby mode is configured so that the monitoring device 20 in the standby mode turns off the detection module 23 and switches the communication module 21 to a low power consumption mode.

[0079] The monitoring device 20 automatically starts the detection function in the detection mode and obtains radiation information in real time. The radiation information obtained will be immediately transmitted to the monitoring platform 10 to ensure the real-time and accuracy of the data. In this mode, the device can continuously monitor and promptly feedback environmental changes.

[0080] In standby mode, the monitoring device 20 will turn off the detection module 23 and stop acquiring radiation data to save energy. At the same time, the communication module 21 will switch to low power mode to reduce power consumption and extend the use time of the device. The standby mode keeps the device in a ready state and can quickly respond to the start signal of the next measurement. Through such a design, the device can effectively manage resources in different working states, ensuring that it can quickly switch to the working state when needed, while maintaining low energy consumption when not working.

[0081] The structural module mainly includes a screen, buttons, a housing and a bracket module. The screen is used to display the measurement data and equipment status in real time, providing a user-friendly interface. Through button operation, the user can easily turn on and off the continuous measurement function to improve the convenience of use. The bracket module includes straps and brackets, which are used to firmly fix the device in various environments. The straps are suitable for pipe fixation, and the bracket can be lifted off the ground to meet different height requirements. The bracket can be a tripod or a telescopic rod, which can meet the continuous measurement requirements of high areas and the outer wall of the pipeline. In addition to the bracket, the device can also be fixed using cable ties, pipe clamps, etc. to ensure the stability of the device in various measurement scenarios.

[0082] The processing control module 28 is mainly used for collecting, analyzing and processing radiation measurement signals and electrical quantities, processing clock signals and start-up standby signals, and can control the voltage output of each circuit, display screen, sound and light alarm, wireless communication, key response, and complete data management and parameter management functions.

[0083] The radiation measurement system also includes a background control module 30. All monitoring devices 20 are centrally controlled by the background control module 30, which can control the start and stop of a single / multiple devices, the modification of alarm thresholds, measurement cycle time and other parameters, monitor the operation of each device, read the historical measurement data of each device, etc. These control and modification functions can also be realized on the device through the touch screen and buttons. The functions of the background control module 30 can be integrated into the radiation monitoring platform 10.

[0084] The present invention also proposes a radiation measurement method, which is applied to the radiation measurement system as described above, wherein the monitoring device 20 performs the following steps:

[0085] Obtain time information; the monitoring device 20 first obtains the current time information to provide a basis for subsequent operations. Start detection according to the time information to obtain the radiation information; according to the acquired time information, the device starts detection at a fixed time to obtain radiation information. Send the radiation information to the monitoring platform 10. After the measurement is completed, the obtained radiation information will be sent to the monitoring platform 10 to achieve real-time data updating. The monitoring device 20 is set to start every 7 days, and the single measurement time is 15 minutes to ensure continuous monitoring and effective management of radiation levels. In this way, efficient and regular radiation monitoring can be achieved to ensure the accuracy and timeliness of the data.

[0086] The present invention also proposes a radiation measurement method, which is applied to the radiation measurement system as described above, wherein the monitoring device 20 is arranged in a hot spot area, and the monitoring device 20 performs the following steps:

[0087] Get the startup information; the monitoring device 20 first gets the startup information for subsequent detection. Start the detection according to the startup information to continuously obtain the radiation information; according to the startup information, the device starts continuous detection to obtain radiation information in real time. Send the radiation information to the monitoring platform 10. Arrange the monitoring device 20 in the room or pipeline where the hotspot is located, start continuous measurement, and the device sends measurement data to the server once per second. During the operation of the nuclear power plant, the dose rate in a certain area increases significantly due to the accumulation of activated corrosion products or transient operation. This area is called a hotspot. The monitoring device 20 is arranged in the hotspot area of ​​the nuclear power plant, such as a specific room or pipeline, to deal with the increase in dose rate caused by activated corrosion products or transient operation. In this way, the radiation changes in the hotspot area can be identified and monitored in a timely manner to ensure safe management.

