Intelligent management method for radioactive contaminated clothing and related equipment

Abstract

The application discloses a kind of radioactive contaminated clothing intelligent management method and related equipment.The method comprises the following steps: collecting the initial radiation dose of the contaminated clothing and generation time;Based on the nuclide decay formula, a decay tracking calculation process is constructed, the current dose is calculated in real time according to the nuclide half-life parameter, and the total dose is obtained by superimposing the contribution of each nuclide when there is multi-nuclide contamination;The current dose calculated in real time is compared with the preset control threshold, and the washable instruction is pushed to the medical terminal when the control threshold is met, and the remaining decay time prompt is output when the control threshold is not met.It can solve the problem that the management of radioactive contaminated clothing is highly dependent on manual, which can easily lead to waste of manpower, missed or wrong recording, and occupational health hazards caused by frequent close contact of medical staff with high-activity contaminated clothing during manual monitoring.

Description

Technical Field

[0001] This application relates to the field of smart healthcare, and more specifically, to a method and related equipment for intelligent management of radioactive contaminated clothing. Background Technology

[0002] During radiological examinations such as PET or SPECT and radionuclide treatments such as iodine-131 and Lu177, certain doses of contaminated bedding, including pillowcases, sheets, duvet covers, and patient gowns, are generated. Because these items do not meet the relevant requirements, they need to be stored until they meet the standards before being sent to the bedding warehouse for cleaning and recycling, and then reused.

[0003] Currently, in clinical practice, it is necessary to manually record the type, quantity, and radiation dose of soiled clothing. This is prone to omissions or errors due to illegible handwriting or memory lapses. It is also necessary to periodically use a portable dosimeter to manually check the surface dose rate of each garment, which requires interrupting other diagnostic and treatment work, resulting in a waste of manpower. During manual monitoring, medical staff need to frequently come into close contact with highly active soiled clothing, and pulling on the clothing during operation may cause the generation and splashing of radioactive aerosols. Long-term accumulation may increase the probability of adverse health effects related to radiation exposure, posing an occupational health hazard. Summary of the Invention

[0004] The summary section introduces a series of simplified concepts, which will be further explained in detail in the detailed description section. The summary section of this invention is not intended to limit the key features and essential technical features of the claimed technical solution, nor is it intended to determine the scope of protection of the claimed technical solution.

[0005] To address the current issues of heavy reliance on manual labor in the management of radioactive contaminated clothing, which easily leads to wasted manpower, omissions or errors in recording, and occupational health hazards caused by frequent close contact with highly active contaminated clothing by medical personnel during manual monitoring, this invention proposes, firstly, an intelligent management method for radioactive contaminated clothing, comprising: The initial radiation dose and time of occurrence of the soiled clothing were collected; A decay tracking calculation process is constructed based on the nuclide decay formula. The current dose is calculated in real time based on the nuclide half-life parameter. When there is multi-nuclide contamination, the contributions of each nuclide are superimposed to obtain the total dose. The current dose calculated in real time is compared with the preset de-control threshold. If the de-control threshold is met, a washable command is pushed to the medical terminal. If the de-control threshold is not met, the remaining decay time is output as a prompt.

[0006] Secondly, the present invention also proposes an intelligent management device for radioactive contaminated clothing, comprising: The acquisition unit is used to acquire the initial radiation dose and the time of generation of the soiled clothing; The calculation unit is used to construct a decay tracking calculation process based on the nuclide decay formula, calculate the current dose in real time according to the nuclide half-life parameter, and sum the contributions of each nuclide to obtain the total dose when there is multi-nuclide contamination. The prompting unit is used to compare the current dose calculated in real time with the preset de-control threshold. When the de-control threshold is met, a washable instruction is pushed to the medical terminal. When the de-control threshold is not met, the remaining decay time is output as a prompt.

[0007] Thirdly, an electronic device includes: a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein the processor executes the computer program stored in the memory to implement the steps of the intelligent management method for radioactive contaminated clothing as described in any of the first aspects above.

[0008] Fourthly, the present invention also proposes a computer-readable storage medium having a computer program stored thereon, wherein the computer program, when executed by a processor, implements the intelligent management method for radioactive contaminated clothing of any of the above claims in the first aspect.

[0009] In summary, the intelligent management method for radioactive contaminated clothing proposed in this application collects the initial radiation dose and generation time of the contaminated clothing; constructs a decay tracking calculation process based on the nuclide decay formula; calculates the current dose in real time based on the nuclide half-life parameter; and sums the contributions of each nuclide to obtain the total dose when multiple nuclides are present. The calculated current dose is compared with a preset de-control threshold. If the de-control threshold is met, a washable instruction is pushed to the medical terminal; otherwise, a remaining decay time prompt is output. Thus, through calculable decay tracking, the management of radioactive contaminated clothing is upgraded from an experience-based process to a data-driven process. Compliance is reflected in the clear and traceable basis for de-control determination; efficiency is reflected in providing an estimated compliance time for each garment, reducing blind waiting and repeated measurements, and improving the utilization rate of temporary storage space; safety is reflected in reducing unnecessary contact and handling frequency, lowering peak and cumulative exposure for personnel. More importantly, this solution has advantages for large-scale scenarios. When the number of soiled bedding items increases from dozens to hundreds, the burden of manual retesting and experience-based judgment increases linearly and is prone to errors. In contrast, decay tracking calculation has a lower marginal cost, and the system can process more objects with unified rules and distribute the decision results to the execution end in the form of messages. Attached Figure Description

[0010] Various other advantages and benefits will become apparent to those skilled in the art upon reading the following detailed description of preferred embodiments. The accompanying drawings are for illustrative purposes only and are not intended to limit this specification. Furthermore, the same reference numerals denote the same parts throughout the drawings. In the drawings: Figure 1 This is a schematic flowchart of an intelligent management method for radioactive contaminated clothing provided in an embodiment of this application; Figure 2 A schematic diagram of a smart management device for radioactive contaminated clothing provided in this application embodiment; Figure 3 This is a schematic diagram of an electronic device for intelligent management of radioactive contaminated clothing, provided as an embodiment of this application. Detailed Implementation

[0011] The terms "first," "second," "third," "fourth," etc. (if present) in the specification, claims, and accompanying drawings of this application are used to distinguish similar objects and are not necessarily used to describe a specific order or sequence. It should be understood that such data can be interchanged where appropriate so that the embodiments described herein can be implemented in a sequence other than that illustrated or described herein. Furthermore, the terms "comprising" and "having," and any variations thereof, are intended to cover non-exclusive inclusion; for example, a process, method, system, product, or apparatus that comprises a series of steps or units is not necessarily limited to those steps or units explicitly listed, but may include other steps or units not explicitly listed or inherent to such processes, methods, products, or apparatus. The technical solutions of the embodiments of this application will now be clearly and completely described in conjunction with the accompanying drawings. Obviously, the described embodiments are only a part of the embodiments of this application, and not all of them.

[0012] To address the current issues of over-reliance on manual management of radioactive contaminated clothing, which leads to wasted manpower, omissions or errors in recording, and occupational health hazards caused by frequent close contact with highly contaminated clothing by medical personnel during manual monitoring, please refer to [link to relevant documentation]. Figure 1 This is a schematic diagram of a method for intelligent management of radioactive contaminated clothing provided in an embodiment of this application, which may specifically include steps S110 to S130.

[0013] S110, collect the initial radiation dose and the time of generation of the soiled clothing.

[0014] S120 constructs a decay tracking calculation process based on the nuclide decay formula, calculates the current dose in real time according to the nuclide half-life parameter, and superimposes the contributions of each nuclide when there is multi-nuclide contamination to obtain the total dose.

[0015] S130, compare the current dose calculated in real time with the preset de-control threshold, push a washable command to the medical terminal when the de-control threshold is met, and output the remaining decay time prompt when the de-control threshold is not met.

