A dynamic radiation protection method and management system for isotope production

Abstract

This invention belongs to the field of nuclear reactor radiation protection technology, specifically relating to a dynamic radiation protection method and management system for isotope production. The invention first queries a radiation field-operating condition mapping database based on the identification information of the isotope target to predict the location and intensity of radiation hotspots. Based on the predicted radiation field distribution data, a protection command is generated, driving a movable shield to move to the predicted radiation hotspot area, forming a locally enhanced shield. Radiation data is collected in real time by radiation detectors deployed at key nodes in the process path. The real-time monitoring data is fused and compared with the predicted data to verify the protection effect and to trigger alarms for abnormal situations. Based on the comparison results of real-time radiation data and preset thresholds, the opening and closing of the channel control device is automatically controlled, and a safe detour path is displayed through a visual guidance device. This invention breaks through the design conventions of fixed shields, achieving optimal allocation of shielding resources.

Description

Technical Field

[0001] This invention belongs to the field of nuclear reactor radiation protection technology, specifically relating to a dynamic radiation protection method and management system for isotope production. Background Technology

[0002] High-temperature gas-cooled reactors (HTGRs) offer the unique advantage of continuous refueling without reactor shutdown, providing a crucial edge for the continuous production of medical and industrial radioisotopes. However, this continuous operation also presents new radiation protection challenges: the radioactivity of isotope targets extracted from the reactor-side reflector varies significantly depending on the nuclide type and irradiation history, resulting in a dynamic radiation field from the extraction port and transport channels to the hot chamber and storage area. Traditional radiation protection relies on fixed physical shielding and periodic area dose monitoring, a static and passive approach that cannot adapt to such dynamic changes.

[0003] Specifically, existing protection methods have conservative and rigid shielding designs. Fixed shields designed to deal with worst-case scenarios (such as targets with the highest activity) are cumbersome and inefficient when dealing with targets with low activity, increasing operational inconvenience and costs.

[0004] Secondly, existing protection process management relies on human experience. The judgment of regional radiation levels and the planning of personnel passage routes depend to a large extent on the experience of operators and static monitoring data, lacking real-time, system-level intelligent decision support, and thus posing a risk of human error.

[0005] Meanwhile, the existing protection system is slow to respond. When local radiation hotspots appear, traditional methods are not able to take timely and accurate measures to strengthen shielding or isolate areas, which may result in staff being exposed to unnecessary radiation. Summary of the Invention

[0006] The present invention aims to at least partially solve one of the technical problems in the related art.

[0007] Therefore, the first objective of this invention is to provide a dynamic radiation protection method for isotope production, comprising the following steps:

[0008] S1. Based on the identification information of the isotope target to be processed, query the radiation field-operating condition mapping database to obtain the corresponding predicted radiation field distribution data and predict the location and intensity of the radiation hotspots. S2 generates protection commands based on predicted radiation field distribution data, driving the movable shield to move to the predicted radiation hotspot area to form a localized enhanced shield. S3 collects radiation data in real time by deploying radiation detectors at key nodes in the process path, and fuses and compares the real-time monitoring data with the predicted data to verify the protection effect and handle alarms for abnormal situations. S4. Based on the comparison results of real-time radiation data and preset thresholds, the channel control device is automatically opened and closed, and a safe detour path is displayed through a visual guidance device.

[0009] In one embodiment of the present invention, S1 includes: S11, read the UHF RFID tag on the isotope target to be processed through the radio frequency identification reading device, obtain the UHF RFID tag information, and use its ID as the target identifier; S12, using the target identifier as an index, query the radiation field-operating condition mapping database to retrieve preset radiation field distribution data corresponding to the nuclide type and activity; S13, based on the retrieved preset radiation field distribution data, predict the location and intensity of radiation hotspots at key nodes in the process flow of the isotope target to be processed.

[0010] In one embodiment of the present invention, the radiation field-condition mapping database queried in S12 includes: The three-dimensional dose rate distribution data constructed based on the Monte Carlo particle transport calculation method is associated with a condition identifier, which includes nuclide type, activity level, and process node information. The Monte Carlo particle transport calculation formula is as follows: ; ; in, r For spatial location, T It is a nuclide type. A For activity level, P For process nodes, N To determine the total number of particles sampled in the Monte Carlo simulation. Let i be the statistical weight of the i-th particle. V To calculate the volume of a volume element, For energy E The corresponding dose conversion factor, E It refers to particle energy.

[0011] In one embodiment of the present invention, S2 includes: S21, generate a protection command based on the coordinates of radiation hotspots in the predicted radiation field distribution data, the protection command including the target location coordinates and standby or movement action command; S22, the protection command is sent to the movable shield deployed near the transmission channel via the wireless communication network, and the movable shield is driven to move along the pre-embedded guide rail to the track coordinate point corresponding to the predicted radiation hotspot location; S23, after the movable shield reaches the designated position, it forms a locally reinforced shield.

