A radioactive tailings resource recovery residue safe disposal system

Abstract

The application discloses a radioactive tailing residue resource recycling and residue safe disposal system, and relates to the technical field of radioactive tailing residue treatment. The system comprises a batch boundary module, a transition module, a bearing module, an inheritance module, a sealing and checking module and a grading module. The batch boundary module is used for performing time sequence analysis on radioactive intensity data, nuclide composition data, slurry density data and flow data collected in the tailing residue conveying and treatment process, determining a tailing residue real batch boundary by calculating the characteristic change degree of adjacent time intervals, and generating batch boundary information. The transition module is used for setting a transition interval on both sides of the batch boundary, and analyzing the nuclide composition change of the tailing residue in the transition interval and the tailing residue residence time. The application can establish a unified data control chain around the data flow relationship of the radioactive tailing residue in the conveying, treatment, rework and packaging process, and can identify the tailing residue batch boundary and analyze the transition interval.

Description

Technical Field

[0001] This invention relates to the field of radioactive tailings treatment technology, specifically to a safe disposal system for the resource recovery and recycling of radioactive tailings residue. Background Technology

[0002] Radioactive tailings typically undergo multiple stages in resource recovery and safe disposal of residues, including transportation, testing, segmented processing, rework, packaging, and subsequent disposal. Because tailings possess both radioactive and slurry transport properties, their pipeline transportation, process switching, and packaging processes involve not only various parameters such as nuclide composition, radioactivity intensity, slurry density, and flow rate, but also multiple state information such as material batch boundaries, mixing transition zones, rework paths, and packaging sources. Therefore, the actual processing exhibits strong continuity, coupling, and process dependence. Existing radioactive tailings treatment systems typically include devices or software platforms for radioactivity detection, process recording, and packaging management. These technologies play a crucial role in tailings treatment, data acquisition, and process management. In practical applications, existing technologies usually focus on monitoring or recording single stages, such as collecting parameters for the conveying process, recording the time of each process, managing the numbering of packaging containers, and re-inspecting rework processes. While these methods can meet general process management needs, there is still a need for further improvements in batch boundary identification accuracy, transition zone attribution determination, the correspondence between material carrying units throughout the entire process, and the consistency of packaging source confirmation under the condition of continuous flow of tailings across multiple stages. Especially in scenarios involving batch switching of tailings transport, nuclide mixing in the transition zone, overlapping rework paths, and changes in automatic packaging cycle time, the lack of a unified control mechanism that integrates batch boundary identification, transition zone analysis, carrier unit establishment, rework inheritance recording, and packaging confirmation may make it difficult to establish a stable, consistent, and traceable correspondence between data generated in different stages, thereby affecting the accuracy of subsequent disposal classification. Therefore, it is necessary to propose a systematic data control scheme for the safe disposal process of radioactive tailings resource recovery residues to achieve synergistic consistency among material information, detection information, and packaging information throughout the entire tailings treatment process. Summary of the Invention

[0003] The purpose of this invention is to provide a safe disposal system for the resource recovery and recycling of radioactive tailings, so as to solve the problems mentioned in the background art.

[0004] This invention can be achieved through the following technical solution: a safe disposal system for the resource recovery and recycling of radioactive tailings, comprising: The batch boundary module is used to perform time-series analysis on radioactivity intensity data, nuclide composition data, slurry density data and flow rate data collected during the tailings transportation and treatment process. It determines the true batch boundary of tailings by calculating the degree of characteristic change between adjacent time intervals and generates batch boundary information. The transition module is used to set transition intervals on both sides of the batch boundary, analyze the changes in nuclide composition and residence time of tailings within the transition interval, determine the contribution ratio of tailings from the previous batch and the contribution ratio of tailings from the subsequent batch, and form a transition data object accordingly. The carrier module is used to generate tailings material carrier units based on batch boundary information and transition data objects, and to use the material carrier unit as the unique data identifier of tailings during the detection and packaging process. The inheritance module is used to extract the original nuclide composition information, historical test records and historical risk levels of the material carrier unit during tailings rework to form the original risk identifier, and to add new test records during the rework process to form a risk inheritance record. The sealing and verification module is used to match the filling process data with the time information of the material carrier unit during the tailings packaging process, determine the material carrier unit received by the packaging container, and confirm the source of the tailings corresponding to the packaging container. The grading module is used to obtain the radioactivity risk of tailings based on the detection data, and to determine the data attribution reliability and historical integrity by combining the material carrying unit information and risk inheritance records, thereby generating the disposal path grading results of tailings or packaging containers.

[0005] A further technical improvement of the present invention is that the batch boundary module determines the true batch boundary of the tailings according to the following steps: During the tailings transportation process, data on radioactivity intensity, nuclide composition, slurry density, and flow rate are collected, and the variation of each monitoring data is calculated within a continuous sampling period. A joint comparison of various change magnitudes is conducted, and a synchronous mutation interval is determined only when the change magnitudes of at least two types of monitoring data simultaneously exceed the preset mutation threshold within the same time window. The synchronous mutation interval is continuously periodically confirmed, and it is retained as a candidate boundary interval only when the mutation occurs consecutively in multiple sampling periods. The tailings conveying volume is calculated based on the tailings conveying flow rate and the duration of the candidate boundary interval. The calculated tailings conveying volume is compared with the preset minimum conveying volume threshold. Only when the tailings conveying volume is not less than the minimum conveying volume threshold is it determined as a valid boundary interval. A stable zone is set after the effective boundary interval. When the variation of the monitoring data in each sampling cycle within the stable zone remains within the preset stable range, the starting position of the effective boundary interval is determined as the true batch boundary of the tailings.

[0006] A further technical improvement of the present invention is that: the minimum transport volume threshold is modified based on the residual volume of the tailings transport pipeline, the response delay time of the radioactive detection equipment, and the batch boundary diffusion characteristics of the tailings in the transport pipeline. The basic minimum transport volume is formed by superimposing the residual volume with the detection delay compensation volume determined by the response delay time and the tailings transport flow rate. The batch boundary propagation distance is determined based on the tailings transport velocity and propagation time. The batch boundary diffusion volume is calculated based on the batch boundary propagation distance and the pipeline cross-sectional area. The batch boundary diffusion volume is superimposed with the basic minimum transport volume to form the dynamic minimum transport volume. When calculating the tailings conveying volume, the batch boundary module compares the actual conveying volume with the dynamic minimum conveying volume, and only confirms the effective boundary interval when the actual conveying volume is not less than the dynamic minimum conveying volume.

[0007] A further technical improvement of the present invention is that the transition module determines the contribution ratio of the previous batch of tailings and the subsequent batch of tailings in the transition zone according to the following steps: Obtain the nuclide composition data of the first batch of tailings, the nuclide composition data of the second batch of tailings, and the nuclide composition data of the tailings in the transition zone, and construct the nuclide characteristic sequence according to the nuclide type and corresponding activity value. Based on the decay parameters of each nuclide and the detection time difference, the nuclide feature sequences are processed to unify the time reference, resulting in nuclide feature sequences under a unified time reference. The nuclide activity weights are determined based on the proportion of each nuclide activity value in the total activity value, and the nuclide feature sequences under a unified time reference are weighted according to the nuclide activity weights to form weighted nuclide feature sequences. The weighted nuclide feature sequence in the transition region is represented as a combination of the weighted nuclide feature sequences of the previous batch and the weighted nuclide feature sequences of the subsequent batch. The contribution ratio of the previous batch and the contribution ratio of the subsequent batch are obtained by proportionally calculating the sequence difference corresponding to each nuclide position. The contribution ratios of the previous batch and the subsequent batch are written into the transition data object and used as input data for the material carrying unit generated by the carrying module.