[0016] It is understandable that the radioactivity level of radiocontaminated clothing decreases over time from the moment it is generated, but the rate of decrease is not determined by empirical estimation, but by the half-life and decay law of the nuclide. This scheme transforms the empirical judgment of when contaminated clothing can be washed into a calculable determination process: an initial radiation dose value is recorded at the moment of generation, with the generation time as the zero point; the dose value at any subsequent moment can be calculated using the decay formula. By comparing the calculated current dose with the preset release threshold, a deterministic output of whether the clothing can be washed now or how long it needs to wait can be obtained. The key to this scheme is not to increase the number of monitoring sessions, but to establish a decay tracking calculation process, enabling the management system to consistently evaluate contaminated clothing from different batches and different nuclide sources using uniform rules, and to directly quantify the remaining waiting time, avoiding overly conservative or overly aggressive approaches based solely on human experience. For contaminated clothing contaminated with a single nuclide, if the dose rate or equivalent dose index measured at the moment of generation is the initial dose, and the half-life of the nuclide is known, the current dose at any moment can be calculated based on the exponential decay law. The physical meaning of exponential decay is that after each half-life, the activity of a nuclide decreases to half of its previous value. In engineering management, dose rate and activity can be considered to decay synchronously with activity, thus allowing for time-series dose estimation by using the half-life parameter as the driving force. For soiled clothing contaminated with multiple nuclides, a single half-life model is insufficient to characterize the true decay process because the half-lives of different nuclides can vary significantly, and the dominant nuclide may change over different time periods. This solution treats the total dose as the sum of the dose contributions of each nuclide at the computational level. Each nuclide decays independently according to its own half-life. The system calculates the current dose contribution of each nuclide at the same time and then sums them to obtain the total dose. This avoids approximating all contamination with the half-life of a single nuclide, thereby improving the accuracy of the decontamination point prediction. Hospitals or regulatory requirements typically provide decontamination thresholds. When the current dose of soiled clothing is below the threshold, it can enter the washing process according to normal procedures; when it is above the threshold, it must continue to undergo temporary decay or be disposed of in other ways. This scheme uses threshold comparison as the decision trigger condition and outputs the results in two forms: when the threshold is reached, a washable instruction is output; when the threshold is not reached, a remaining decay time indication is output. The remaining decay time indication is not an empirical estimate, but is derived by combining the order of magnitude difference between the current dose and the threshold with the decay rate, and can be directly used for scheduling and capacity planning.

[0017] For example, in departments related to nuclear medicine examinations or radionuclide therapy, when contaminated linens are removed from the clinical setting and placed into temporary storage, the initial information is collected by a data acquisition terminal. The initial radiation dose can be collected using a dose rate meter, portable radiation monitoring equipment, or a fixed monitoring station. During collection, the system records at least the following elements: the initial dose value of the contaminated linen under the given conditions, the collection timestamp, and the generation timestamp. The generation time can be automatically retrieved by the operational system, for example, using the time the patient completes medication or examination, or the time the contaminated linen is removed from the contaminated area as the generation time anchor. When the operational system is unavailable, the generation time can also be confirmed and entered by staff on the terminal, and the system will logically verify the consistency between the entered time and the collection time, for example, to prevent the generation time from being later than the collection time. To ensure the reliability of subsequent decay calculations, initial dose collection can also be configured with measurement procedures, such as specifying probe distance, measurement direction, and measurement duration, to ensure that the values ​​of the same type of linen under different shifts and by different personnel are comparable. After data acquisition, the system records the initial dose and generation time in the entry for that contaminated garment, serving as the input for subsequent decay tracking calculations. For example, in a fluorine-18-related inspection area, a garment is measured as it exits the contaminated area, with the initial dose recorded as a specific dose rate value and the generation time recorded as the end time of the inspection. Due to the short half-life of fluorine-18, the system can predict the time point when the threshold is reached on a timescale of several hours, thus avoiding mixing this garment with garments containing long-half-life nuclides and preventing them from occupying temporary storage space for extended periods.

[0018] For example, the system maintains a table of radionuclide half-life parameters in the background. This table can be configured by the management terminal and includes at least the half-lives of common nuclear medicine radionuclides and configuration items related to dose conversion. Updates to the table are versioned to ensure traceability of calculation results at different stages. For each contaminated garment, the system obtains the corresponding half-life parameters based on the known type of contaminating radionuclide. When multiple radionuclides are present, the system establishes a decay tracking calculation chain for each radionuclide. The chain input includes the initial dose contribution and generation time corresponding to the radionuclide, and the chain output is the current dose contribution at any given time. Real-time calculation can be implemented using a combination of event triggering and timed refresh. Event triggering includes new registration, parameter updates, threshold adjustments, and manual retest data writing; timed refresh is used to periodically update the current dose and remaining time prompts, and the refresh cycle can be set to minutes or hours as needed. During calculation, the system uses the time difference between the current time and the generation time as the decay time variable and substitutes it into the decay formula to obtain the current dose. In cases of multi-nucleoside contamination, the system calculates the dose for each nuclide simultaneously, then sums them to obtain the total dose, which is used as the threshold comparison input. To ensure the stability of real-time calculations, the system can divide the calculation results into two categories: one is the numerical result of the current dose, used for immediate judgment; the other is the predicted value at several key future time points, used to provide indications of remaining decay time and for backward scheduling, such as predicting the earliest and latest time when the threshold will be reached. The earliest predicted time can be deduced by working backward from the relationship between the current dose and the threshold, while the latest time can be incorporated into the measurement error margin and parameter error margin to suggest a more conservative waiting window. For example, a piece of contaminated clothing contains traces of both iodine-131 and technetium-99m. Technetium-99m has a shorter half-life, while iodine-131 has a longer half-life. In the initial period, technetium-99m may contribute significantly, but after tens of hours, its contribution significantly decreases, and the remaining total dose is mainly determined by iodine-131. Using the half-life of technetium-99m as an approximation would lead to the system misjudging that it has reached the target too quickly. By using the method of decaying each nuclide separately and then superimposing the results, the risk of iodine-131 dominating in the later stage can be identified earlier, thereby avoiding premature release.

[0019] For example, the system presets a control threshold and allows the management terminal to configure it. The threshold can be set with different values ​​according to the type of clothing, department, or treatment process, but in the main line of claim 1, the threshold can be used as a comparison threshold. The system performs a comparison after each refresh of the calculation results: if the current dose is not higher than the threshold, a washable instruction is generated and pushed to the medical or logistics terminal; if the current dose is higher than the threshold, the system calculates the decay time still required to reach the target and outputs it in the form of a prompt, which may include the expected date and time of reaching the target, as well as a suggested temporary storage strategy during this period, such as continuing to store until the expected time point for review. The calculation of the remaining decay time can be obtained based on the inverse relationship of exponential decay. For single nuclide contamination, the system can directly inversely calculate how many half-lives are needed from the ratio of the current dose to the threshold combined with the half-life, thereby calculating the expected time to reach the threshold. For multi-nucleoside contamination, the system can use a numerical method to search for the time point to reach the threshold, for example, by extrapolating the total dose into the future with a certain time step and finding the moment when it first falls below the threshold, and this moment can be used as the basis for the remaining decay time prompt. This numerical calculation can simultaneously output a range to cover measurement and model errors. When pushing a washable instruction, the system can include the identification information and compliance timestamp of the soiled garment, facilitating subsequent process integration. The push channel can be a mobile application, SMS, workstation messages, or the hospital's messaging system; the key is to ensure the instruction is reachable and traceable. For example, in a batch of soiled garments, some are from short-half-life nuclides, and some are from long-half-life nuclides. The system calculates and outputs the estimated compliance time for each garment separately. Logistics personnel can then prioritize garments nearing compliance in the available washing window, while continuing to store garments requiring longer waiting times, avoiding peak congestion of washing resources caused by a single concentrated release and mitigating compliance risks associated with premature washing.