[0012] In one embodiment of the present invention, S3 includes: S31 collects radiation dose rate data in real time through radiation detectors deployed at key nodes in the process path; S32 transmits the real-time collected radiation dose rate data to the central processing unit via an industrial Ethernet bus. S33, in the central processing unit, the real-time monitoring data is fused and compared with the predicted radiation field distribution data obtained by S1, and the prediction deviation value is calculated. S34, when the predicted deviation value exceeds the preset deviation threshold, an abnormal alarm is triggered and an alarm message is generated.

[0013] In one embodiment of the present invention, S4 includes: S41 compares the real-time collected radiation dose rate data with the preset action threshold; S42, when the real-time dose rate of any critical node exceeds the preset action threshold, a locking signal is sent to the access controller of the corresponding channel to physically prevent the channel door lock from opening; S43, at the same time, triggers the visual guidance device to display the dynamically generated detour path, and explains the reason for the closure and the estimated detour time through text prompts.

[0014] S44, When the monitoring network data shows that the dose rate in the relevant area has returned to below the background level, the locking status of the access control will be automatically released; S45 commands the movable shield to return to the standby position and restores the human-machine interface to normal status.

[0015] To achieve the above objectives, a second aspect of the present invention provides a dynamic radiation protection system for isotope production, comprising: The radiation field prediction module is used to query the radiation field-operating condition mapping database based on the identification information of the isotope target to be processed, obtain the predicted radiation field distribution data, and predict the location and intensity of radiation hotspots. The mobile shielding control module generates protection commands based on predicted radiation field distribution data, driving the movable shield to move to the radiation hotspot area to form localized enhanced shielding. The monitoring and verification module collects radiation data from key nodes in the process path in real time through radiation detectors, merges and compares the real-time monitoring data with the predicted data, and triggers anomaly alarms. The safety guidance module controls the opening and closing of the channel control device based on the comparison results of real-time radiation data and preset thresholds, and dynamically displays the safe detour path through the visual guidance device.

[0016] In one embodiment of the present invention, the radiation field prediction module includes: The RFID reading unit is configured to read the UHF RFID tag information on the target and extract the target ID; The database query unit retrieves preset three-dimensional dose rate distribution data with associated nuclide types and activity levels using the target ID as an index. The hotspot prediction unit predicts radiation hotspot parameters at key nodes in the process flow based on three-dimensional dose rate distribution data.

[0017] In one embodiment of the present invention, the mobile shielding control module includes: The instruction generation unit generates control signals containing target position and movement instructions based on the coordinates of the radiation hotspots. The communication execution unit drives the movable shield to move along the pre-embedded guide rail to the specified track coordinates via a wireless network. The shielding confirmation unit activates the locally reinforced shielding structure after the movable shielding body is in place.

[0018] To achieve the above objectives, a third aspect of the present invention provides a computer-readable storage medium storing a computer program that, when executed by a processor, implements the method described in the first aspect.

[0019] The method, system, and storage medium of this invention, by constructing a closed-loop control system of radiation field prediction-real-time monitoring-intelligent response, achieve accurate prediction and active protection of dynamically changing radiation fields. At the same time, it deeply integrates personnel access control with radiation data and automatically plans safe passage paths, effectively solving the technical problem that traditional static protection cannot adapt to dynamic changes in radiation fields.

[0020] Additional aspects and advantages of the invention will be set forth in part in the description which follows, and in part will be obvious from the description, or may be learned by practice of the invention. Attached Figure Description

[0021] The above and / or additional aspects and advantages of the present invention will become apparent and readily understood from the following description of the embodiments taken in conjunction with the accompanying drawings, wherein: Figure 1 This is a flowchart of a dynamic radiation protection and optimization method for non-stop isotope production according to an embodiment of the present invention; Figure 2 This is an overall architecture diagram of a dynamic radiation protection and optimization method for non-stop isotope production according to an embodiment of the present invention; Figure 3 This is a schematic diagram of the effect of an intelligent radiation monitoring network for a dynamic radiation protection and optimization method for non-stop isotope production according to an embodiment of the present invention.

[0022] Figure 4This is a schematic diagram of the deployment of a movable auxiliary shielding body next to a transmission channel, which is a dynamic radiation protection and optimization method for non-stop isotope production according to an embodiment of the present invention. Detailed Implementation

[0023] It should be noted that, unless otherwise specified, the embodiments and features described in the present invention can be combined with each other. The present invention will now be described in detail with reference to the accompanying drawings and embodiments.

[0024] To enable those skilled in the art to better understand the present invention, the technical solutions of the present invention will be clearly and completely described below with reference to the accompanying drawings of the embodiments of the present invention. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort should fall within the scope of protection of the present invention.

[0025] The following description, with reference to the accompanying drawings, describes a dynamic radiation protection method and management system for isotope production according to an embodiment of the present invention.

[0026] Example 1 Figure 1 This is a flowchart of a dynamic radiation protection and optimization method for non-stop isotope production according to an embodiment of the present invention.