[0008] A further technical improvement of the present invention is that: before determining the nuclide composition data of the tailings in the transition zone, the transition module corrects the interval of the transition zone according to the following steps: Obtain the length, cross-sectional area, and effective volume of each pipe section in the tailings conveying path, and divide the conveying into segmented conveying units according to the tailings conveying sequence; The theoretical residence time of each segment conveying unit is calculated based on the effective volume of each segment conveying unit and the tailings conveying flow rate of the corresponding time period. The theoretical residence time of each segment conveying unit is then summed to obtain the basic residence time. The volumetric memory time is calculated based on the residual volume in each segment conveying unit when the previous batch of tailings is finished and the current tailings conveying flow rate. The volumetric memory time is then superimposed with the basic residence time to obtain the corrected residence time. The detection offset time is calculated based on the conveying distance between the detection location and the batch boundary formation location and the tailings conveying velocity, and the start and end positions of the transition zone are determined based on the correction residence time and the detection offset time. Nuclide composition data of tailings in the transition zone are extracted based on the determined start and end positions of the transition zone, and the extraction results are used as input data to determine the contribution ratio of the previous batch of tailings and the contribution ratio of the subsequent batch of tailings.

[0009] A further technical improvement of the present invention is that the carrying module establishes a material carrying unit lifecycle tracking record and performs flow consistency verification according to the following steps: Establish a process topology based on the tailings treatment process, and record the corresponding process number, entry time and initial nuclide composition information for each material carrying unit. When the material carrying unit enters the next processing step, the current process number and the departure time of the previous process are recorded, and the legality of the process sequence relationship is verified according to the process topology. The actual dwell time is calculated based on the current process entry time, the previous process exit time, and the allowable dwell time range of the corresponding process, and the actual dwell time is matched and verified with the allowable dwell time range; When the testing or packaging process is completed, the current nuclide composition information is obtained and compared with the initial nuclide composition information for consistency. The material propagation time is calculated based on the propagation distance of the tailings in the conveying system, the residence time in the pipeline, and the processing time of each processing step. The material propagation time is then compared with the actual process time sequence of the material carrying unit. When all the above checks meet the preset conditions, the relevant process information is written into the lifecycle tracking record. When any check fails, an abnormal carrying unit mark is generated and the data verification process is started.

[0010] A further technical improvement of the present invention is that the inheritance module performs nuclide structure consistency verification on the rework material carrier unit according to the following steps: The original nuclide composition information, original detection time, rework detection time and rework processing path record corresponding to the material carrier unit are extracted, and the original nuclide composition sequence and rework nuclide composition sequence are constructed according to the nuclide type and corresponding activity value. Based on the decay parameters of each nuclide and the time difference between the original detection time and the rework detection time, the decay time of the reworked nuclide composition sequence is corrected to obtain the reworked nuclide composition sequence under a unified time reference. Based on the sequence of each processing step and the dwell time in the rework processing path record, the rework path propagation verification conditions are determined, and the corrected rework nuclide composition sequence is compared with the original nuclide composition sequence on a nuclide-by-nuclide basis. The consistency of the nuclide structure of the rework material carrier unit is determined based on the deviation of the proportion of each nuclide from the preset deviation range. When the deviation of any nuclide proportion exceeds the preset deviation range, the corresponding material carrier unit is written into the abnormal inheritance record and the original risk identifier remains unchanged.

[0011] A further technical improvement of the present invention is that the sealing and inspection module confirms the material carrier unit received by the packaging container according to the following steps: The pipeline length, cross-sectional area, tailings transport flow rate, valve opening time, valve closing time, and packaging container weighing data of the filling channel are obtained, and the filling time interval of the packaging container is determined accordingly. The theoretical arrival time interval of the material carrying unit is determined based on the time when the material carrying unit enters the filling channel, the tailings conveying flow rate, and the volume of the filling channel. The filling time interval is overlapped with the theoretical arrival time interval. When there is an overlap, the corresponding material carrying unit is identified as a candidate to enter the material carrying unit. The candidate entry mass is determined based on the tailings conveying volume and slurry density corresponding to the candidate entry material carrying unit, and the actual entry mass is determined based on the weighing increment of the packaging container within the corresponding time interval. When the quality deviation between the candidate entry quality and the actual entry quality is within a preset range, the material carrier unit is confirmed to have entered the packaging container, and a packaging confirmation record is generated to determine the source of the tailings corresponding to the packaging container.

[0012] Compared with the prior art, the present invention has the following beneficial effects: This invention can establish a unified data control chain around the data flow relationship of radioactive tailings in the process of transportation, processing, rework and packaging; and can also associate tailings batch boundary identification, transition interval analysis, material carrying unit generation, rework risk inheritance, packaging source confirmation and disposal classification, so that the data status of tailings in different processes maintains a corresponding relationship with the material status. Furthermore, through the collaborative processing of the batch boundary module and the transition module, this invention can identify the actual batch boundaries and transition zones during the tailings transportation process, and determine the contribution ratios of the previous batch of tailings and the subsequent batch of tailings based on data such as nuclide composition, flow rate, slurry density, and residence time, forming a transition data object. On this basis, the carrying module can generate material carrying units based on the batch boundary information and the transition data object, so that the data identification of tailings during the detection and packaging process has continuity and traceability, thereby improving the accuracy of data attribution during the tailings circulation process. On the other hand, through the cooperation of the inheritance module, the sealing and verification module, and the classification module, this invention can maintain the consistency between the original risk information, the current processing record, and the source of the packaging during the rework and packaging confirmation process, and generate classification results of the disposal path of tailings or packaging containers based on this. Through the above technical solution, the system can collaboratively process multi-source data in the safe disposal process of radioactive tailings resource recovery residue, and provide systematic support for risk identification, data verification, and disposal management in the tailings treatment process. Attached Figure Description

[0013] To facilitate understanding by those skilled in the art, the present invention will be further described below with reference to the accompanying drawings.

[0014] Figure 1 This is a system block diagram of the present invention. Detailed Implementation

[0015] To further illustrate the technical means and effects of the present invention in achieving its intended purpose, the following detailed description of the specific implementation methods, structures, features, and effects of the present invention, in conjunction with the accompanying drawings and preferred embodiments, is provided.

[0016] Please see Figure 1 As shown, the present invention provides a safe disposal system for the resource recovery and recycling of radioactive tailings residue, comprising: The batch boundary module is used to perform time-series analysis on radioactivity intensity data, nuclide composition data, slurry density data, and flow rate data collected during the tailings transportation and processing. By calculating the degree of characteristic change between adjacent time intervals, it determines the true batch boundary of tailings and generates batch boundary information. This module is used to identify the true boundary position between tailings from different sources during continuous tailings transportation. By performing time-series analysis on multiple monitoring data, the system can identify the change nodes between different tailings batches under the tailings material flow state, thereby establishing the correspondence between tailings batches and detection data, providing basic data support for subsequent transition zone analysis and material carrying unit generation.

[0017] The batch boundary module determines the true batch boundary of tailings according to the following steps: During the tailings transportation process, data on radioactivity intensity, nuclide composition, slurry density, and flow rate are collected, and the variation of each monitoring data is calculated within a continuous sampling period. A joint comparison of various change magnitudes is conducted, and a synchronous mutation interval is determined only when the change magnitudes of at least two types of monitoring data simultaneously exceed the preset mutation threshold within the same time window. The synchronous mutation interval is continuously periodically confirmed, and it is retained as a candidate boundary interval only when the mutation occurs consecutively in multiple sampling periods. The tailings conveying volume is calculated based on the tailings conveying flow rate and the duration of the candidate boundary interval. The calculated tailings conveying volume is compared with the preset minimum conveying volume threshold. Only when the tailings conveying volume is not less than the minimum conveying volume threshold is it determined as a valid boundary interval. A stable zone is set after the effective boundary interval. When the variation of the monitoring data in each sampling cycle within the stable zone remains within the preset stable range, the starting position of the effective boundary interval is determined as the true batch boundary of the tailings.