[0020] For example, the nuclide decay formula is A(t) = A0 × e −λt (λ=ln2 / T) 1 / 2 T 1 / 2 The current dose is calculated in real time (based on the half-life).

[0021] It is understandable that the effect of collecting the initial dose and generation time is not only to obtain two fields, but also to fix the starting point of decay calculation, so that the dose estimation at any subsequent moment has a traceable physical basis. Without the generation time, it is impossible to determine how long the decay time has been, and the system can only rely on remeasurement or experience; without the initial dose, it is impossible to quantify the initial amplitude of the decay curve and to estimate the remaining time. Therefore, the system can still provide actionable time prompts without frequent remeasurement, thereby reducing the frequency of manual measurement and operational exposure opportunities. The technical effect of the decay tracking calculation process is reflected in the prediction accuracy and consistency. For clothing from the same nuclide source, the decay law is consistent, and the target time calculated by the system is repeatable, reducing the judgment differences between different personnel and shifts. For multi-nucleoside contamination, calculating and superimposing separately can avoid the systematic bias caused by using a single half-life to represent all contamination, thereby reducing the probability of premature de-escalation or overly conservative approaches. By comparing with the de-escalation threshold and outputting two types of results, the system standardizes key action nodes. Push notifications when thresholds are reached reduce the problem of staff forgetting to recheck or missing processing windows; reminders of remaining time before thresholds are reached transform uncontrollable waiting into plannable waiting, providing a definitive basis for temporary storage capacity, washing schedules, and staffing arrangements. Furthermore, it reduces the need for repeated manual measurements and minimizes the time staff spend near radioactive environments, thereby lowering occupational exposure risks.

[0022] In some examples, it also includes: The soiled bedding is uniquely identified by RFID tags or barcodes. Based on the unique identity binding result, the soiled clothing category information is automatically associated, and consistency verification is performed on the registered soiled clothing type and quantity. When the consistency check fails to meet the preset rules, an abnormal warning message is output.

[0023] In some examples, the summation of the contributions of each nuclide in the presence of multi-nucleon contamination to obtain the total dose includes: Retrieve the half-life and decay parameters corresponding to the contaminated nuclides in the soiled clothing from the nuclide-specific decay model library; When multiple nuclides are present, the dominant nuclide is determined based on the initial dose ratio or dose contribution of each nuclide over time, and the remaining decay time indication is dynamically corrected based on the dominant nuclide.

[0024] It is understandable that multi-nucleoside contamination essentially involves the simultaneous presence of several radioactive nuclides on the same contaminated garment. Each nuclide has a different half-life, radiation type, and energy spectrum, thus their contribution to the dose indicator varies over time. If a single half-life or single decay formula is used to calculate the total dose, systematic biases will occur, especially near the critical stage when the desensitization threshold is approaching. This bias is most likely to lead to incorrect remaining time indications. The nuclide-specific decay model library parameterizes and stores the decay patterns of each nuclide, enabling the calculation process to have two capabilities. First, it allows for the selection of the correct half-life parameter for different nuclides, avoiding the misapplication of the decay rate of short-half-lived nuclides for long-half-lived nuclides. Second, when more precise parameters are needed, in addition to the half-life, other decay-related parameters can be retrieved, such as the decay constant, branching ratio, and nuclide-specific coefficients used for dose conversion, thereby more accurately mapping activity changes to dose contribution changes. In multi-nucleus stacking, the total dose is the sum of the dose contributions of each nuclide. However, the indication of reaching the target dose depends not only on the difference between the current total dose and the threshold, but also on the rate of decrease of the total dose over a subsequent period. The rate of decrease of the total dose may be determined by different nuclides at different time periods. For example, short-half-lived nuclides decrease rapidly in the initial stage and contribute significantly to the rate of change of the total dose; however, after a period of time, the contribution of short-half-lived nuclides almost disappears, and the rate of decrease of the total dose is dominated by long-half-lived nuclides, resulting in a slower decrease. Therefore, if the remaining decay time indication is always calculated based on the current rate of decrease of the total dose or the proportion at the initial moment, significant errors will occur when the dominant nuclide switches. The purpose of determining the dominant nuclide is to identify the nuclide that has the most decisive effect on the change of the total dose at the current moment or in the future critical interval, and then use the decay rate of that nuclide to correct the prediction of the remaining time, making the indication closer to the actual time of reaching the target dose. The initial dose proportion criterion emphasizes absolute contribution. When a particular nuclide contributes a high percentage of the dose initially and its half-life is not extremely short, it tends to dominate the total dose for a considerable period, making it suitable for rapid determination in the early stages or when high-frequency refresh rates are lacking. The dose contribution rate-of-change criterion emphasizes the factors determining the rate of decrease. Even if a nuclide's current contribution is not the largest, as long as it contributes the most to the rate of decrease in the total dose, it is more likely to determine the time required to reach the threshold. This criterion is more suitable for use in the critical phase or when the dominant nuclide is about to switch, as it directly reflects how quickly the total dose will decrease in the short term. The two criteria are not mutually exclusive but rather complementary strategies for different stages. The initial percentage criterion is more robust and computationally simpler; the rate of change criterion is more sensitive and closer to critical decisions, but requires more timely computational updates and more reliable nuclide decomposition.

[0025] For example, a nuclide-specific decay model library can be stored in the background as a table of nuclide parameters or a set of versioned configuration files. Each nuclide entry contains at least a half-life parameter to determine the decay rate; it may also contain decay parameters for dose contribution calculation. In engineering implementations, these decay parameters typically include: a decay constant that maps a time variable to an attenuation factor, and a nuclide-specific conversion factor or correction factor used when activity needs to be mapped to dose rate. When the system receives a soiled garment determined to be contaminated with multiple nuclides, it first queries the model library one by one according to the nuclide list, loads the corresponding parameters, and caches them in the calculation object of the soiled garment to support subsequent real-time updates. To adapt to actual changes in medical institutions, the model library should support parameter version control. This way, when the half-life parameter or conversion factor is revised, the system can record the revised version and reproduce the parameter version used at the time when reviewing historical judgment results, avoiding situations where the same input yields different historical conclusions at different times that cannot be explained. The dominant nuclide can be determined based on the initial dose contribution. When establishing a multi-nuclide object, the system assigns an initial dose contribution value to each nuclide. This value can come from actual energy spectrum decomposition results, reported and experienced proportions of nuclides from pollution sources, or historical statistics of similar scenarios. The system divides the initial dose contribution of each nuclide by the initial total dose to obtain a proportion sequence, and selects the nuclide with the highest proportion that meets the minimum proportion threshold as the dominant nuclide. To prevent frequent switching due to very close proportions, the system can introduce hysteresis rules, such as switching only when the proportion of a new nuclide exceeds a certain difference from the proportion of the current dominant nuclide. Alternatively, the dominant nuclide can be determined based on the rate of change of dose contribution over time. The system can obtain the current dose contribution of each nuclide at any refresh time, as well as the predicted dose contribution at the next refresh time, or directly calculate the instantaneous decay slope at that time. The system uses the absolute value of the rate of decrease of the dose contribution of each nuclide as a weight, and selects the nuclide with the largest absolute value of the rate of decrease as the dominant nuclide. This method is more effective in the critical stage because it reflects the rate at which the total dose will decrease in the short future time, and this rate is mainly determined by the nuclide with the largest rate of decrease contribution. To avoid instability when the overall descent rate is very small in the later stages, the system can introduce a minimum slope threshold. When the absolute values ​​of the slopes of all nuclides are below the threshold, the dominant nuclide is determined by the indicator of the largest dose contribution. For example, a segmented strategy can be adopted, using the initial proportion criterion when the target is far away, and the rate of change criterion when the target is close to the threshold or expected to be reached, in order to balance stability and accuracy.