[0027] like Figure 1 As shown, the dynamic radiation protection and optimization method for non-stop reactor isotope production includes the following steps: S1. Based on the identification information of the isotope target to be processed, query the radiation field-operating condition mapping database to obtain the corresponding predicted radiation field distribution data and predict the location and intensity of radiation hotspots. This invention first acquires the identification information of the isotope target to be processed. This identification information includes key parameters such as nuclide type, activity level, and decommissioning time, serving as a crucial index for subsequent radiation field prediction. The system uses this identification information as a query condition to retrieve predicted radiation field distribution data matching the current target's operating conditions from a pre-constructed radiation field-operating condition mapping database. This database stores the three-dimensional spatial distribution of radiation fields generated by targets with different nuclide types and activity levels at various stages of the process, including key data such as gamma-ray dose rate distribution and neutron fluence rate distribution. Through query matching, the system can predict the possible location coordinates of radiation hotspots and their corresponding radiation intensities, thus providing data support for subsequent protection decisions.

[0028] In one specific implementation, an RFID tag or barcode can be attached to the target container to store information such as nuclide type, activity, and decommissioning time. After acquiring this identification information through a reading device, the system queries the radiation field-condition mapping database using nuclide type and activity as indexes. Each record in the database is associated with a specific condition identifier, such as "Ir-192 mid-transmission" or "Co-60 hot cell storage," and stores the corresponding three-dimensional dose rate distribution cloud map. The query results can predict the surrounding dose rate distribution of the target when it reaches each critical node in the process flow. For example, it can predict that when a Co-60 target with an activity of 1.0E14Bq is transmitted to a specific coordinate point, the dose rate within 1 meter around it will rise to 500 μSv / h.

[0029] This step enables the early prediction of radiation fields, transforming the protection system from a passive response to an active prevention approach. It allows for the understanding of radiation field distribution trends before new targets are removed from the reactor, providing a basis for decision-making in the forward-looking deployment of protective measures and minimizing the risk of personnel being exposed to unnecessary radiation.

[0030] S2 generates protection commands based on the predicted radiation field distribution data, driving the movable shield to move to the predicted radiation hotspot area to form a localized enhanced shield.

[0031] Based on the predicted radiation field distribution data, a protection command is generated, driving the movable shield to move to the predicted radiation hotspot area, forming a locally enhanced shield. This step involves the central processing unit analyzing the predicted radiation field data obtained in step S1, identifying key areas requiring enhanced protection, and generating a protection command containing target location coordinates and motion parameters. The protection command is sent via a wireless communication network to the movable shield deployed on a track system along the process path. Upon receiving the command, the shield is autonomously moved to the designated position by the drive control system according to a preset motion trajectory, forming a locally enhanced shield for the radiation hotspot area. In one implementation, the central processing unit uses the dose rate peak position in the predicted radiation field distribution data as the target point, generates a protection command containing track coordinates, and sends it to the corresponding movable shield. The shield moves along the track to the coordinate position and then performs the shielding task.

[0032] This technical step achieves precise matching of protective resources with dynamic radiation fields, transforming passive static protection into proactive and forward-looking protection, and significantly reducing the risk of exposure to workers in radiation hotspot areas.

[0033] S3 collects radiation data in real time by deploying radiation detectors at key nodes in the process path, and then fuses and compares the real-time monitoring data with the predicted data to verify the protection effect and handle alarms for abnormal situations.

[0034] like Figure 4As shown, by deploying radiation detectors at key nodes in the isotope production process, real-time sensing and data acquisition of the on-site radiation status are achieved. These detectors continuously monitor the radiation dose rate and transmit the collected data to the central processing unit. The real-time monitoring data is fused and compared with the predicted data pre-stored in the radiation field-condition mapping database. Based on this, the system evaluates the actual effectiveness of the deployed protective measures and determines whether the protection has achieved the expected goals. When there is a significant deviation between the real-time monitoring data and the predicted data, or when the dose rate in a certain area exceeds a preset safety threshold, the system automatically executes an alarm processing procedure, generates a warning signal, and triggers the corresponding emergency response mechanism. As a specific implementation method, a range coverage is selected. ~ The gamma dose rate probe, in conjunction with the He proportional counter neutron detector, is arranged according to the principle of redundancy coverage of key nodes, at locations such as outside the shielding door of the feed port, every 5 meters along the transmission pipeline, at the entrance of the hot chamber operating room, and on the main operating surface. All detectors transmit digital signals in real time to the central processing unit for data fusion and comparison analysis via the field industrial Ethernet bus.

[0035] This step achieves closed-loop verification of the protective effect, ensuring that the actual effectiveness of the dynamic shielding measures can be quantitatively evaluated. At the same time, the abnormal alarm mechanism can promptly detect sudden changes in the radiation field or prediction deviations, effectively preventing the risk of radiation leakage and ensuring the safety of on-site personnel and the environment.