[0018] The minimum transport volume threshold is modified based on the residual volume of the tailings transport pipeline, the response delay time of the radioactive detection equipment, and the batch boundary diffusion characteristics of the tailings in the transport pipeline. The basic minimum transport volume is formed by superimposing the residual volume with the detection delay compensation volume determined by the response delay time and the tailings transport flow rate. The batch boundary propagation distance is determined based on the tailings transport velocity and propagation time. The batch boundary diffusion volume is calculated based on the batch boundary propagation distance and the pipeline cross-sectional area. The batch boundary diffusion volume is superimposed with the basic minimum transport volume to form the dynamic minimum transport volume. When calculating the tailings conveying volume, the batch boundary module compares the actual conveying volume with the dynamic minimum conveying volume, and only confirms the effective boundary interval when the actual conveying volume is not less than the dynamic minimum conveying volume.

[0019] Specifically, during the tailings transportation process, radioactivity intensity data, nuclide composition data, slurry density data, and flow rate data are continuously collected at the detection locations. The sampling period is set to 2 seconds, with every 10 sampling points constituting a time interval. The variation range of each monitoring data point within adjacent time intervals is calculated. Specifically, radioactivity intensity data is expressed as the ratio of the average count difference between adjacent intervals to the average count value of the previous interval; nuclide composition data is expressed as the difference in the activity ratio of the dominant nuclides between adjacent intervals; slurry density data is expressed as the ratio of the average density difference between adjacent intervals to the average density of the previous interval; and flow rate data is expressed as the ratio of the average flow rate difference between adjacent intervals to the average flow rate of the previous interval. For example, if the average radioactivity intensity of the previous interval is 1200 counts / s and the next interval is 1500 counts / s, the corresponding variation range is 25%; if the average flow rate of the previous interval is 1.8 m³ / h and the next interval is 2.1 m³ / h, the corresponding variation range is approximately 16.7%. The variation range of each monitoring data point over time is obtained using the above method.

[0020] The changes in various monitoring data are jointly compared to determine the synchronous mutation interval. In this embodiment, the preset mutation threshold for radioactivity intensity data is set to 15%, the preset mutation threshold for nuclide composition data is set to 8%, the preset mutation threshold for slurry density data is set to 5%, and the preset mutation threshold for flow rate data is set to 10%. When at least two types of monitoring data simultaneously exceed the corresponding mutation threshold within the same time window, that time window is determined as the synchronous mutation interval. Based on this, continuous periodic confirmation is performed. In this embodiment, the synchronous mutation condition must be met for three consecutive sampling periods before the corresponding interval is retained as a candidate boundary interval to avoid misjudgment caused by short-term fluctuations.

[0021] The tailings transport volume is calculated based on the tailings transport flow rate and the duration of the candidate boundary interval, and the dynamic minimum transport volume is determined by combining the characteristics of the transport pipeline. For example, if a candidate boundary interval lasts for 20 seconds and the average flow rate of the interval is 2.0 m³ / h, the corresponding tailings transport volume is approximately 0.011 m³. Subsequently, the minimum transport volume threshold is corrected based on the residual volume of the tailings transport pipeline, the response delay time of the radioactive detection equipment, and the batch-boundary diffusion characteristics of the tailings in the transport pipeline. Specifically, in this embodiment, the residual volume of the pipeline is 0.004 m³, the response delay time of the detection equipment is 3 seconds, and the detection delay compensation volume is approximately 0.0017 m³ under the condition of a flow rate of 2.0 m³ / h. The sum of these two values ​​yields the basic minimum transport volume. The batch-boundary propagation distance is then determined based on the tailings transport velocity and propagation time. For example, if the transport velocity is 0.6 m / s and the propagation time is 2 seconds, the batch-boundary propagation distance is 1.2 m; combined with the pipeline cross-sectional area of ​​0.003 m², the batch-boundary diffusion volume is calculated to be approximately 0.0036 m³. The batch boundary diffusion volume is superimposed with the basic minimum conveying volume to form the dynamic minimum conveying volume. Then, the calculated tailings conveying volume is compared with the dynamic minimum conveying volume, and the candidate boundary interval is determined as the effective boundary interval only when the tailings conveying volume is not less than the dynamic minimum conveying volume.

[0022] A stabilization zone is set after the effective boundary interval, and the stability of the tailings is determined based on the variation of monitoring data in each sampling cycle within the stabilization zone. In this embodiment, the duration of the stabilization zone is set to 30 seconds. When the variation of radioactivity intensity data, nuclide composition data, slurry density data, and flow rate data within the stabilization zone does not exceed 5%, the starting position of the effective boundary interval is determined as the true batch boundary of the tailings, and the corresponding batch boundary information is generated. This batch boundary information can then be used as the basic input data for subsequent transition modules to determine transition intervals, form transition data objects, and for the carrier module to generate material carrier units, thereby achieving continuous data correlation during the tailings transportation, detection, and packaging processes.

[0023] The transition module is used to define transition intervals on both sides of the batch boundary, analyze the changes in nuclide composition and residence time of tailings within the transition intervals, determine the contribution ratios of tailings from previous and subsequent batches, and generate transition data objects accordingly. This module is also used to identify mixing zones formed during batch switching. By analyzing the nuclide composition change trends within the transition intervals and the residence time of tailings in the pipeline, it determines the contribution ratios of different batches of tailings within these zones. This allows the system to assign data to tailings in the mixing zone, reducing uncertainty in data assignment caused by tailings mixing during batch switching, and providing transition ratio information for the material carrying unit generated by the carrying module.

[0024] The transition module determines the contribution ratio of the previous batch of tailings and the subsequent batch of tailings in the transition zone according to the following steps: Obtain the nuclide composition data of the first batch of tailings, the nuclide composition data of the second batch of tailings, and the nuclide composition data of the tailings in the transition zone, and construct the nuclide characteristic sequence according to the nuclide type and corresponding activity value. Based on the decay parameters of each nuclide and the detection time difference, the nuclide feature sequences are processed to unify the time reference, resulting in nuclide feature sequences under a unified time reference. The nuclide activity weights are determined based on the proportion of each nuclide activity value in the total activity value, and the nuclide feature sequences under a unified time reference are weighted according to the nuclide activity weights to form weighted nuclide feature sequences. The weighted nuclide feature sequence in the transition region is represented as a combination of the weighted nuclide feature sequences of the previous batch and the weighted nuclide feature sequences of the subsequent batch. The contribution ratio of the previous batch and the contribution ratio of the subsequent batch are obtained by proportionally calculating the sequence difference corresponding to each nuclide position. The contribution ratios of the previous batch and the subsequent batch are written into the transition data object and used as input data for the material carrying unit generated by the carrying module.

[0025] Before determining the nuclide composition data of the tailings in the transition zone, the transition module corrects the intervals of the transition zone according to the following steps: Obtain the length, cross-sectional area, and effective volume of each pipe section in the tailings conveying path, and divide the conveying into segmented conveying units according to the tailings conveying sequence; The theoretical residence time of each segment conveying unit is calculated based on the effective volume of each segment conveying unit and the tailings conveying flow rate of the corresponding time period. The theoretical residence time of each segment conveying unit is then summed to obtain the basic residence time. The volumetric memory time is calculated based on the residual volume in each segment conveying unit when the previous batch of tailings is finished and the current tailings conveying flow rate. The volumetric memory time is then superimposed with the basic residence time to obtain the corrected residence time. The detection offset time is calculated based on the conveying distance between the detection location and the batch boundary formation location and the tailings conveying velocity, and the start and end positions of the transition zone are determined based on the correction residence time and the detection offset time. Nuclide composition data of tailings in the transition zone are extracted based on the determined start and end positions of the transition zone, and the extraction results are used as input data to determine the contribution ratio of the previous batch of tailings and the contribution ratio of the subsequent batch of tailings.