[0026] For example, the remaining decay time indicator can be understood as the system's output of the expected attainment time and the remaining waiting time. This indicator is not fixed after a one-time calculation, but rather the attainment time is reassessed based on the current dominant nuclide each time the calculation results are refreshed or new data is received. The system can first use a complete multi-nuclide superposition model to calculate the total dose curve on the future time axis and find the time point when the total dose first does not exceed the threshold as the basic attainment time. Subsequently, the system corrects this basic attainment time using the decay characteristics of the dominant nuclide. For example, when the dominant nuclide is a long half-life nuclide, a conservative correction is introduced to slightly adjust the indicator time backward to cover the risk of misjudging the attainment time due to estimation errors caused by the contribution of other nuclides; when the dominant nuclide is a short half-life nuclide, a fine correction is introduced to make the indicator closer to the short-term rapid decline phase and reduce the waste of resources caused by excessive conservatism. Other dynamic correction methods can also be used. For example, instead of relying solely on the total dose curve when calculating the remaining time, the decay slope of the dominant nuclide can be used as the primary constraint. This is equivalent to approximating the total dose decay rate by the decay rate controlled by the dominant nuclide in a local time period, thereby quickly updating the remaining time indicator. This method is easier to implement when the terminal refreshes frequently and requires real-time prompts.

[0027] Understandably, this elevates decay calculation from a general exponential decay to a parameterized decay calculation identifiable by the nuclide. The direct result is that when nuclides differ significantly in half-life, the system no longer requires manual selection of calculation parameters, thus reducing systematic errors caused by human configuration mistakes. Simultaneously, when a certain type of nuclide appears frequently, the unified parameters in the model library ensure consistent predictions for similar contaminated linens, facilitating cross-departmental alignment of management rules. Remaining time indicators are no longer misled by early rapid decay phases. In multi-nuclide scenarios, the most common error pattern is that the system or personnel only see the rapid decline caused by short-half-life nuclides and infer that the total dose will continue to decline rapidly, thus outputting premature target achievement times. The dominant nuclide mechanism significantly reduces this error by identifying different decisive nuclides at different time periods. The effect of dynamic correction is reflected in indicator availability and risk control. Indicators are updated over time, synchronized with the actual decay process, allowing managers to schedule shifts and plan capacity accordingly, rather than making decisions based on outdated predictions. Risk control refers to the following: In the critical stage, when the dominant nuclide is a long half-life nuclide, the system can reduce the probability of premature de-control through conservative correction; when the dominant nuclide is a short half-life nuclide, the system can reduce excessive waiting through fine correction.

[0028] In some examples, it also includes: When the control release threshold is met, a washable instruction is pushed to the medical terminal, and a washable status marker is generated for the soiled clothing and the control release timestamp is recorded. The inventory and location status of soiled linens are updated based on the washable status markers, and a retention warning is generated for soiled linens that have not been washed within the specified period. Generate a statistical report containing at least one piece of information: the number of items released from control, the number of items to be sent for washing, and the number of items that have not been sent for washing within the specified time.

[0029] Understandably, in the management of radioactive contaminated clothing, reaching the de-contamination threshold only satisfies the condition for allowing entry into the washing process, not equates to actually entering the washing process. In actual operation, factors such as shift handover, insufficient transport capacity, congested washing equipment scheduling, mixed storage in temporary storage areas, and personnel forgetfulness can cause clothing that has met the standards to not be transferred or washed in a timely manner. If the system only pushes a washable instruction once without writing the event into the state machine and recording a timestamp, it is difficult to trace when the standard was met, how long it remained after meeting the standard, and whether there were any process blockages. It is also impossible to automatically identify and warn against overdue stays. Therefore, this solution upgrades the de-contamination judgment from a one-time message output to a manageable and statistically significant state change event through washable status markers and de-contamination timestamps. The washable status marker allows each piece of clothing to enter a clear state range at the data level, and the de-contamination timestamp gives this state range a time starting point, thereby allowing the calculation of the stay duration and triggering of rules. The risks in the management of radioactive contaminated clothing come not only from the dose level but also from the uncertainty of physical location and logistics status. If clothing remains in the radioactive temporary storage area after meeting the standards, it may lead to two types of problems: First, managers may mistakenly believe that the standards are still not met and repeat measurements or waiting, resulting in efficiency losses; second, mixing compliant and non-compliant clothing can cause picking errors, and even the risk of non-compliant clothing being mistakenly sent for washing. By synchronously updating inventory and location status based on status tags, the system can explicitly distinguish washable items from temporary storage items and locate them in logical locations such as the waiting-for-transfer area and the waiting-for-washing area, thereby reducing the probability of mixed storage and misoperation. In the management regulations of most institutions, prolonged retention in temporary storage or waiting-for-transfer areas after the standards have been lifted can bring management risks, such as hygiene management requirements, cross-contamination risks, accumulation risks due to space occupation, and increased traceability difficulties. The principle of the retention warning is to define a maximum allowable retention time or a latest allowable washing time starting from the lifting timestamp. When this constraint is exceeded, the system automatically generates a warning and can point the warning to a specific object and location, thereby making management conflicts explicit. When the number of soiled linens is large, individual item tracking is insufficient to support resource allocation decisions. Statistical reports summarize the status of individual items into operational metrics. For example, the number of items released from control reflects the daily target release scale, the number of items awaiting washing reflects short-term logistical pressure, and the number of items overdue for washing reflects process anomalies and risk exposure. By periodically generating statistical reports, managers can assess whether temporary storage capacity is insufficient, whether washing capacity is matched, whether transfer shifts need adjustment, and which time periods have the most anomalies, thereby achieving continuous optimization.

[0030] For example, when the system determines that the current dose is not higher than the de-control threshold and pushes a "washable" instruction to the medical terminal, it simultaneously writes a status change for the soiled garment in the background. The status change includes at least setting the garment's status field to "washable" and recording a de-control timestamp next to the status field. The de-control timestamp is usually the time the system determined the condition was met, but it can also be the closest calculation and refresh time; the key is to maintain a consistent rule. For traceability, the system can write this status change to an event log, which can include the calculation basis for meeting the condition, such as the current dose value, threshold value, radionuclide parameter version number, and calculation time. This allows for the reconstruction of why the garment was deemed washable in case of disputes or audits. On the terminal side, the push message can carry a summary of the status marker, such as "de-control, status is washable, de-control time is [time]," ensuring that the status of the personnel on-site is consistent with the system's.

[0031] For example, inventory updates typically involve changes at both the quantity and location levels. After a garment's status changes to "ready for washing," the system removes it from the pending decay inventory set and adds it to the pending washing inventory set. Simultaneously, the system updates its location status. Location status can be determined from barcode scanning or RFID access control, or by staff performing a location confirmation operation via a handheld terminal during handling. Location status updates should match the actual site layout; for example, the garment's location is marked as a specific cell in the pending washing storage rack for quick on-site location. The rules for generating overdue warnings can be designed to start timing from the release timestamp. If no status event indicating "washed" or "transferred to the washing area" appears within the preset maximum overdue period, it is considered overdue and an overdue warning is generated. The warning content includes at least the object identifier, release timestamp, current location, and overdue duration, and is pushed to the corresponding responsible terminal. To avoid false alarms, the system can set warning levels; for example, a prompt is generated when the expiration date is approaching, and a higher-level warning is generated after the expiration date is exceeded, with the number of warning triggers recorded.