[0036] S4. Based on the comparison results of real-time radiation data and preset thresholds, the channel control device is automatically opened and closed, and a safe detour path is displayed through a visual guidance device.

[0037] After comparing real-time radiation monitoring data with preset thresholds, the system automatically executes channel control and personnel guidance operations based on the comparison results to achieve dynamic access control and safe path planning. Regarding channel control, the system compares radiation monitoring data with preset action thresholds. When the real-time dose rate in a certain area exceeds the preset safety threshold, the central processing unit sends a control command to the corresponding channel control device, driving the device to close or lock, physically preventing personnel from entering high-radiation areas. Simultaneously, the system continuously monitors changes in radiation levels in the relevant areas. When the dose rate falls below the safety threshold, it automatically sends an unlock command to restore normal passage. For visual guidance, the system triggers the visual guidance device to operate simultaneously with the channel control device's closing operation. Based on real-time radiation field distribution data, it dynamically generates and displays safe detour routes, providing text prompts and route diagrams to staff via electronic displays to guide them away from high-radiation areas. As a specific implementation method, the system can employ a linkage mechanism between the access control system and radiation detectors. When the detector detects a dose rate exceeding 100 μSv / h, it sends a locking signal to the access control system to prevent the door from opening. Simultaneously, it displays a message on the electronic display board such as "Due to high radiation activity, Route A is temporarily closed. Please proceed to your destination via Corridor B." It can also trigger a vibration or audible alert from the personnel's personal electronic dosimeter. This step achieves deep integration of radiation safety and personnel flow management. By using real-time dose data as the basis for access control and route planning decisions, it automatically isolates high-risk areas and dynamically generates safe routes, fundamentally eliminating the possibility of personnel accidentally entering high-dose areas and ensuring that staff are always under optimal radiation protection conditions.

[0038] Example 2 like Figure 2 As shown, based on the above embodiments, this embodiment provides a detailed description of the specific implementation of step S1 in the dynamic radiation protection and optimization method for non-stop isotope production: "Query the radiation field-operating condition mapping database according to the identification information of the isotope target to be processed, obtain the corresponding predicted radiation field distribution data, and predict the location and intensity of radiation hotspots."

[0039] S11: Read the ultra-high frequency radio frequency identification tag on the isotope target to be processed through the radio frequency identification reading device to obtain a unique identifier containing information on nuclide type, activity and decomposition time.

[0040] In this embodiment, an ultra-high frequency radio frequency identification (UHF) reader is deployed near the shielding door of the isotope sampling port. Its operating frequency is 860MHz to 960MHz, and its reading distance can reach 3 meters. After the irradiated isotope target is removed from the core-side reflector, the UHF RFID tag fixed to the surface of the target container enters the sensing area of ​​the reader. The reader activates the tag via radio frequency signals and receives its stored data. The unique identifier stored inside the tag includes a nuclide type field (such as Ir-192, Co-60, Mo-99, etc.), an activity value field (in Bq), and a timestamp field for exiting the reactor. The reader transmits this unique identifier to the central intelligent processing and control unit via an industrial Ethernet bus, completing the input data preparation for the operating condition identification and prediction activation steps.

[0041] S12: Use the unique identifier as an index to query the radiation field-condition mapping database and retrieve the preset radiation field distribution data corresponding to the nuclide type and activity.

[0042] As one implementation method, the radiation field-condition mapping database is constructed based on the Monte Carlo particle transport calculation method, and pre-computed three-dimensional detailed modeling and simulation calculations are performed on the physical space involved in the entire isotope production process. The three-dimensional dose rate distribution data in the database are associated with condition identifiers, which specifically include three dimensions: nuclide type, activity level, and process node information. The specific calculation formula is as follows:

[0043] ; In the formula, This represents the three-dimensional dose rate (unit: Sv / h) at spatial location r under the corresponding operating condition identifier, where T It is a nuclide type. A For activity level, P For process nodes, database index matching is achieved by directly associating them with operating condition identifiers. This represents the position r, energy E, and particle flux (particles / (cm²·s)) under the corresponding operating condition, the value of which is determined by the nuclide type. T Activity level A process nodes P Joint decision; N The total number of particles sampled in the Monte Carlo simulation is adjusted according to the space complexity corresponding to process node P. For the first i The statistical weight of particle number T is related to the particle decay characteristics corresponding to nuclide type T. For the first i The track length of particle number r within the computational volume element is affected by the spatial modeling of process node P and the particle transport characteristics of nuclide type T. VTo calculate the volume of a volume element, the process node is used. P The corresponding detailed 3D modeling is determined; This is the dose conversion coefficient corresponding to energy E, which corresponds one-to-one with the nuclide type T. E The particle energy is determined by the decay characteristics of nuclide type T.

[0044] The process nodes cover key locations such as the middle section of the transmission pipeline, the hot chamber operating platform, and the storage pool. Once the central intelligent processing and control unit receives a unique identifier, it performs a rapid query in the database using nuclide type and activity as composite index conditions to obtain the preset three-dimensional dose rate distribution cloud map data of the target at each process node. This data is stored with a 0.1-meter precision grid and includes dose rate values ​​and location coordinates for each spatial location, serving as input data for subsequent radiation hotspot prediction.