[0026] Specifically, in this embodiment, based on the batch boundary information generated by the aforementioned batch boundary module, an initial transition interval is preset on both sides of the batch boundary, and the residence time of this initial transition interval is corrected. Specifically, the length, cross-sectional area, and effective volume of each pipe segment in the tailings conveying path are obtained, and the path is divided into segmented conveying units according to the tailings conveying sequence. For example, the conveying path sequentially includes a first pipe segment, a second pipe segment, and a detection branch. The first pipe segment has a length of 8m, a cross-sectional area of ​​0.003m², and an effective volume of 0.024m³; the second pipe segment has a length of 5m, a cross-sectional area of ​​0.003m², and an effective volume of 0.015m³; and the detection branch has an effective volume of 0.006m³. The theoretical residence time of each segmented conveying unit is calculated based on the effective volume of each segmented conveying unit and the tailings conveying flow rate for the corresponding time period. In this embodiment, the tailings conveying flow rate is 2.0 m³ / h, which is approximately 0.00056 m³ / s. Therefore, the theoretical residence time of the first pipe section is approximately 43 s, the theoretical residence time of the second pipe section is approximately 27 s, and the theoretical residence time of the detection branch is approximately 11 s. The sum of these three values ​​gives a basic residence time of 81 s.

[0027] After obtaining the basic residence time, the transition zone is further adjusted based on the residual conditions at the end of the previous batch of tailings transport. Specifically, the volumetric memory time is calculated based on the residual volume in each segment of the transport unit at the end of the previous batch of tailings transport and the current tailings transport flow rate. For example, if the residual volume of the first pipe segment is 0.002 m³, the residual volume of the second pipe segment is 0.001 m³, and the residual volume of the detection branch is 0.0005 m³, then the total residual volume is 0.0035 m³, corresponding to a volumetric memory time of approximately 6 s at a transport flow rate of 2.0 m³ / h. Adding the volumetric memory time to the basic residence time yields a corrected residence time of 87 s. Subsequently, the detection offset time is calculated based on the transport distance between the detection position and the batch boundary formation position and the tailings transport flow rate. For example, if the transport distance between the detection position and the batch boundary formation position is 1.8 m, and the tailings transport flow rate is 0.6 m / s, then the detection offset time is 3 s. The start and end positions of the transition zone are determined based on the corrected dwell time and the detection offset time. In this embodiment, the data interval corresponding to 90 seconds before the batch boundary time to 20 seconds after the batch boundary time is determined as the corrected transition zone.

[0028] After determining the start and end positions of the transition zone, the nuclide composition data of the tailings in the transition zone is extracted based on this interval and then processed uniformly with the nuclide composition data of the preceding and following batches. Specifically, the nuclide composition data of the preceding batch of tailings, the following batch of tailings, and the transition zone tailings are obtained, and nuclide characteristic sequences are constructed according to nuclide type and corresponding activity value. In this embodiment, cesium-137, strontium-90, and cobalt-60 are selected as the main nuclides, with corresponding activity values ​​of 62 Bq / g, 18 Bq / g, and 10 Bq / g for the preceding batch of tailings, 35 Bq / g, 30 Bq / g, and 22 Bq / g for the following batch of tailings, and 48 Bq / g, 24 Bq / g, and 16 Bq / g for the transition zone tailings. Then, the nuclide characteristic sequences are processed to unify the time reference based on the decay parameters of each nuclide and the detection time difference. To ensure consistency in the comparison basis, this embodiment uses the detection time of the previous batch as a unified time reference. If the detection time of the transition zone is 4 hours later than the detection time of the previous batch, and the detection time of the subsequent batch is 6 hours later than the detection time of the previous batch, the corresponding activity values ​​are back-corrected based on the decay parameters of each nuclide to obtain the nuclide characteristic sequence under the unified time reference. Based on this, the nuclide activity weight is determined according to the proportion of each nuclide activity value in the total activity value. For example, in the tailings of the transition zone, the activity weights of cesium-137, strontium-90, and cobalt-60 are approximately 0.55, 0.27, and 0.18, respectively. The nuclide characteristic sequence under the unified time reference is then weighted according to the nuclide activity weight to form a weighted nuclide characteristic sequence.

[0029] Based on the aforementioned weighted nuclide feature sequences, the contribution ratios of the preceding and following batches are determined, and a transition data object is formed. Specifically, the weighted nuclide feature sequences of the transition region are represented as a combination of the weighted nuclide feature sequences of the preceding and following batches. Then, the contribution ratios of the preceding and following batches are obtained by proportionally calculating the sequence differences corresponding to each nuclide position. In this embodiment, after proportional calculation, the contribution ratio of the preceding batch is 0.58, and the contribution ratio of the following batch is 0.42. Subsequently, the contribution ratios of the preceding and following batches are written into the transition data object, and this transition data object is used as the input data for the subsequent material carrying module to generate the material carrying unit. In this way, the batch boundary information formed by the batch boundary module and the transition data object formed in this embodiment can jointly define the true ownership relationship of the tailings during the batch switching process, thereby providing a continuous and consistent data foundation for the subsequent processing stage.

[0030] The carrier module is used to generate tailings material carrier units based on batch boundary information and transition data objects, and to use the material carrier unit as a unique data identifier for tailings during the detection and packaging process. This module is used to uniformly package the batch information and transition zone information formed during the transportation and processing of tailings. By generating material carrier units, the data records of tailings in different processing steps can be associated with a unified identifier, thereby establishing a stable data connection relationship between multiple processing stages such as detection, processing, and packaging, and realizing the continuous correspondence between tailings material status and detection data.

[0031] The carrier module establishes a lifecycle tracking record for the material carrier unit and performs consistency verification of its flow according to the following steps: Establish a process topology based on the tailings treatment process, and record the corresponding process number, entry time and initial nuclide composition information for each material carrying unit. When the material carrying unit enters the next processing step, the current process number and the departure time of the previous process are recorded, and the legality of the process sequence relationship is verified according to the process topology. The actual dwell time is calculated based on the current process entry time, the previous process exit time, and the allowable dwell time range of the corresponding process, and the actual dwell time is matched and verified with the allowable dwell time range; When the testing or packaging process is completed, the current nuclide composition information is obtained and compared with the initial nuclide composition information for consistency. The material propagation time is calculated based on the propagation distance of the tailings in the conveying system, the residence time in the pipeline, and the processing time of each processing step. The material propagation time is then compared with the actual process time sequence of the material carrying unit. When all the above checks meet the preset conditions, the relevant process information is written into the lifecycle tracking record. When any check fails, an abnormal carrying unit mark is generated and the data verification process is started.