[0032] In some cases, considering the transformation from parent to daughter nuclides in multi-nucleotope contamination, and the significant radiation contribution of daughter nuclides, the total dose may not necessarily decrease monotonically and rapidly over time. Late dose rebound can occur, such as when daughter nuclides are generated with a time lag, or when parent nuclides continuously generate daughter nuclides during decay. The activity of daughter nuclides may initially increase and then decrease over time. When the management system estimates the total dose solely based on the decay of parent nuclides, it may underestimate the total dose after a certain period. Alternatively, daughter nuclides may be more easily escaped or detected, and may exist in gaseous form, as volatile components, or with higher energy spectrum components, making their contribution to the external dose rate more significant under certain environmental conditions. This leads to a delayed increase in the external dose rate of clothing during resting periods; furthermore, material release kinetics introduce additional hysteresis, and clothing fibers undergo adsorption and desorption processes for contaminating nuclides or their decay products. Even if daughter nuclides have already formed inside the fiber, their contribution to the external measurable dose is still controlled by the desorption rate, resulting in a time shift in the peak external dose rate relative to the peak activity. Based on this, in some examples, the summation of the contributions of each nuclide to obtain the total dose in the presence of multi-nucleon contamination includes: Identify whether a decay chain consisting of a parent nuclide and its daughter nuclide exists in the multi-nucleoside contamination; When the decay chain is identified, a time-varying activity calculation model for the parent nuclide and the daughter nuclide is established based on the Bateman equations, and the time-varying activity corresponding to the daughter nuclide is converted into the time-varying dose contribution of the daughter nuclide. The total dose is obtained by superimposing the time-varying dose contribution of the daughter nuclide with the dose contributions of the parent nuclide and other nuclides.

[0033] In some examples, it also includes: When the time-varying activity is converted into the time-varying dose contribution of the daughter nuclide, daughter release kinetic parameters are configured for different soiled clothing materials or fabric structures. The daughter release kinetic parameters include at least the adsorption coefficient and the desorption rate constant. Based on the daughter nuclide release kinetic parameters, the time-varying activity of the daughter nuclide is mapped to the daughter nuclide escape flux, and the upper bound of the daughter nuclide escape dose rate within a preset observation window is calculated based on the daughter nuclide escape flux. When the safety margin between the upper limit of the sub-external escape dose rate and the decontrol threshold does not meet the preset conditions, it is determined that there is a risk of delayed dose rebound.

[0034] In some examples, it also includes: If it is determined that there is a risk of delayed dose rebound, the washable instruction when the control threshold is met is replaced with a delayed wash prompt, and an observation delay window associated with the soiled clothing is generated. Within the observation delay window, at least one supplementary measurement time point is determined based on the upper bound of the sub-external escape dose rate, and a supplementary dose measurement of the soiled clothing is triggered when the supplementary measurement time point is reached. When the dose retest result meets the consistency constraint with the upper bound of the sub-external escape dose rate and the dose retest result is lower than the control threshold, a washable instruction is pushed to the medical terminal; otherwise, the observation delay window is updated and the retest time point is re-determined.

[0035] It is understandable that when radioactive contaminated clothing contains a decay chain consisting of a parent nuclide and daughter nuclides, the temporal evolution of the measurable external dose rate may not necessarily coincide with the exponential decay of the parent nuclide. It is possible that the dose contribution of the parent nuclide may have decreased to near or below the de-escalation threshold, while the daughter nuclide, due to its continued generation, accumulation, and escape over a subsequent period, causes a localized increase or a significant slowdown in the external dose rate. The reasons for this phenomenon include the continuous generation of daughter nuclides from parent decay, the daughter nuclides having their own half-life and potentially experiencing an initial increase followed by a decrease in activity over a certain period, and the adsorption and desorption processes of the clothing material on the nuclide or its decay products, resulting in a time lag in the escape process of the daughter nuclides from the fiber interior to the external space. To address this, the time-varying activity calculation of chain decay can be incorporated into the prediction framework. The time-varying activities of the parent and daughter nuclides can be obtained using the Bateman equations or equivalent numerical solutions. The daughter activity is then mapped to the daughter dose contribution and superimposed into the total dose prediction. Simultaneously, material release kinetic parameters are introduced to further map the daughter activity to the escape flux, and the upper bound of the escape dose rate within and outside the observation window is calculated. The risk of delayed rebound is determined by comparing this with the safety margin of the de-control threshold. When a risk exists, the system does not directly allow release but generates an observation delay window and triggers a supplementary measurement at the point of maximum information. The consistency between the supplementary measurement result and the prediction upper bound determines whether to release or extend the observation period, thus avoiding the risk of delayed rebound caused by premature de-control without relying on excessively conservative waiting. For a decay chain consisting of a parent nuclide and a daughter nuclide, the activity of the daughter nuclide does not decay independently exponentially but is jointly determined by the parent decay generation and its own decay consumption. The Bateman equations provide an analytical or numerical calculation framework for this chain process, allowing the system to obtain the time-varying curves of the parent and daughter activities at any given time. Even if the current parent dose contribution is already low, the system can still predict whether the daughter nuclide activity will reach a high level within the observation window in the future, thus creating a delayed dose rebound risk. At the management level, the system focuses on whether the dose or dose rate is below a threshold. Therefore, it is necessary to convert the time-varying activity of the daughter nuclide into its time-varying dose contribution. This conversion typically depends on the nuclide-specific dose conversion factor, measurement geometry, and detector response characteristics. The dose contribution of the daughter nuclide must be calculated separately; the conversion relationship of the parent nuclide cannot be simply applied to the daughter nuclide. The actual danger of delayed dose rebound does not depend on the activity within the fiber itself, but on the extent to which the daughter nuclide is released from the fiber or fabric structure and contributes to the measurable environmental dose rate. By using the adsorption coefficient and desorption rate constant, a model is essentially established to represent the transfer of the daughter nuclide from the material's interior to the external space. This model can map the daughter nuclide activity to an outflow flux, and then use the outflow flux to calculate the upper bound of the external dose rate within the observation window. Using an upper bound instead of a single-value prediction is intended to cover measurement errors, material differences, and environmental disturbances, thus making the decision more robust. Then, comparing this upper bound with the control threshold provides a safety margin to determine if there is a risk of delayed dose rebound.When there is a risk of delayed rebound, it is not advisable to issue a washable command directly; instead, an observation delay window should be entered. The significance of the observation delay window is that the egress dose rate of the offspring may peak or rebound within a certain period of time. The system obtains real data at key time points through supplementary testing, thereby verifying whether the upper bound of the prediction is too conservative or if there is indeed a risk. If the supplementary test result is lower than the threshold and consistent with the upper bound prediction, it can be released; otherwise, the observation period is extended and the supplementary test time point is re-determined.

[0036] For example, when a soiled garment is registered as having multi-nucleoside contamination or suspected multi-nucleoside contamination, the system first reads the nuclide list information associated with the soiled garment. This nuclide list can come from the declared nuclides at the time of registration, the results of energy spectrum rapid scan identification, or the presumed nuclide set from historical records of similar treatments. The system maintains a decay chain relationship table in the nuclide-specific decay model library. The relationship table records the correspondence between the parent nuclide and its possible daughter nuclides, the chain transformation type, and the half-life parameter index of each chain node. The system searches the nuclide list item by item. If a parent nuclide entry is matched in the decay chain relationship table, the parent nuclide is added to the candidate parent set, and its corresponding daughter nuclide entry is added to the candidate daughter set. When a daughter nuclide entry already appears in the nuclide list, the system increases the decay chain identification confidence and marks the daughter nuclide as an observed daughter. When no daughter nuclide entry appears in the nuclide list, the system still retains the daughter nuclide as a potential daughter, because the daughter may only explicitly contribute to the external dose rate later. To avoid false triggering, the system can set an identification threshold, such as the initial dose contribution of the parent nuclide being higher than the preset minimum contribution threshold, or the parent nuclide being a common decay chain source nuclide in this type of scenario before proceeding to the subsequent calculation; after identification is completed, the decay chain identification result, parent nuclide list, daughter nuclide list and identification confidence level can be output and written into the calculation task configuration of the contaminated clothing.