[0088] The present invention also proposes a radiation measurement method, which is applied to the radiation measurement system as described above, wherein the monitoring device 20 performs the following steps:

[0089] The monitoring device 20 first obtains the control information sent by the monitoring platform 10 to determine when to start the detection and the detection time. The detection is started according to the control information to obtain the radiation information; the radiation information is sent to the monitoring platform 10. The monitoring device 20 is arranged at a fixed measurement site. When the monitoring platform 10 determines that the measurement conditions are met, the background control module 30 uniformly starts the measurement software to start the measurement. After the measurement is completed, the device enters the standby state. When the next power platform has the measurement conditions, the background control module 30 uniformly starts the measurement software again to start the measurement.

[0090] The present invention proposes a radiation measurement system and method, wherein the monitoring device 20 can automatically transmit measurement data, replacing the manual weekly measurement of traditional nuclear power plants. This not only reduces the workload of radiation protection workers and reduces their exposure dose, but also reduces data storage errors caused by human errors. The device automatically starts regularly according to the measurement requirements, and automatically enters the standby state after the measurement is completed, which greatly reduces the energy consumption of the device and improves the energy utilization efficiency. The device can continuously measure high-dose and high-change rate radiation fields, solving the problem of lack of dedicated measurement equipment for transient radiation fields in nuclear power plants. This capability ensures that accurate radiation data can be obtained even under extreme conditions. The design of the self-contained bracket module enables the device to be flexibly arranged on various pipelines, equipment surfaces and different heights in the nuclear power plant, adapting to different monitoring scenarios and expanding the scope of application. All monitoring devices 20 can be uniformly controlled by the background software, and users can conveniently modify basic parameters such as alarm thresholds, measurement cycles and measurement durations according to actual measurement requirements, thereby improving the flexibility and operability of the system. The regional dose rate radiation measurement data is transmitted to the radiation monitoring platform 10 via a wireless network and a wired network to ensure the unified storage, analysis and application of the data. This dual transmission mode improves the system's reliability and anti-interference ability.

[0091] The above embodiments are only illustrative of the principles and effects of the present invention, and are not intended to limit the present invention. Anyone familiar with this technology may modify or change the above embodiments without violating the spirit and scope of the present invention. Therefore, all equivalent modifications or changes made by those with ordinary knowledge in the relevant technical field without departing from the spirit and technical ideas disclosed by the present invention should still be covered by the claims of the present invention. Efficiently realize the connection between the high voltage of the motor and the high voltage of the controller, small size, oil-resistant sealing design, reliable sealing of the controller cavity and the motor cavity, oil cooling design of the radiation measurement system and method, effectively reduce the temperature, achieve greater flow and increase product life.

[0092] In the description herein, many specific details, such as examples of components and / or methods, are provided to provide a complete understanding of embodiments of the present invention. However, those skilled in the art will recognize that embodiments of the present invention may be practiced without one or more of the specific details or with other devices, systems, components, methods, components, materials, parts, etc. In other cases, well-known structures, materials, or operations are not specifically shown or described in detail to avoid obscuring aspects of embodiments of the present invention.

[0093] References throughout this specification to "one embodiment," "an embodiment," or "a specific embodiment" mean that a particular feature, structure, or characteristic described in connection with the embodiment is included in at least one embodiment of the invention, and not necessarily in all embodiments. Thus, various appearances of the phrases "in one embodiment," "in an embodiment," or "in a specific embodiment" in different places throughout this specification do not necessarily refer to the same embodiment. In addition, the particular features, structures, or characteristics of any specific embodiment of the invention may be combined with one or more other embodiments in any suitable manner. It should be understood that other variations and modifications of the embodiments of the invention described and illustrated herein may be possible in light of the teachings herein and are to be considered part of the spirit and scope of the invention.

[0094] It should also be understood that one or more of the elements shown in the figures may also be implemented in a more separate or more integrated manner, or even removed because they are inoperable in certain circumstances or provided because they may be useful depending on the application.

[0095] In addition, unless otherwise explicitly indicated, any marking arrows in the drawings should be regarded as exemplary only and not limiting. In addition, unless otherwise indicated, the term "or" used herein is generally intended to mean "and / or". In the case where the term is not clear because it is anticipated that the ability to separate or combine is provided, the combination of components or steps will also be regarded as indicated.

[0096] As used in the description herein and throughout the claims that follow, "a", "an", and "the" include plural references unless otherwise indicated. Likewise, as used in the description herein and throughout the claims that follow, the meaning of "in" includes "in" and "on" unless otherwise indicated.