[0032] Specifically, in this embodiment, material carrier units are generated based on the batch boundary information and transition data objects generated in the aforementioned embodiments, and a process topology corresponding to the tailings treatment process is established. Specifically, the tailings treatment process is divided into four process nodes: pretreatment, inspection, rework, and packaging. The allowed process sequences are specified as "pretreatment → inspection → packaging" and "inspection → rework → inspection → packaging." When generating each material carrier unit, the corresponding process number, process entry time, and initial nuclide composition information are recorded. For example, based on the aforementioned implementation method, the contribution ratio of the preceding batch of tailings is determined to be 0.58, and the contribution ratio of the subsequent batch is 0.42. This information is then written into the corresponding transition data object. Subsequently, a material carrying unit is generated based on this transition data object, with its initial process number recorded as "inspection process," the process entry time recorded as 10:00:00 on March 11, 2026, and the initial nuclide composition information recorded as 48 Bq / g for Cesium-137, 24 Bq / g for Strontium-90, and 16 Bq / g for Cobalt-60. Through this method, each material carrying unit has a traceable initial state before entering the subsequent processing flow.

[0033] After generating the material carrier unit, its flow process is validated for the legality of the process sequence and the dwell time range. Specifically, when the material carrier unit enters the next processing step, the current process number and the departure time of the previous process are recorded, and the legality of the process sequence is validated based on the aforementioned process topology. For example, if a material carrier unit directly enters the "packaging process" after the "inspection process," the sequence is legal; if it directly enters an unauthorized process after the "inspection process," the sequence is considered abnormal. Simultaneously, the actual dwell time is calculated based on the current process entry time, the previous process departure time, and the allowed dwell time range for the corresponding process, and the actual dwell time is matched and validated against the allowed dwell time range. In this embodiment, the allowed dwell time range for the inspection process is set to 10 to 40 minutes, and the allowed dwell time range for the packaging process is set to 5 to 20 minutes. If a material carrier unit enters the inspection process at 10:00:00 and leaves at 10:18:00, the actual dwell time is 18 minutes, which is within the allowable dwell time range and passes this verification. If the dwell time is only 3 minutes or exceeds 40 minutes, it is determined to be an abnormal dwell time. Through this step, the initial process record formed in the previous stage can establish a continuous time and sequence association with the subsequent process records.

[0034] After verifying the legality of the process sequence and the dwell time interval, the consistency comparison between the initial nuclide composition information and the current nuclide composition information is performed, along with a material propagation time consistency comparison. Specifically, the current nuclide composition information is obtained upon completion of the detection or packaging process and compared with the initial nuclide composition information. In this embodiment, the threshold for deviation of each nuclide proportion is set to 8%, meaning that if the current proportion of any dominant nuclide deviates from the initial proportion by more than 8%, the consistency comparison is deemed to fail. For example, if a material carrier unit measures cesium-137 at 47 Bq / g, strontium-90 at 25 Bq / g, and cobalt-60 at 15.5 Bq / g during the packaging process, these values ​​are all within the allowable range compared to the aforementioned initial nuclide composition information, and the consistency comparison can be passed. Subsequently, the material propagation time is calculated based on the propagation distance of the tailings in the conveying path, the pipeline dwell time, and the processing time of each processing step, and the material propagation time is compared with the actual process time sequence of the material carrier unit. For example, if the conveying distance between the inspection station and the packaging station is 12m, and the average conveying velocity of the tailings is 0.6m / s, then the conveying time is approximately 20s. Combining this with the pipeline dwell time of 60s and the packaging preparation time of 180s, the theoretical material propagation time is 260s. If the actual time interval between the end of the inspection and the start of the packaging of the material carrying unit is 270s, then the deviation is 10s, which falls within the 20s allowable deviation range preset in this embodiment, indicating that the material propagation time consistency comparison has passed. This step combines the process records and radionuclide records from the previous stage with the physical propagation process during material conveying.

[0035] After the above verification is completed, the lifecycle tracking record is written, and an abnormal carrying unit marker is generated based on the verification results. Specifically, when the verification of the legality of the process sequence relationship, the verification of the dwell time interval, the consistency comparison of the nuclide composition information, and the consistency comparison of the material propagation time all meet the preset conditions, the relevant process information is written into the lifecycle tracking record, including the current process number, the entry time of the process, the exit time of the process, the current nuclide composition information, and the corresponding verification results; when any verification is not met, an abnormal carrying unit marker is generated and the data verification process is initiated. In this embodiment, the data verification process includes comparing the previous process record, the current process record, and the detection record of the material carrying unit again, and using the comparison results as an auxiliary basis for the subsequent inheritance module to determine whether the original risk identifier remains unchanged and for the sealing and inspection module to confirm the source of the packaging container. Thus, the material carrying unit generated based on the aforementioned batch boundary information and transition data object further forms a continuous lifecycle tracking record in this embodiment, thereby achieving partial connection with the subsequent technical solution.

[0036] The inheritance module is used to extract the original nuclide composition information, historical test records, and historical risk levels corresponding to the material carrier unit to form the original risk identifier during tailings rework. It also adds new test records during the rework process to form a risk inheritance record. This module is used to maintain the continuity of historical risk information during tailings rework. It forms the original risk identifier by extracting the original test data and historical risk levels corresponding to the material carrier unit, and records new test data during the rework process. This allows the reworked tailings to retain the original risk information and treatment records, thereby realizing the continuous transmission of tailings risk information in multiple treatment processes.

[0037] The inheritance module performs nuclide structure consistency verification on the reworked material carrier unit according to the following steps: The original nuclide composition information, original detection time, rework detection time and rework processing path record corresponding to the material carrier unit are extracted, and the original nuclide composition sequence and rework nuclide composition sequence are constructed according to the nuclide type and corresponding activity value. Based on the decay parameters of each nuclide and the time difference between the original detection time and the rework detection time, the decay time of the reworked nuclide composition sequence is corrected to obtain the reworked nuclide composition sequence under a unified time reference. Based on the sequence of each processing step and the dwell time in the rework processing path record, the rework path propagation verification conditions are determined, and the corrected rework nuclide composition sequence is compared with the original nuclide composition sequence on a nuclide-by-nuclide basis. The consistency of the nuclide structure of the rework material carrier unit is determined based on the deviation of the proportion of each nuclide from the preset deviation range. When the deviation of any nuclide proportion exceeds the preset deviation range, the corresponding material carrier unit is written into the abnormal inheritance record and the original risk identifier remains unchanged.

[0038] Specifically, in this embodiment, the inheritance module extracts the original nuclide composition information, historical detection records, and historical risk levels corresponding to the material carrying unit at the start of tailings rework to form an original risk identifier, and adds new detection records during the rework process to form a risk inheritance record. Specifically, it reads the data corresponding to the material carrying unit generated in the aforementioned embodiments, extracts the original nuclide composition information, original detection time, rework detection time, and rework processing path records, and constructs the original nuclide composition sequence and the rework nuclide composition sequence based on the nuclide type and corresponding activity value. In this embodiment, the original nuclide composition information of a certain material carrier unit at the original detection time of 10:00:00 on March 11, 2026 was: Cesium-137 48 Bq / g, Strontium-90 24 Bq / g, and Cobalt-60 16 Bq / g, with a corresponding historical risk level of medium risk in the historical detection record. After rework, a second detection was performed at 14:00:00 on March 11, 2026, yielding the reworked nuclide composition data as: Cesium-137 46.8 Bq / g, Strontium-90 24.5 Bq / g, and Cobalt-60 15.7 Bq / g. Based on the above information, the original risk identifier of the material carrier unit is formed, and the rework detection record is used as the basic input for the subsequent formation of the risk inheritance record.