[0045] S13: Based on the retrieved preset radiation field distribution data, predict the location and intensity of radiation hotspots at key nodes in the process flow of the isotope target to be processed.

[0046] The central intelligent processing and control unit analyzes the retrieved three-dimensional dose rate distribution data, identifies spatial areas where the dose rate exceeds a preset threshold, and marks these areas as predicted radiation hotspots. The system further combines this with the real-time location information of the target within the process flow to predict the peak dose rate within a 1-meter radius of the target when it moves to each key node, along with its corresponding geographic coordinates. For example, for an activity of 1.0 × e-1... 14 For the Co-60 target of Bq, the system predicts that the dose rate within 1 meter around the target will rise to 500 μSv / h when it is transmitted to the coordinate point (X1, Y1, Z1). This prediction result is output in the form of spatial coordinates and dose rate values, serving as the basis for generating protection commands in step S2.

[0047] This embodiment uses UHF RFID technology to automatically collect target information and combines it with a pre-built radiation field-operating condition mapping database for rapid data retrieval and hotspot prediction, enabling the forward-looking deployment of protective measures and upgrading radiation safety management from passive response to proactive prevention.

[0048] Example 3 Based on the above embodiments, this embodiment provides a detailed description of the specific implementation of step S2 in the dynamic radiation protection and optimization method for non-stop isotope production: "Generate protection instructions based on predicted radiation field distribution data, drive the movable shield to move to the predicted radiation hotspot area, and form a local enhanced shield."

[0049] In step S21, the central intelligent processing and control unit extracts the coordinate information of radiation hotspot locations based on the predicted radiation field distribution data obtained in step S1. Specifically, the predicted radiation field distribution data includes a dose rate distribution cloud map in three-dimensional space. The system automatically identifies the coordinates of areas where the dose rate exceeds a preset action threshold and generates a protection command containing the target location coordinates and action instructions. This protection command uses a structured data format, where the target location coordinates correspond to the track coordinates of the predicted radiation hotspot on the pre-embedded guide rail, and the action instructions include two types: "standby" or "move". When the prediction shows that the target is about to enter a certain area, the system generates a "move" command; when the target has safely passed through and the radiation level in the area has returned to background, the system generates a "standby" or "return" command.

[0050] In step S22, the central intelligent processing and control unit sends the generated protection command to the movable shield deployed near the transmission channel via a wireless communication network. As an example, the wireless communication network uses the Wi-Fi 6 protocol, and the protection command is transmitted via an industrial local area network to the wireless communication module of the target shield module. Each movable shield module integrates a servo motor drive system, navigation sensors, and a Wi-Fi 6 wireless communication module at its bottom. After receiving the command, it analyzes the target position coordinates and drives the module to move along a pre-embedded guide rail to the designated track coordinate point. According to the following claims, the moving speed of the movable shield is set to 0.1 to 0.5 meters per second, and the positioning accuracy is at the centimeter level. The guide rail system is made of stainless steel and is pre-embedded in the ground on both sides of the transmission channel and in the personnel activity area of ​​the hot chamber operating room. The guide rail elevation is flush with the ground, so as not to affect normal personnel passage.

[0051] In step S23, the movable shield forms a locally enhanced shield after reaching the designated location. Each movable shield module has a 2mm thick stainless steel outer shell and is filled with shielding material. For gamma radiation, a lead-tungsten alloy with a density of not less than 15 grams per cubic centimeter is used, while for neutrons, boron-containing polyethylene is used. The module dimensions are designed to be 500mm x 500mm x 1000mm, and the weight of a single module is controlled to be less than 200kg. When the shield moves to the predicted radiation hotspot location, its high-density shielding material effectively blocks gamma rays, and the boron-containing polyethylene absorbs neutrons, thereby forming a locally enhanced shield in that area and reducing the dose rate level of the surrounding environment.

[0052] In summary, this invention refines the protection command into a complete command structure that includes the target location coordinates and action instructions, and combines it with a wireless communication network to achieve real-time transmission and execution of the command. With the precise movement control of the movable shield (moving speed of 0.1-0.5 m / s and centimeter-level positioning accuracy) and the local reinforcement shielding with high-density shielding material (lead-tungsten alloy density ≥15 g / cm³), it achieves the forward-looking deployment and precise execution of protection measures, effectively improving the response speed and protection effectiveness of dynamic radiation protection.

[0053] Example 4 Based on the above embodiments, this embodiment provides a detailed description of the specific implementation of step S3 in the dynamic radiation protection and optimization method for non-stop reactor isotope production: "Real-time collection of radiation data by radiation detectors deployed at key nodes in the process path, fusion and comparison of real-time monitoring data and predicted data, verification of protection effectiveness, and alarm processing for abnormal situations."