[0037] For example, after identifying the parent and daughter nuclides, the system uses the timestamp of soiled clothing generation as the zero point to establish a time-varying model input and obtains the initial activity or initial dose contribution of the parent nuclide. If only the initial dose index is collected on-site and the activity is not directly obtained, the system uses a nuclide-specific conversion relationship to back-calculate the initial dose contribution into an equivalent initial activity. The conversion relationship is determined by the equipment type, measurement geometry, and nuclide dose conversion coefficient, and is saved in the background as a parameter version for traceability. The system then determines the parent decay constant based on the parent nuclide's half-life parameter and the daughter decay constant based on the daughter nuclide's half-life parameter. A generation and decay model of daughter activity over time is established using the Bateman equations, where the generation term of daughter activity is determined by the parent decay rate, and the consumption term is determined by the daughter's own decay. When multiple daughter chains exist, the system prioritizes explicit modeling of chain nodes that significantly contribute to external dose. For chain nodes with smaller contributions or extremely short half-lives that are unlikely to pose external risks, a merging or truncation strategy is employed, and the truncation criteria are recorded. The system discretely samples the activity curve within a preset observation window. The length of the observation window can be determined based on the order of magnitude of the parent and daughter half-lives, the constraints of the system's own design on the frequency of retests, and safety margin requirements; for example, it should at least cover the time period during which the daughter may experience a peak or plateau. The system can output the parent and daughter activity sequences, and simultaneously output candidate intervals for the peak daughter activity time, serving as the basis for selecting subsequent retest time points.

[0038] For example, after obtaining the parent and daughter nuclides' activity sequences, the system calls the dose conversion parameters from the nuclide-specific decay model library to map the activity sequence of each nuclide to its dose contribution sequence under the current management scenario. The mapping process can be completed using nuclide dose conversion coefficients combined with measurement geometric correction parameters. These parameters characterize the influence of the distance and orientation between the detector and the protective clothing, as well as the clothing's folding shape, on the readings and can be obtained through pre-calibration. For daughter nuclides, the system uses daughter-specific conversion parameters instead of reusing parent parameters to avoid systematic errors caused by differences in energy spectrum or radiation type. Subsequently, at each sampling time within the observation window, the system sums the parent dose contribution, daughter dose contribution, and dose contributions of other nuclides on the contaminated clothing to obtain a total dose prediction curve including decay chain effects. To support subsequent risk assessment, the system can also calculate the maximum value of the total dose prediction curve within the observation window, the prediction time when it first falls below the de-control threshold, and the rate of change index near the threshold, thereby identifying whether the total dose exhibits morphological characteristics of a rebound, plateau, or significantly slowed decline. It can output the total dose prediction curve and the set of key time points, and use them as input for the assessment of delayed rebound risk.

[0039] For example, considering that the external measurable dose rate is often more affected by the escape behavior of daughter nuclides, the system further introduces a material release kinetic model based on the daughter nuclide activity sequence, mapping the daughter nuclide activity generated inside the fiber to the daughter nuclide escape flux released into the external space. The system first reads the material identifier or fabric structure identifier of the soiled garment. The material identifier can be retrieved from the garment asset management information or selected by on-site registration. The system retrieves the adsorption coefficient and desorption rate constant corresponding to the material from the material parameter table. The adsorption coefficient is used to characterize the degree to which daughter nuclides are bound inside or on the surface of the fiber, and the desorption rate constant is used to characterize the rate at which daughter nuclides transform from a bound state to an escapeable state. Subsequently, based on these kinetic parameters, the system converts the daughter nuclide activity sequence into an escape flux sequence, and combines measurement geometry and environmental correction parameters to convert the escape flux sequence into an external dose rate sequence within the observation window. To ensure robust decision-making, the system does not directly use single-value predictions. Instead, it introduces conservative margins for kinetic parameters and measurement errors. For example, it uses a higher value for the desorption rate constant to cover rapid release conditions and a lower value for the adsorption coefficient to cover weak binding conditions, thereby calculating the upper limit curve of the escape dose rate. The system defines the difference between this upper limit curve and the decontrol threshold as the safety margin and determines whether there are moments of insufficient safety margin within the observation window. If so, it determines that the delayed rebound risk is established and enters the observation delay strategy; otherwise, it allows the push of a washable command according to the normal decontrol procedure. It can output the upper limit curve of the escape dose rate, the minimum safety margin value, and the risk assessment result, and record the parameter values ​​and version numbers used to generate the upper limit.

[0040] For example, when the system determines that a delayed rebound risk is established, it does not directly issue a washable instruction. Instead, it generates an observation delay window for the soiled garment and displays a summary of the delayed wash and its reasons on the terminal, such as indicating the risk of delayed contribution from offspring and suggesting the next retest time. The starting point of the observation delay window can be set to the current time, and the ending point should at least cover the critical interval where the upper bound curve of the escape dose rate may be close to the peak or close to the threshold. The selection of the retest time point aims to maximize information gain. The system prioritizes selecting retest time points near the inflection point where the slope of the upper bound curve changes, near the local maximum of the upper bound curve, or near the minimum safety margin between the upper bound curve and the threshold, in order to reduce the number of retests while improving the ability to identify risks. Upon reaching the supplementary testing point, the system triggers a dose supplementation task and records the results. These results can be uploaded from on-site detection equipment or entered via a handheld terminal. The system compares the supplementary testing results with the release threshold and simultaneously evaluates the consistency constraints between the supplementary testing results and the upper bound curve of the escaped dose rate. These consistency constraints stipulate that the supplementary testing value should not significantly exceed the upper bound, and the difference between the supplementary testing value and the upper bound should fall within the allowable error range. This prevents the model from significantly underestimating the value, leading to erroneous release, or from being overly conservative, causing unnecessary delays. When the supplementary testing value is below the release threshold and meets the consistency constraints, the system updates the status from observation delay to washable and pushes a washable command. When the supplementary testing value is above the threshold or does not meet the consistency constraints, the system extends the observation delay window or recalculates the upper bound curve, and accordingly reselects the supplementary testing point until the release conditions are met or a higher-level treatment process is initiated. The system then outputs the final release decision, the supplementary testing record link, and an auditable event log.

[0041] In some cases, considering the potential for underreporting, misreporting, or overgeneralization of contaminated clothing nuclide information during registration, the system may call incorrect half-life and dose conversion parameters, leading to a systematic discrepancy between the real-time dose calculation and the remaining decay time indication. This discrepancy is particularly severe when short- and long-lived nuclides are confused, potentially resulting in premature release or excessively conservative waiting. Energy spectrum data contains nuclide characteristic information; the main peak energy channel position, peak width, and Compton scattering step morphology formed by different nuclides on the detector are distinguishable. Even with short acquisition times, by selecting energy spectrum features with high nuclide distinguishability and using similarity matching, a candidate nuclide set can be provided under low statistical conditions. Based on this, in some examples, before performing real-time calculation of the current dose based on the nuclide half-life parameter, the method further includes: collecting the energy spectrum data of the soiled clothing and extracting the energy spectrum fingerprint features of the main peak energy channel, peak width, and Compton step slope; performing similarity matching between the energy spectrum fingerprint features and a preset nuclide fingerprint database to obtain a candidate nuclide set; performing a consistency comparison between the candidate nuclide set and a preset declared nuclide set; and when the consistency comparison does not meet the preset conditions, switching to the half-life parameter and dose superposition model corresponding to the candidate nuclide set to perform the real-time calculation and outputting a manual review prompt.

[0042] Understandably, short-time energy spectrum fingerprints can be used to verify the consistency of declared nuclides before decay tracking calculations. When the consistency is insufficient, the system automatically switches to the nuclide parameter group obtained by energy spectrum inference and triggers a review prompt, thereby improving the reliability of nuclide identification and reducing prediction bias without increasing a large amount of manual workload.