[0039] After obtaining the aforementioned original and reworked nuclide composition sequences, the reworked nuclide composition sequences undergo time unification processing. Specifically, based on the decay parameters of each nuclide and the time difference between the original detection time and the rework detection time, the decay time of the reworked nuclide composition sequences is corrected to obtain reworked nuclide composition sequences under a unified time reference. In this embodiment, the time difference between the original detection time and the rework detection time is 4 hours, with the original detection time used as the unified time reference. Since 4 hours is relatively short compared to the decay periods of cesium-137, strontium-90, and cobalt-60, the correction magnitude is small, but it is still corrected by back-calculation according to the nuclide decay parameters. After correction, the reworked nuclide composition sequences are adjusted as follows: cesium-137 is 46.9 Bq / g, strontium-90 is 24.5 Bq / g, and cobalt-60 is 15.8 Bq / g. Through this step, the reworked detection values ​​and the original nuclide composition information are placed under the same time reference, providing a unified comparison basis for subsequent rework path propagation verification. Meanwhile, in this embodiment, the nuclide detection error range is preset to ±3%. This error range is determined based on the calibration results of the nuclide detection device and the historical detection fluctuation range, and is used as one of the verification reference boundaries in the subsequent proportional deviation judgment.

[0040] After decay time correction, the nuclide structure is verified for consistency in conjunction with the rework path. Specifically, the rework path propagation verification conditions are determined based on the sequence and dwell time of each processing step in the rework path record, and the corrected rework nuclide composition sequence is compared with the original nuclide composition sequence on a nuclide-by-nuclide basis. In this embodiment, the rework path record is "inspection step → rework step → inspection step", the dwell time of the rework step is 35 minutes, and the transport dwell time before re-entering the inspection step after rework is 8 minutes. Therefore, the rework path propagation verification conditions include: the sequence of processes in the rework path must be consistent with the process topology structure established by the aforementioned carrier module; the dwell time of the rework step must be within 20 minutes to 90 minutes; and the transport dwell time before re-entering the inspection step must be within 5 minutes to 15 minutes. When the above rework path propagation verification conditions are met, the corrected rework nuclide composition sequence is then compared with the original nuclide composition sequence on a nuclide-by-nuclide basis. Based on the normalized proportions of total activity, the original nuclide composition in this embodiment is approximately: cesium-137 54.5%, strontium-90 27.3%, and cobalt-60 18.2%; the corrected reworked nuclide composition is approximately: cesium-137 53.9%, strontium-90 28.1%, and cobalt-60 18.0%. In this embodiment, the preset deviation range for each nuclide proportion is uniformly set at 10%. This range is pre-calibrated based on the nuclide detection error range before and after rework, decay time correction error, and the allowable fluctuation range of the rework process. After comparison, the deviation of the cesium-137 proportion is approximately 0.6 percentage points, the strontium-90 proportion is approximately 0.8 percentage points, and the cobalt-60 proportion is approximately 0.2 percentage points, all of which do not exceed the preset deviation range of 10%. Therefore, the nuclide structure consistency verification of the reworked material carrier unit is deemed successful.

[0041] After the nuclide structure consistency verification is completed, a risk inheritance record or anomaly inheritance record is formed accordingly, and the original risk identifier is maintained in a continuous association. Specifically, the nuclide structure consistency of the rework material carrier unit is judged based on the deviation of each nuclide ratio from the preset deviation range. When the deviation of any nuclide ratio exceeds the preset deviation range, the corresponding material carrier unit is written into the anomaly inheritance record while the original risk identifier remains unchanged. When the deviation of each nuclide ratio does not exceed the preset deviation range, a rework inspection record, a rework processing path record, and a corrected rework nuclide composition sequence are added under the original risk identifier to form the corresponding risk inheritance record. In this embodiment, since the ratio deviations of the aforementioned three nuclides are all within the preset deviation range, the material carrier unit forms a risk inheritance record rather than an anomaly inheritance record. If, in another rework scenario, the cesium-137 ratio deviation reaches 12.5%, the material carrier unit is written into the anomaly inheritance record while its original risk identifier remains unchanged, so that it can be prioritized for review during subsequent packaging confirmation and disposal path classification. Thus, the material carrying unit and lifecycle tracking record formed by the aforementioned carrying module are further linked to a continuous risk transmission relationship through the inheritance module in this embodiment, and are consistent with the subsequent confirmation of the source of the packaging container and the classification results of the disposal path of the tailings and packaging containers.

[0042] The sealing and verification module is used to match the filling process data with the time information of the material carrier unit during the tailings packaging process to determine the material carrier unit received by the packaging container and confirm the source of the tailings corresponding to the packaging container. This module is used to establish the correspondence between the material carrier unit and the packaging container during the tailings packaging stage. By matching the flow data, time information and packaging process data during the filling process, the system can identify the source of the tailings entering each packaging container, thereby ensuring the traceability of the source relationship between the packaging container and the tailings material.

[0043] The sealing and verification module confirms the material carrier unit received by the packaging container according to the following steps: The pipeline length, cross-sectional area, tailings transport flow rate, valve opening time, valve closing time, and packaging container weighing data of the filling channel are obtained, and the filling time interval of the packaging container is determined accordingly. The theoretical arrival time interval of the material carrying unit is determined based on the time when the material carrying unit enters the filling channel, the tailings conveying flow rate, and the volume of the filling channel. The filling time interval is overlapped with the theoretical arrival time interval. When there is an overlap, the corresponding material carrying unit is identified as a candidate to enter the material carrying unit. The candidate entry mass is determined based on the tailings conveying volume and slurry density corresponding to the candidate entry material carrying unit, and the actual entry mass is determined based on the weighing increment of the packaging container within the corresponding time interval. When the quality deviation between the candidate entry quality and the actual entry quality is within a preset range, the material carrier unit is confirmed to have entered the packaging container, and a packaging confirmation record is generated to determine the source of the tailings corresponding to the packaging container.

[0044] Specifically, in this embodiment, the sealing and verification module acquires basic parameters during the filling process before the tailings packaging begins, and determines the filling time interval of the packaging container accordingly. Specifically, it acquires the pipeline length, channel cross-sectional area, tailings conveying flow rate, valve opening time, valve closing time, and packaging container weighing data of the filling channel. In this embodiment, the pipeline length of the filling channel is 6m, the channel cross-sectional area is 0.0025m², the filling channel volume is 0.009m³, the tailings conveying flow rate is 1.8m³ / h, the valve opening time is 14:20:10 on March 11, 2026, and the valve closing time is 14:20:34 on March 11, 2026, thus determining the filling time interval of the packaging container to be 24s. Simultaneously, the time information of the material carrying unit entering the filling channel, generated in the aforementioned embodiment, is read as the starting basis for subsequently determining the theoretical arrival time interval.

[0045] After obtaining the aforementioned filling time interval, the theoretical arrival time interval of the material carrying unit is determined based on the time it enters the filling channel, the tailings conveying flow rate, and the volume of the filling channel. In this embodiment, a certain material carrying unit enters the filling channel at 14:20:05. Under the condition of a tailings conveying flow rate of 1.8 m³ / h, the propagation time required for the tailings to pass through a 0.009 m³ filling channel is approximately 18 seconds. Therefore, the theoretical arrival time interval of this material carrying unit is determined to be from 14:20:23 to 14:20:29. Subsequently, the aforementioned filling time interval and the theoretical arrival time interval are overlapped. When there is an overlap, the corresponding material carrying unit is determined as a candidate material carrying unit. In this embodiment, there is a 6-second overlap between 14:20:23 and 14:20:29, therefore, this material carrying unit is determined as a candidate material carrying unit.