[0054] In S31, the deployment of radiation detectors follows the principle of redundancy coverage at critical nodes. As one embodiment, during data acquisition, this invention deploys two gamma dose rate probes 1 meter outside the shielding door of the isotope extraction port, providing redundancy to ensure data reliability; one gamma dose rate probe is deployed every 5 meters along the transmission pipeline to achieve continuous monitoring of the transmission path; one gamma dose rate probe and one neutron detector are deployed at the entrance, main operating surface, and exit of the hot chamber operating area to comprehensively monitor gamma and neutron radiation in the operating area; gamma dose rate probes are deployed at the entrance and key internal passages of the storage area. The gamma dose rate probes have a range covering 1 μSv / h to 1 Sv / h, and the neutron detector uses a He-3 proportional counter, capable of responding to thermal neutrons and outputting a pulse signal proportional to the neutron fluence rate. The detectors continuously collect radiation dose rate data at their locations, serving as the raw input for the real-time radiation monitoring network.

[0055] In S32, real-time acquired radiation dose rate data is transmitted to the central processing unit via an industrial Ethernet bus. Specifically, each detector is connected to an intrinsically safe signal transmitter via armored cables, converting analog signals into digital signals. These digital signals are then transmitted in real-time to the central processing unit via the field industrial Ethernet bus using the TCP / IP protocol. A redundant communication mechanism is employed during transmission to ensure data integrity and timeliness. The central processing unit receives real-time data streams from each detector, enabling continuous monitoring of the field radiation status.

[0056] In S33, the central processing unit fuses and compares the real-time monitoring data with the predicted radiation field distribution data acquired in S1 to calculate the prediction deviation value. The central processing unit first establishes a spatial mapping relationship based on the detector's position coordinates, spatially aligning the real-time data with the predicted dose rate distribution for the corresponding operating condition in the database. Then, a weighted fusion algorithm is used to fuse the real-time and predicted data, generating a fused dose rate field distribution. Finally, the deviation between the fused result and the predicted value is calculated to obtain the prediction deviation value. When the prediction deviation value is within the allowable range, the system confirms the effectiveness of the protective measures; when the deviation value exceeds a preset deviation threshold, it indicates a significant difference between the on-site radiation field and the prediction model, requiring the triggering of an anomaly handling procedure.

[0057] In S34, when the predicted deviation exceeds a preset deviation threshold, the system triggers an alarm and generates alarm information. The alarm information includes the location of the deviation, the magnitude of the deviation, the current dose rate level, and suggested response measures. The central processing unit pushes the alarm information to the graphical human-machine interface (HMI) to alert maintenance personnel via audio and visual means; simultaneously, it automatically triggers a protection strategy adjustment process, instructing movable shielding to move towards the deviation area to strengthen local shielding, and linking the access control system to block relevant passages. The alarm information is also simultaneously recorded in the system log for subsequent analysis and model optimization.

[0058] This embodiment constructs a highly reliable real-time monitoring network by redundantly deploying multiple types of detectors. Combined with real-time data transmission of industrial Ethernet and intelligent fusion comparison algorithms, it realizes closed-loop verification of the predicted protection effect, which can promptly detect radiation field anomalies and trigger alarm and response mechanisms, significantly improving the reliability and response speed of dynamic radiation protection.

[0059] Example 5 Based on the above embodiments, this embodiment provides a detailed description of the specific implementation of step S4 in the dynamic radiation protection and optimization method for non-stop reactor isotope production: "Automatically control the opening and closing of the channel control device based on the comparison results of real-time radiation data and preset thresholds, and display the safe detour path through a visual guidance device." In step S4, path planning is achieved using a fusion method of "real-time radiation field constraints + shortest path optimization." Combining the characteristics of isotope production process paths, radiation safety thresholds, and channel control logic, the specific implementation process is as follows: A radiation safety weighted AI algorithm is used, with "shortest total path length" as the basic objective and "radiation dose throughout the path is lower than the preset safety threshold" as the constraint. Real-time radiation monitoring data and predicted data from the radiation field-operating condition mapping database are fused to construct a path cost function, thereby achieving rapid planning and dynamic updating of safe detour paths. Based on the radiation protection standards for isotope production, radiation dose safety thresholds are preset for different areas. Areas in the grid nodes with real-time radiation doses higher than the preset thresholds are marked as "dangerous areas" and the path is prohibited from passing through them; areas with radiation doses lower than the thresholds are marked as "safe areas" and the path is allowed to pass through them; areas within the threshold critical range are marked as "warning areas" and serve as alternative detour areas for path planning.