[0043] For example, when the system is triggered for registration or retesting of soiled linen, it acquires short-term energy spectrum data through the energy spectrum acquisition module. The duration of energy spectrum acquisition can be set from several seconds to tens of seconds depending on the scenario. During acquisition, the distance and measurement orientation between the probe and the linen are fixed to reduce the impact of geometric changes on the energy spectrum morphology. The system performs basic preprocessing on the energy spectrum, including background subtraction, channel smoothing, and abnormal pulse removal, and uses the processed energy spectrum as the fingerprint extraction input. The system extracts energy spectrum fingerprint features from the processed energy spectrum. The fingerprint features include at least the position of the main peak channel, the estimated half-width at half-maximum or peak width of the main peak, the peak count ratio, and the slope or area ratio of the Compton step interval. If the main peak is not obvious due to short-term acquisition, the system uses the count ratios of multiple energy regions to construct a fingerprint vector and records the confidence index of the fingerprint. The confidence index can be determined by a combination of total count, signal-to-noise ratio, and peak significance. The system searches for similar nuclides in the nuclide fingerprint database. The database stores a reference fingerprint and allowable drift range for each nuclide, covering channel shifts caused by different detectors, geometries, and shielding conditions. The system calculates the similarity between the current fingerprint and the reference fingerprint in the database, outputting the highest similarity nuclides as a candidate set. Simultaneously, it generates a confidence level for the candidate set based on a confidence index and the similarity difference. The system performs a consistency comparison between the candidate set and the declared nuclide set during registration. This consistency comparison can use a combination of set intersection / union relations and a similarity threshold criterion. For example, if the declared nuclide is not in the candidate set and the highest similarity of the candidate set exceeds a preset threshold, an inconsistency is determined. Once an inconsistency is determined, the system switches to using the half-life parameters and dose conversion parameters corresponding to the candidate nuclide set to perform decay tracking calculations. A manual review prompt is output to the terminal, including at least the declared nuclide, candidate nuclides, similarity level, and a suggested retest or review action. The switching event is also written to the audit log for traceability. To mitigate the risk of erroneous switching, the system can be configured with a rollback mechanism. For example, if a subsequent energy spectrum fingerprint differs significantly from the initial energy spectrum fingerprint, the system can reassess the candidate nuclide set. When the consistency check recovery conditions are met, the system can resume using the declared nuclide parameters or adopt a conservative combination of both, clearly recording the timestamps and basis for parameter changes. This reduces the bias in remaining decay time indications caused by nuclide misidentification. Because remaining decay time is highly dependent on the half-life parameter, mistaking a long half-life for a short half-life leads to overly optimistic predictions, while mistaking a short half-life for a long half-life leads to unnecessary prolonged storage. By correcting errors before calculation through energy spectrum self-checking, bias is suppressed at its source.

[0044] In some cases, considering that the external measurable dose rate of the same soiled garment can be affected by factors such as background radiation levels, scattering from the enclosure structure, shield geometry, and proximity to pollution sources under different storage locations or operating conditions, the fixed release threshold may be too strict in some locations and too lenient in others. An overly strict fixed threshold can cause unnecessary delays for compliant items, while an overly lenient threshold can allow unsafe items to be released prematurely. Therefore, in some examples, comparing the real-time calculated current dose with the preset release threshold includes: acquiring background energy spectrum data, enclosure structure material information, and shield geometry information corresponding to the storage location of the soiled garment; determining a threshold correction amount based on the background energy spectrum data, enclosure structure material information, and shield geometry information, and updating the preset release threshold to a location-adaptive release threshold; comparing the current dose with the location-adaptive release threshold to generate the washable instruction or the remaining decay time indication.

[0045] Understandably, the threshold can be extended from a constant to a judgment interface related to location and operating conditions. Measurability can be estimated using background energy spectrum and geometric information, and the minimum separability threshold under a fixed confidence level can be used as the basis for threshold correction, thereby ensuring consistent judgment risk across different locations. The core principle is not arbitrarily adjusting the threshold, but rather deriving the threshold correction amount using observable background energy spectrum and structural parameters, making threshold migration interpretable and traceable.

[0046] For example, the system establishes a location tagging system for key locations such as the temporary storage area, the area to be washed, and the pre-wash buffer zone. Each location tag is associated with information on the building envelope material, its relative geometric relationship with the shield, and a typical background energy spectrum template. When soiled clothing enters a location, the system obtains the current location tag through access control card reading, handheld terminal scanning, or positioning base station identification, and performs background energy spectrum acquisition at that location. Background acquisition is performed under the condition that no clothing under test is near the probe, and the duration is set according to statistical stability. The background energy spectrum is used as a threshold calibration input. The system calculates the background level and statistical fluctuation parameters based on the background energy spectrum. The statistical fluctuation parameters are used to reflect the natural fluctuation range of the reading at that location. The system simultaneously reads the building envelope material and geometric information. The material information is used to estimate the scattering ratio, and the geometric information is used to estimate the shielding and reflection contributions. Based on this, the system uses a threshold correction model to calculate the threshold correction amount. The threshold correction model can be a regression model trained based on historical calibration data, or an analytical estimation model established based on background fluctuation and scattering estimation. The system outputs the correction amount along with a confidence level. The system combines the basic release threshold with the threshold correction amount to generate a location-adaptive release threshold, and performs a comparison between the current dose and the threshold under this location-adaptive threshold. When the soiled clothing moves between multiple locations, the system recalculates the location-adaptive threshold based on the new location label and synchronously updates the remaining decay time indication to ensure consistency between the indication and the execution site. To prevent excessive threshold drift, the system sets boundary constraints on the correction amount, such as the correction amount not exceeding a certain proportion of the basic threshold, and adopts a more conservative correction direction when the confidence level is insufficient. The system writes the background energy spectrum, location label, and correction results used for each calibration to a log to ensure auditability and allows the management end to manually review and recalibrate abnormal locations.

[0047] In some cases, even if the average dose level of soiled clothing decreases with decay, actions such as handling, shaking, folding, or bagging during actual operation may cause particle resuspension or contaminant redistribution, resulting in a transient increase in the local external dose rate within a short period of time. Personnel handling these items at close range may experience short-term peak exposure. Traditional management often only focuses on whether the current dose is below the control threshold, without incorporating the transient increase caused by the operation into the risk assessment. Based on this, some examples also include: after outputting the remaining decay time prompt, the following steps are also included: determining the type and duration of the operation on the soiled clothing, wherein the operation type includes at least handling, folding, shaking, and bagging; calculating the upper limit of the resuspension dose increment based on the operation type, the duration of the operation, and the risk parameter of particle resuspension on the soiled clothing surface; when the upper limit of the resuspension dose increment causes the predicted instantaneous dose to exceed a preset safety threshold, outputting an operation sequence constraint prompt to the medical terminal, wherein the operation sequence constraint prompt includes at least a resting waiting time, a dust suppression instruction, and a minimum interval time between actions.

[0048] Understandably, risk assessment can be extended from static to operational process assessment. A mapping model between action categories and resuspension risk parameters can be established to calculate the upper bound of the potential resuspension dose increment under a given action duration and intensity. Based on this, operational sequence constraints can be generated, such as first allowing the system to stand, then suppressing dust, and then performing low-disturbance handling. Minimum intervals between actions can be set to reduce the probability of transient peak exposure and secondary contamination spread. The action sequence can be used as an adjustable control variable, rather than simply a delay in processing time.