[0097] The above description of the illustrated embodiments of the present invention (including the contents described in the Abstract) is not intended to be an exhaustive list or to limit the present invention to the precise form disclosed herein. Although specific embodiments of the present invention and examples of the present invention are described herein for illustrative purposes only, various equivalent modifications are possible within the spirit and scope of the present invention as will be recognized and appreciated by those skilled in the art. As noted, these modifications may be made to the present invention in accordance with the above description of the embodiments described in the present invention, and these modifications will be within the spirit and scope of the present invention.

[0098] Systems and methods have been generally described herein as details that aid in understanding the present invention. In addition, various specific details have been given to provide an overall understanding of embodiments of the present invention. However, those skilled in the relevant art will recognize that embodiments of the present invention may be practiced without one or more of the specific details, or may be practiced using other devices, systems, accessories, methods, components, materials, parts, etc. In other cases, well-known structures, materials, and / or operations are not specifically shown or described in detail to avoid confusion with various aspects of embodiments of the present invention.

[0099] Thus, although the invention has been described herein with reference to specific embodiments thereof, freedom of modification, various changes and substitutions are also within the foregoing disclosure, and it should be understood that in some cases, some features of the invention will be employed without the corresponding use of other features without departing from the scope and spirit of the proposed invention. Thus, many modifications may be made to adapt a particular environment or material to the essential scope and spirit of the invention. The invention is not intended to be limited to the specific terms used in the claims below and / or the specific embodiments disclosed as the best mode contemplated for carrying out the invention, but the invention will include any and all embodiments and equivalents falling within the scope of the appended claims. Thus, the scope of the invention will be determined solely by the appended claims.

Claims

1. A radiation measurement system, applied to a nuclear power plant, characterized in that: include: Monitoring equipment, wherein a plurality of monitoring equipment are provided, and the monitoring equipment is used to detect radiation information of various areas of the nuclear power plant; A monitoring platform is communicatively connected with the monitoring device, and the monitoring platform is used to store and process the radiation information.

2. The radiation measurement system according to claim 1, characterized in that: The monitoring device comprises a communication module for communicating with the monitoring platform, and the communication module comprises a wireless communication unit.

3. The radiation measurement system according to claim 1, characterized in that: The monitoring device comprises a power module, and the power module comprises a power interface and a battery.

4. The radiation measurement system according to claim 1, characterized in that: The monitoring device comprises a detection module, and the detection module is used to detect the dose rate of each area of ​​the nuclear power plant.

5. The radiation measurement system according to claim 1, characterized in that: The monitoring device comprises a clock module, and the monitoring device starts detection according to time information of the clock module.

6. The radiation measurement system according to claim 1, characterized in that: The monitoring device comprises a human-computer interaction module, and the monitoring device starts detection according to interaction information of the human-computer interaction module.

7. The radiation measurement system according to claim 1, characterized in that: The monitoring device comprises a storage module, and the storage module is used to store the radiation information.

8. The radiation measurement system according to claim 1, characterized in that: The monitoring device comprises a switching module, and the switching module is used to switch the monitoring device between a detection mode and a standby mode, wherein the power of the standby mode is less than the power of the detection mode.

9. The radiation measurement system according to claim 8, characterized in that: The detection mode is configured so that the monitoring device in the detection mode starts detection to obtain the radiation information and transmits it to the monitoring platform, and the standby mode is configured so that the monitoring device in the standby mode turns off the detection module and switches the communication module to a low power consumption mode.

10. The radiation measurement system according to claim 1, characterized in that: It also includes a strap or a bracket, wherein the strap is used to fix the monitoring device to the pipeline, and the bracket is used to fix the monitoring device and lift it off the ground, and the bracket has different heights.

11. A radiation measurement method, applied to the radiation measurement system according to any one of claims 1 to 10, characterized in that: The monitoring device performs the following steps: Get time information; Initiate detection according to the time information to obtain the radiation information; The radiation information is sent to the monitoring platform.

12. A radiation measurement method, applied to the radiation measurement system according to any one of claims 1 to 10, characterized in that: The monitoring device is set in the hot spot area, and the monitoring device performs the following steps: Get startup information; Initiate detection according to the startup information to continuously obtain the radiation information; The radiation information is sent to the monitoring platform.

13. A radiation measurement method, applied to the radiation measurement system according to any one of claims 1 to 10, characterized in that: The monitoring device performs the following steps: Obtaining control information sent by the monitoring platform; Initiate detection according to the control information to obtain the radiation information; The radiation information is sent to the monitoring platform.

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