[0060] In step S41, the system continuously receives real-time dose rate data from radiation detectors deployed at key nodes such as isotope sampling ports, transmission pipelines, hot chamber operating rooms, and storage areas. This data is transmitted in real-time to the central intelligent processing and control unit via an industrial Ethernet bus. The system updates the radiation status and safety costs of the grid nodes in real time, calls algorithms to solve for the shortest safe path that meets the constraints, and simultaneously, combines the on / off status of the channel control device (controlled by comparing real-time radiation data with preset thresholds: when the radiation dose in the area where the channel is located is higher than the threshold, the channel is closed and excluded from the path planning; when it is lower than the threshold, the channel remains open), dynamically adjusts the connectivity of the path nodes, and re-solves for the path.

[0061] In step S42, when the real-time dose rate of any critical node exceeds a preset action threshold, the central processing unit sends a locking signal to the access controller of the corresponding channel via its digital output module. This access controller employs a dual-mode access control system using both card swiping and facial recognition; the locking signal physically keeps the door locked, preventing personnel from entering the high-radiation area.

[0062] In step S43, the planned route is calculated in S41 and dynamically displayed on high-brightness LED electronic displays deployed at personnel passage intersections and access control points, marking the start point, end point, and intermediate nodes. Simultaneously, text prompts are provided indicating the reason for closure and the estimated detour time. At the same time, the route data is synchronized to the graphical human-machine interface. If the real-time dose rate changes, the system immediately recalculates the route and updates the display to ensure that guidance is always safe and accurate, providing clear and reliable passage guidance for staff. If an anomaly occurs in the real-time radiation field, the route is immediately replanned and updated synchronously through the guidance device, while simultaneously triggering an alarm mechanism.

[0063] Furthermore, when the monitoring network data shows that the dose rate in the relevant area returns to below the background level, i.e., below 2.5 microsieverts per hour, the central processing unit automatically executes step S44 to unlock the access control and restore normal access permissions. Subsequently, the system executes step S45 to direct the movable shield to return to the standby position along the track and restore the graphical human-machine interface from the warning state to the normal display state, completing this dynamic protection process.

[0064] This implementation method deeply integrates real-time dose data with access control and guidance systems, realizing intelligent traffic management based on real-time radiation field maps. It can automatically isolate high-risk areas and dynamically generate safe routes, fundamentally eliminating the possibility of people accidentally entering high-dose areas and achieving optimal management of personnel radiation dose.

[0065] Example 6 A dynamic radiation protection system for isotope production, the effect of which is as follows: Figure 3 As shown, including The radiation field prediction module is used to query the radiation field-operating condition mapping database based on the identification information of the isotope target to be processed, obtain the predicted radiation field distribution data, and predict the location and intensity of radiation hotspots. The mobile shielding control module generates protection commands based on predicted radiation field distribution data, driving the movable shield to move to the radiation hotspot area to form localized enhanced shielding. The monitoring and verification module collects radiation data from key nodes in the process path in real time through radiation detectors, merges and compares the real-time monitoring data with the predicted data, and triggers anomaly alarms. The safety guidance module controls the opening and closing of the channel control device based on the comparison results of real-time radiation data and preset thresholds, and dynamically displays the safe detour path through the visual guidance device.

[0066] Furthermore, the radiation field prediction module includes: The RFID reading unit is configured to read the UHF RFID tag information on the target and extract the target ID; The database query unit retrieves preset three-dimensional dose rate distribution data with associated nuclide types and activity levels using the target ID as an index. The hotspot prediction unit predicts radiation hotspot parameters at key nodes in the process flow based on three-dimensional dose rate distribution data.

[0067] Furthermore, the mobile shielding control module includes: The instruction generation unit generates control signals containing target position and movement instructions based on the coordinates of the radiation hotspots. The communication execution unit drives the movable shield to move along the pre-embedded guide rail to the specified track coordinates via a wireless network. The shielding confirmation unit activates the locally reinforced shielding structure after the movable shielding body is in place.

[0068] The present invention also provides a computer-readable storage medium storing a computer program, which, when executed by a processor, implements the above-described method for dynamic radiation protection in isotope production.

[0069] In the description of this specification, the references to terms such as "one embodiment," "some embodiments," "example," "specific example," or "some examples," etc., refer to specific features, structures, materials, or characteristics described in connection with that embodiment or example, which are included in at least one embodiment or example of the present invention. In this specification, the illustrative expressions of the above terms do not necessarily refer to the same embodiment or example. Furthermore, the specific features, structures, materials, or characteristics described may be combined in any suitable manner in one or more embodiments or examples. Moreover, without contradiction, those skilled in the art can combine and integrate the different embodiments or examples described in this specification, as well as the features of different embodiments or examples.

[0070] Furthermore, the terms "first" and "second" are used for descriptive purposes only and should not be construed as indicating or implying relative importance or implicitly specifying the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one of that feature. In the description of this invention, "a plurality of" means at least two, such as two, three, etc., unless otherwise explicitly specified.