[0049] For example, the system defines an operation action library for soiled linen management. The action library includes action categories such as handling, folding, shaking, bagging, and trolley transfer, and configures risk parameters for each action category. The risk parameters include at least the resuspension tendency coefficient, the geometric coefficient of close-range exposure, and the sensitivity coefficient related to the particle load on the linen surface. The particle load can be estimated statistically from historical similar scenarios, inferred from surface contamination detection results, or estimated from linen disposal records. When the system calculates that the current dose is still higher than the de-escalation threshold and outputs a remaining decay time prompt, it simultaneously triggers the operation risk assessment module. The operation risk assessment module receives information on the planned action category and duration, which can be preset by the standard operating procedure or selected by the terminal when preparing to handle the linen. The system combines the current dose level, particle load estimation, and action risk parameters to calculate the upper limit of the resuspension dose increment and further extrapolates the upper limit of the instantaneous dose peak that personnel may suffer during the action execution. The system compares the upper limit of the instantaneous dose peak with a preset safety threshold. If the peak is expected to exceed the safety threshold, an operation sequence constraint prompt is generated and pushed to the terminal. The operation sequence constraint prompt includes at least the waiting time, dust suppression instructions, and minimum interval between actions. The waiting time is used to reduce the mobility of loose particles, dust suppression can be achieved through atomized spraying or pre-sealing with covered bags, and the minimum interval between actions is used to avoid resuspension accumulation due to continuous disturbance. When the peak is expected to not exceed the safety threshold, the system can still output low-disturbance suggestions, such as suggesting a smooth handling path, reducing the number of folds, and prioritizing bagging before transfer. The execution results are recorded in the log to assess whether risk parameters need adjustment. If an abnormal rise in measurement occurs after on-site execution, the system can associate the abnormal record with the action category to update risk parameters and optimize subsequent prompts.

[0050] Please see Figure 2 One embodiment of the intelligent management device for radioactive contaminated clothing in this application includes: The acquisition unit 21 is used to acquire the initial radiation dose and the time of generation of the soiled clothing; The calculation unit 22 is used to construct a decay tracking calculation process based on the nuclide decay formula, calculate the current dose in real time according to the nuclide half-life parameter, and superimpose the contributions of each nuclide to obtain the total dose when there is multi-nuclide contamination. The prompting unit 23 is used to compare the current dose calculated in real time with the preset de-control threshold, push a washable instruction to the medical terminal when the de-control threshold is met, and output the remaining decay time prompt when the de-control threshold is not met.

[0051] like Figure 3 As shown, this application embodiment also provides an electronic device 300, including a memory 310, a processor 320, and a computer program 311 stored in the memory 310 and executable on the processor. When the processor 320 executes the computer program 311, it implements the steps of any of the above-mentioned methods of the intelligent management of radioactive contaminated clothing.

[0052] Since the electronic device described in this embodiment is the device used to implement the intelligent management device for radioactive contaminated clothing in the embodiments of this application, those skilled in the art can understand the specific implementation method and various variations of the electronic device in this embodiment based on the method described in the embodiments of this application. Therefore, how the electronic device implements the method in the embodiments of this application will not be described in detail here. Any device used by those skilled in the art to implement the method in the embodiments of this application falls within the scope of protection of this application.

[0053] In practical implementation, when the computer program 311 is executed by the processor, it can achieve the following: Figure 1 Any of the corresponding implementation methods in the embodiments.

Claims

1. A method for intelligent management of radioactive contaminated clothing, characterized in that, include: The initial radiation dose and time of occurrence of the soiled clothing were collected; A decay tracking calculation process is constructed based on the nuclide decay formula. The current dose is calculated in real time based on the nuclide half-life parameter. When there is multi-nuclide contamination, the contributions of each nuclide are superimposed to obtain the total dose. The current dose calculated in real time is compared with the preset de-control threshold. If the de-control threshold is met, a washable command is pushed to the medical terminal. If the de-control threshold is not met, the remaining decay time is output as a prompt.

2. The method as described in claim 1, characterized in that, Also includes: The soiled bedding is uniquely identified by RFID tags or barcodes. Based on the unique identity binding result, the soiled clothing category information is automatically associated, and consistency verification is performed on the registered soiled clothing type and quantity. When the consistency check fails to meet the preset rules, an abnormal warning message is output.

3. The method as described in claim 1, characterized in that, The method of summing the contributions of each nuclide to obtain the total dose in the presence of multi-nucleoside contamination includes: Retrieve the half-life and decay parameters corresponding to the contaminated nuclides in the soiled clothing from the nuclide-specific decay model library; When multiple nuclides are present, the dominant nuclide is determined based on the initial dose ratio or dose contribution of each nuclide over time, and the remaining decay time indication is dynamically corrected based on the dominant nuclide.

4. The method as described in claim 1, characterized in that, Also includes: When the control release threshold is met, a washable instruction is pushed to the medical terminal, and a washable status marker is generated for the soiled clothing and the control release timestamp is recorded. The inventory and location status of soiled linens are updated based on the washable status markers, and a retention warning is generated for soiled linens that have not been washed within the specified period. Generate a statistical report containing at least one piece of information: the number of items released from control, the number of items to be sent for washing, and the number of items that have not been sent for washing within the specified time.

5. The method as described in claim 1, characterized in that, The method of summing the contributions of each nuclide to obtain the total dose in the presence of multi-nucleoside contamination includes: Identify whether a decay chain consisting of a parent nuclide and its daughter nuclide exists in the multi-nucleoside contamination; When the decay chain is identified, a time-varying activity calculation model for the parent nuclide and the daughter nuclide is established based on the Bateman equations, and the time-varying activity corresponding to the daughter nuclide is converted into the time-varying dose contribution of the daughter nuclide. The total dose is obtained by superimposing the time-varying dose contribution of the daughter nuclide with the dose contributions of the parent nuclide and other nuclides.

6. The method as described in claim 5, characterized in that, Also includes: When the time-varying activity is converted into the time-varying dose contribution of the daughter nuclide, daughter release kinetic parameters are configured for different soiled clothing materials or fabric structures. The daughter release kinetic parameters include at least the adsorption coefficient and the desorption rate constant. Based on the daughter nuclide release kinetic parameters, the time-varying activity of the daughter nuclide is mapped to the daughter nuclide escape flux, and the upper bound of the daughter nuclide escape dose rate within a preset observation window is calculated based on the daughter nuclide escape flux. When the safety margin between the upper limit of the sub-external escape dose rate and the decontrol threshold does not meet the preset conditions, it is determined that there is a risk of delayed dose rebound.

7. The method as described in claim 6, characterized in that, Also includes: If it is determined that there is a risk of delayed dose rebound, the washable instruction when the control threshold is met is replaced with a delayed wash prompt, and an observation delay window associated with the soiled clothing is generated. Within the observation delay window, at least one supplementary measurement time point is determined based on the upper bound of the sub-external escape dose rate, and a supplementary dose measurement of the soiled clothing is triggered when the supplementary measurement time point is reached. When the dose retest result meets the consistency constraint with the upper bound of the sub-external escape dose rate and the dose retest result is lower than the control threshold, a washable instruction is pushed to the medical terminal; otherwise, the observation delay window is updated and the retest time point is re-determined.

8. A smart management device for radioactive contaminated clothing, characterized in that, include: The acquisition unit is used to acquire the initial radiation dose and the time of generation of the soiled clothing; The calculation unit is used to construct a decay tracking calculation process based on the nuclide decay formula, calculate the current dose in real time according to the nuclide half-life parameter, and sum the contributions of each nuclide to obtain the total dose when there is multi-nuclide contamination. The prompting unit is used to compare the current dose calculated in real time with the preset de-control threshold. When the de-control threshold is met, a washable instruction is pushed to the medical terminal. When the de-control threshold is not met, the remaining decay time is output as a prompt.

9. An electronic device, comprising: A memory, a processor, and a computer program stored in the memory and executable on the processor, characterized in that the processor, when executing the computer program stored in the memory, implements the steps of the intelligent management method for radioactive contaminated clothing as described in any one of claims 1-7.

10. A computer-readable storage medium having a computer program stored thereon, characterized in that: When the computer program is executed by the processor, it implements the intelligent management method for radioactive contaminated clothing as described in any one of claims 1-7.

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