[0046] After determining the aforementioned candidate material carrier units, the candidate entry mass is determined based on the corresponding tailings conveying volume and slurry density, and the actual entry mass is determined based on the weighing increment of the packaging container within the corresponding time interval. Specifically, the aforementioned overlapping interval lasts for 6 seconds, and under a conveying flow rate of 1.8 m³ / h, the corresponding tailings conveying volume is approximately 0.003 m³; in this embodiment, the slurry density is 1.45 t / m³, thus the candidate entry mass is approximately 4.35 kg. The weighing data of the packaging container within the same time interval increases from 186.20 kg to 190.40 kg, and the corresponding actual entry mass is 4.20 kg. In this embodiment, the preset range for mass deviation is set to ±0.30 kg, which is predetermined based on the packaging container weighing accuracy of ±0.10 kg, the tailings conveying metering error range of ±0.15 kg, and the instantaneous fluctuation correction margin of ±0.05 kg in the filling channel. Since the mass deviation between the candidate entry mass and the actual entry mass is 0.15 kg, which is within the preset range of ±0.30 kg, it is determined that the candidate entry material carrying unit meets the mass verification conditions.

[0047] After the aforementioned time overlap verification and quality verification conditions are met, the material carrier unit is confirmed to have entered the packaging container, and a packaging confirmation record is generated to determine the source of the tailings corresponding to the packaging container. Specifically, the packaging confirmation record includes the packaging container number, the corresponding material carrier unit identifier, the filling time interval, the theoretical arrival time interval, the candidate entry quality, the actual entry quality, and the quality deviation result. In this embodiment, the packaging confirmation record is simultaneously associated with the aforementioned lifecycle tracking record and risk inheritance record, enabling the source of the tailings corresponding to the packaging container to be traced back to the material carrier unit entering the filling channel. When multiple candidate material carrier units appear in another candidate interval and all overlap with the filling time interval, their respective candidate entry qualities are calculated separately according to the aforementioned method, and then compared one by one with the actual entry quality within the corresponding time interval of the packaging container. Finally, the material carrier unit with the smallest quality deviation within the preset range is selected as the confirmed object for entering the packaging container. In this way, the material carrier unit, lifecycle tracking record, and risk inheritance record formed in the aforementioned implementation method are further correlated with the packaging container through the packaging confirmation record in this embodiment, thereby providing a continuous data foundation for subsequent disposal path classification.

[0048] The grading module is used to obtain the radioactivity risk level of tailings based on the detection data, and to determine the reliability and historical completeness of the data attribution by combining the information of the material carrier unit and the risk inheritance record, thereby generating the grading results of the disposal path of tailings and packaging containers. This module is used to conduct risk assessment and disposal path division of tailings or packaging containers after the tailings treatment process is completed. By analyzing the radioactivity risk level reflected in the detection data, and combining the data records of the material carrier unit during the treatment process and the risk inheritance record, the module determines the reliability of the tailings data attribution and the completeness of the historical record, thereby providing data basis for the subsequent disposal methods of tailings or packaging containers.

[0049] Specifically, the radioactivity risk level of the tailings is obtained based on the detection data. Specifically, the detection data corresponding to the tailings or packaging containers is read, including radioactivity intensity data, nuclide composition data, and total activity value, and the radioactivity level of the tailings is classified according to pre-set risk classification rules. In this embodiment, a total activity value not higher than 40 Bq / g is defined as low risk, a total activity value higher than 40 Bq / g but not higher than 80 Bq / g is defined as medium risk, and a total activity value higher than 80 Bq / g is defined as high risk. Through the above method, the detected nuclide activity information is converted into the corresponding radioactivity risk level of the tailings, providing a basis for determining the subsequent disposal path.

[0050] The reliability of data attribution is determined by combining information from the material carrier unit. Specifically, the packaging confirmation record corresponding to the packaging container and the relevant material carrier unit information are read to determine whether the source of the tailings corresponding to the packaging container is unique and whether the time matching and quality verification results in the packaging confirmation process meet the conditions. When the packaging container corresponds to only one material carrier unit that has passed the time overlap verification and quality verification, and the material carrier unit is not marked as an abnormal carrier unit, the reliability of data attribution is determined to be high; when the packaging container corresponds to multiple candidate material carrier units or there are abnormal carrier unit markings, the reliability of data attribution is determined to be low.

[0051] Historical completeness is determined by combining risk inheritance records. Specifically, the record information of the corresponding material carrier unit from initial inspection, process flow, rework to packaging confirmation is read to determine whether there are continuous time records, process records, and radionuclide composition records. When the material carrier unit has complete lifecycle tracking records and the risk inheritance records formed during rework are continuously closed, the historical completeness is determined to be complete; when there are missing inspection records, incomplete rework path records, or abnormal inheritance records that have not been reviewed, the historical completeness is determined to be incomplete.

[0052] Based on the aforementioned tailings radioactivity risk level, data attribution reliability, and historical integrity, a classification result for the disposal path of tailings and packaging containers is generated. In this embodiment, the disposal paths are divided into three categories: general disposal path, controlled storage disposal path, and key review disposal path. When the tailings radioactivity risk level is low, the data attribution reliability is high, and the historical integrity is complete, a general disposal path is generated; when the tailings radioactivity risk level is medium, the data attribution reliability is high, and the historical integrity is complete, a controlled storage disposal path is generated; when the tailings radioactivity risk level is high, or the data attribution reliability is low, or the historical integrity is incomplete, a key review disposal path is generated. Through the above method, the material carrying unit information, risk inheritance record, and packaging confirmation record formed in the aforementioned implementation method can be used together as the basis for disposal decision-making, thereby achieving a unified determination of the disposal path of tailings and packaging containers.

[0053] The above formulas are all dimensionless calculations. The formulas are derived from software simulations based on a large amount of collected data to obtain the most recent real-world results. The preset parameters and thresholds in the formulas are set by those skilled in the art according to the actual situation.

[0054] The above description is merely a preferred embodiment of the present invention and is not intended to limit the present invention in any way. Although the present invention has been disclosed above with reference to preferred embodiments, it is not intended to limit the present invention. Any person skilled in the art can make some modifications or alterations to the above-disclosed technical content to create equivalent embodiments without departing from the scope of the present invention. Any simple modifications, equivalent changes and alterations made to the above embodiments based on the technical essence of the present invention without departing from the scope of the present invention shall still fall within the scope of the present invention.

Claims

1. A safe disposal system for the resource recovery and recycling of radioactive tailings residue, characterized in that, include: The batch boundary module is used to perform time-series analysis on radioactivity intensity data, nuclide composition data, slurry density data and flow rate data collected during the tailings transportation and treatment process. It determines the true batch boundary of tailings by calculating the degree of characteristic change between adjacent time intervals and generates batch boundary information. The transition module is used to set transition intervals on both sides of the batch boundary, analyze the changes in nuclide composition and residence time of tailings within the transition interval, determine the contribution ratio of tailings from the previous batch and the contribution ratio of tailings from the subsequent batch, and form a transition data object accordingly. The carrier module is used to generate tailings material carrier units based on batch boundary information and transition data objects, and to use the material carrier unit as the unique data identifier of tailings during the detection and packaging process. The inheritance module is used to extract the original nuclide composition information, historical test records and historical risk levels of the material carrier unit during tailings rework to form the original risk identifier, and to add new test records during the rework process to form a risk inheritance record. The sealing and verification module is used to match the filling process data with the time information of the material carrier unit during the tailings packaging process, determine the material carrier unit received by the packaging container, and confirm the source of the tailings corresponding to the packaging container. The grading module is used to obtain the radioactivity risk of tailings based on the detection data, and to determine the data attribution reliability and historical integrity by combining the material carrying unit information and risk inheritance records, thereby generating the disposal path grading results of tailings and packaging containers.