Claims

1. A dynamic radiation protection method for isotope production, characterized in that, Includes the following steps: S1. Based on the identification information of the isotope target to be processed, query the radiation field-operating condition mapping database to obtain the corresponding predicted radiation field distribution data and predict the location and intensity of the radiation hotspots. S2 generates protection commands based on predicted radiation field distribution data, driving the movable shield to move to the predicted radiation hotspot area to form a localized enhanced shield. S3 collects radiation data in real time by deploying radiation detectors at key nodes in the process path, and fuses and compares the real-time monitoring data with the predicted data to verify the protection effect and handle alarms for abnormal situations. S4. Based on the comparison results of real-time radiation data and preset thresholds, the channel control device is automatically opened and closed, and a safe detour path is displayed through a visual guidance device.

2. The method as described in claim 1, characterized in that, S1 includes: S11, read the UHF RFID tag on the isotope target to be processed through the radio frequency identification reading device, obtain the UHF RFID tag information, and use its ID as the target identifier; S12, using the target identifier as an index, query the radiation field-operating condition mapping database to retrieve preset radiation field distribution data corresponding to the nuclide type and activity; S13, based on the retrieved preset radiation field distribution data, predict the location and intensity of radiation hotspots at key nodes in the process flow of the isotope target to be processed.

3. The method as described in claim 2, characterized in that, The radiation field-condition mapping database queried in S12 includes: The three-dimensional dose rate distribution data constructed based on the Monte Carlo particle transport calculation method is associated with a condition identifier, which includes nuclide type, activity level, and process node information. The Monte Carlo particle transport calculation formula is as follows: ； ； in, r For spatial location, T It is a nuclide type. A For activity level, P For process nodes, N To determine the total number of particles sampled in the Monte Carlo simulation. Let i be the statistical weight of the i-th particle. V To calculate the volume of a volume element, For energy E The corresponding dose conversion factor, E It refers to particle energy.

4. The method as described in claim 1, characterized in that, S2 includes: S21, generate a protection command based on the coordinates of radiation hotspots in the predicted radiation field distribution data, the protection command including the target location coordinates and standby or movement action command; S22, the protection command is sent to the movable shield deployed near the transmission channel via the wireless communication network, and the movable shield is driven to move along the pre-embedded guide rail to the track coordinate point corresponding to the predicted radiation hotspot location; S23, after the movable shield reaches the designated position, it forms a locally reinforced shield.

5. The method as described in claim 1, characterized in that, S3 includes: S31 collects radiation dose rate data in real time through radiation detectors deployed at key nodes in the process path; S32 transmits the real-time collected radiation dose rate data to the central processing unit via an industrial Ethernet bus. S33, in the central processing unit, the real-time monitoring data is fused and compared with the predicted radiation field distribution data obtained by S1, and the prediction deviation value is calculated. S34, when the predicted deviation value exceeds the preset deviation threshold, an abnormal alarm is triggered and an alarm message is generated.

6. The method as described in claim 1, characterized in that, S4 includes: S41 compares the real-time collected radiation dose rate data with the preset action threshold; S42, when the real-time dose rate of any critical node exceeds the preset action threshold, a locking signal is sent to the access controller of the corresponding channel to physically prevent the channel door lock from opening; S43, at the same time, triggers the visual guidance device to display the dynamically generated detour path, and explains the reason for the closure and the estimated detour time through text prompts. S44, When the monitoring network data shows that the dose rate in the relevant area has returned to below the background level, the locking status of the access control will be automatically released; S45 commands the movable shield to return to the standby position and restores the human-machine interface to normal status.

7. A dynamic radiation protection system for isotope production, characterized in that, include The radiation field prediction module is used to query the radiation field-operating condition mapping database based on the identification information of the isotope target to be processed, obtain the predicted radiation field distribution data, and predict the location and intensity of radiation hotspots. The mobile shielding control module generates protection commands based on predicted radiation field distribution data, driving the movable shield to move to the radiation hotspot area to form localized enhanced shielding. The monitoring and verification module collects radiation data from key nodes in the process path in real time through radiation detectors, merges and compares the real-time monitoring data with the predicted data, and triggers anomaly alarms. The safety guidance module controls the opening and closing of the channel control device based on the comparison results of real-time radiation data and preset thresholds, and dynamically displays the safe detour path through the visual guidance device.

8. The system as described in claim 7, characterized in that, The radiation field prediction module includes: The RFID reading unit is used to read the UHF RFID tag information on the target and extract the target ID; The database query unit is used to retrieve preset three-dimensional dose rate distribution data with associated nuclide type and activity level using the target ID as an index; The hotspot prediction unit is used to predict radiation hotspot parameters at key nodes in the process flow based on three-dimensional dose rate distribution data.

9. The system as described in claim 7, characterized in that, The mobile shielding control module includes: The instruction generation unit is used to generate control signals containing target position and movement instructions based on the coordinates of the radiation hotspots. The communication execution unit is used to drive the movable shield to move along the pre-embedded guide rail to the specified track coordinates via a wireless network. The shielding confirmation unit is used to activate the locally reinforced shielding structure after the movable shielding body is in place.

10. A computer-readable storage medium storing a computer program that, when executed by a processor, implements the method as claimed in any one of claims 1-6.

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