2. The safe disposal system for the resource recovery and recycling of radioactive tailings residue according to claim 1, characterized in that, The batch boundary module determines the true batch boundary of tailings according to the following steps: During the tailings transportation process, data on radioactivity intensity, nuclide composition, slurry density, and flow rate are collected, and the variation of each monitoring data is calculated within a continuous sampling period. A joint comparison of various change magnitudes is conducted, and a synchronous mutation interval is determined only when the change magnitudes of at least two types of monitoring data simultaneously exceed the preset mutation threshold within the same time window. The synchronous mutation interval is continuously periodically confirmed, and it is retained as a candidate boundary interval only when the mutation occurs consecutively in multiple sampling periods. The tailings conveying volume is calculated based on the tailings conveying flow rate and the duration of the candidate boundary interval. The calculated tailings conveying volume is compared with the preset minimum conveying volume threshold. Only when the tailings conveying volume is not less than the minimum conveying volume threshold is it determined as a valid boundary interval. A stable zone is set after the effective boundary interval. When the variation of the monitoring data in each sampling cycle within the stable zone remains within the preset stable range, the starting position of the effective boundary interval is determined as the true batch boundary of the tailings.

3. The safe disposal system for the resource recovery and recycling of radioactive tailings residue according to claim 2, characterized in that, The minimum transport volume threshold is modified based on the residual volume of the tailings transport pipeline, the response delay time of the radioactive detection equipment, and the batch boundary diffusion characteristics of the tailings in the transport pipeline. The basic minimum transport volume is formed by superimposing the residual volume with the detection delay compensation volume determined by the response delay time and the tailings transport flow rate. The batch boundary propagation distance is determined based on the tailings transport velocity and propagation time. The batch boundary diffusion volume is calculated based on the batch boundary propagation distance and the pipeline cross-sectional area. The batch boundary diffusion volume is superimposed with the basic minimum transport volume to form the dynamic minimum transport volume. When calculating the tailings conveying volume, the batch boundary module compares the actual conveying volume with the dynamic minimum conveying volume, and only confirms the effective boundary interval when the actual conveying volume is not less than the dynamic minimum conveying volume.

4. The safe disposal system for the resource recovery and recycling of radioactive tailings residue according to claim 1, characterized in that, The transition module determines the contribution ratio of the previous batch of tailings and the subsequent batch of tailings in the transition zone according to the following steps: Obtain the nuclide composition data of the first batch of tailings, the nuclide composition data of the second batch of tailings, and the nuclide composition data of the tailings in the transition zone, and construct the nuclide characteristic sequence according to the nuclide type and corresponding activity value. Based on the decay parameters of each nuclide and the detection time difference, the nuclide feature sequences are processed to unify the time reference, resulting in nuclide feature sequences under a unified time reference. The nuclide activity weights are determined based on the proportion of each nuclide activity value in the total activity value, and the nuclide feature sequences under a unified time reference are weighted according to the nuclide activity weights to form weighted nuclide feature sequences. The weighted nuclide feature sequence in the transition region is represented as a combination of the weighted nuclide feature sequences of the previous batch and the weighted nuclide feature sequences of the subsequent batch. The contribution ratio of the previous batch and the contribution ratio of the subsequent batch are obtained by proportionally calculating the sequence difference corresponding to each nuclide position. The contribution ratios of the previous batch and the subsequent batch are written into the transition data object and used as input data for the material carrying unit generated by the carrying module.

5. A safe disposal system for the resource recovery and recycling of radioactive tailings residue according to claim 4, characterized in that, Before determining the nuclide composition data of the tailings in the transition zone, the transition module corrects the intervals of the transition zone according to the following steps: Obtain the length, cross-sectional area, and effective volume of each pipe section in the tailings conveying path, and divide the conveying into segmented conveying units according to the tailings conveying sequence; The theoretical residence time of each segment conveying unit is calculated based on the effective volume of each segment conveying unit and the tailings conveying flow rate of the corresponding time period. The theoretical residence time of each segment conveying unit is then summed to obtain the basic residence time. The volumetric memory time is calculated based on the residual volume in each segment conveying unit when the previous batch of tailings is finished and the current tailings conveying flow rate. The volumetric memory time is then superimposed with the basic residence time to obtain the corrected residence time. The detection offset time is calculated based on the conveying distance between the detection location and the batch boundary formation location and the tailings conveying velocity, and the start and end positions of the transition zone are determined based on the correction residence time and the detection offset time. Nuclide composition data of tailings in the transition zone are extracted based on the determined start and end positions of the transition zone, and the extraction results are used as input data to determine the contribution ratio of the previous batch of tailings and the contribution ratio of the subsequent batch of tailings.

6. The safe disposal system for radioactive tailings resource recovery residue according to claim 1, characterized in that, The carrier module establishes a lifecycle tracking record for the material carrier unit and performs consistency verification of its flow according to the following steps: Establish a process topology based on the tailings treatment process, and record the corresponding process number, entry time and initial nuclide composition information for each material carrying unit. When the material carrying unit enters the next processing step, the current process number and the departure time of the previous process are recorded, and the legality of the process sequence relationship is verified according to the process topology. The actual dwell time is calculated based on the current process entry time, the previous process exit time, and the allowable dwell time range of the corresponding process, and the actual dwell time is matched and verified with the allowable dwell time range; When the testing or packaging process is completed, the current nuclide composition information is obtained and compared with the initial nuclide composition information for consistency. The material propagation time is calculated based on the propagation distance of the tailings in the conveying system, the residence time in the pipeline, and the processing time of each processing step. The material propagation time is then compared with the actual process time sequence of the material carrying unit. When all the above checks meet the preset conditions, the relevant process information is written into the lifecycle tracking record. When any check fails, an abnormal carrying unit mark is generated and the data verification process is started.

7. A safe disposal system for the resource recovery and recycling of radioactive tailings residue according to claim 1, characterized in that, The inheritance module performs nuclide structure consistency verification on the reworked material carrier unit according to the following steps: The original nuclide composition information, original detection time, rework detection time and rework processing path record corresponding to the material carrier unit are extracted, and the original nuclide composition sequence and rework nuclide composition sequence are constructed according to the nuclide type and corresponding activity value. Based on the decay parameters of each nuclide and the time difference between the original detection time and the rework detection time, the decay time of the reworked nuclide composition sequence is corrected to obtain the reworked nuclide composition sequence under a unified time reference. Based on the sequence of each processing step and the dwell time in the rework processing path record, the rework path propagation verification conditions are determined, and the corrected rework nuclide composition sequence is compared with the original nuclide composition sequence on a nuclide-by-nuclide basis. The consistency of the nuclide structure of the rework material carrier unit is determined based on the deviation of the proportion of each nuclide from the preset deviation range. When the deviation of any nuclide proportion exceeds the preset deviation range, the corresponding material carrier unit is written into the abnormal inheritance record and the original risk identifier remains unchanged.

8. A safe disposal system for the resource recovery and recycling of radioactive tailings residue according to claim 1, characterized in that, The sealing and verification module confirms the material carrier unit received by the packaging container according to the following steps: The pipeline length, cross-sectional area, tailings transport flow rate, valve opening time, valve closing time, and packaging container weighing data of the filling channel are obtained, and the filling time interval of the packaging container is determined accordingly. The theoretical arrival time interval of the material carrying unit is determined based on the time when the material carrying unit enters the filling channel, the tailings conveying flow rate, and the volume of the filling channel. The filling time interval is overlapped with the theoretical arrival time interval. When there is an overlap, the corresponding material carrying unit is identified as a candidate to enter the material carrying unit. The candidate entry mass is determined based on the tailings conveying volume and slurry density corresponding to the candidate entry material carrying unit, and the actual entry mass is determined based on the weighing increment of the packaging container within the corresponding time interval. When the quality deviation between the candidate entry quality and the actual entry quality is within a preset range, the material carrier unit is confirmed to have entered the packaging container, and a packaging confirmation record is generated to determine the source of the tailings corresponding to the packaging container.

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