A radioactive drug dosage control system for pre-injection analysis in imaging

Abstract

The present invention relates to a radioactive drug dosage control system, belonging to the technical field of radioactive drug measurement. The system includes: an activity measurement unit for measuring the current radioactivity of the drug in the target medicine storage bottle; an input unit for obtaining relevant basic information of the current patient receiving the drug, wherein the relevant basic information includes the patient's weight information and height information; and an analysis unit for determining the volume of the drug required for the current injection extraction for the patient according to the radioactivity of the drug in the current medicine storage bottle and the relevant basic information of the current patient receiving the drug. The present invention not only improves the accuracy of drug dose calculation, but also significantly enhances the operation efficiency and user experience of the system. Through accurate activity measurement and accurate input of patient information, the system can quickly generate personalized dosage plans, reduce the errors of manual operations, and improve the safety and effectiveness of use.

Description

Technical Field

[0001] The present invention relates to the technical field of radioactive drug measurement, and in particular to a radioactive drug dosage control system. Background Art

[0002] Radioactive drugs are a class of drugs containing radioactive isotopes and are widely used in medical diagnosis. These drugs provide medical imaging effects by releasing radioactive particles (such as γ-rays, β-particles, etc.). Common radioactive drugs include 18F-FDG, 99mTc, 131I, and 68Ga, etc. 18F-FDG is the most commonly used positron emission tomography (PET) tracer, mainly used for the diagnosis of oncology, neurology, and cardiology. 99mTc is widely used in single photon emission computed tomography (SPECT) imaging and is applicable to a variety of nuclear medicine examinations.

[0003] The accuracy of the total activity dose D that a patient should receive determined simply by using a data lookup table or numerical calculation is not very high. This is because the above single methods rely more on clinical experience data and do not make corrections based on the individual conditions of the patient, resulting in a mismatch between the total activity dose actually received by the patient and the total activity dose that the patient needs to receive. This situation may lead to problems such as poor imaging effects during PET-CT, as recorded in the following paper: Botkin C D, Osman M M. Prevalence, challenges, and solutions for (18)F-FDG PET studies of obese patients: a technologist's perspective. [J]. Journal of Nuclear Medicine Technology, 2007, 35(2):80. However, if the obtained total activity dose D is simply corrected, it is difficult to determine whether the corrected value is reasonable.

[0004] In addition, on the one hand, there are differences in the understanding of those skilled in the art; on the other hand, although the applicant has studied a large number of literatures and patents when making the present invention, due to space limitations, not all details and contents are listed in detail. However, this does not mean that the present invention does not possess the features of these prior arts. On the contrary, the present invention already possesses all the features of the prior arts, and the applicant reserves the right to add relevant prior arts in the background art. Summary of the Invention

[0005] In view of the deficiencies of the prior art, the present invention provides a radioactive drug dosage control system to solve at least some of the above technical problems.

[0006] The present invention discloses a radioactive drug dosage control system, which comprises: an activity measurement unit for measuring the current radioactive activity of the drug in the target medicine storage bottle; an input unit for obtaining relevant basic information of the current patient receiving the medicine, wherein the relevant basic information includes the patient's weight information and height information; and an analysis unit for determining the volume of the drug required to be drawn for the current injection for the patient according to the radioactive activity of the drug in the current storage bottle and the relevant basic information of the current patient receiving the medicine.

[0007] In the field of nuclear medicine, traditional radioactive drug dosage calculations often rely on manual operations. This mode is not only inefficient and error-prone, but also lacks the ability to systematically store and subsequently analyze data, making it difficult to meet the high standards of accuracy and safety required by modern medicine. However, the radioactive drug dosage control system of the present invention realizes the full-process automated management from drug activity measurement to patient information acquisition and then to dosage calculation by integrating an activity measurement unit, an input unit, and an analysis unit. The system can not only accurately measure the current activity of the radioactive drug in the storage bottle in real time and automatically calculate the personalized injection volume according to the patient's weight, height, and other physiological parameters, ensuring the accuracy of each administered dose; at the same time, all data during the operation process are digitally recorded, facilitating future query and analysis, thus providing detailed historical medication record support for medical staff. This design not only improves the accuracy of drug dosage calculation, but also significantly enhances the operation efficiency and user experience of the system. Through accurate activity measurement and accurate entry of patient information, the system can quickly generate personalized dosage plans, reducing manual operation errors, reducing repeated withdrawals, reducing the time for medical staff to frequently contact radioactive drugs, and improving the safety and effectiveness of diagnosis. In addition, the automated management function of the system can also reduce the workload of medical staff, improve the utilization efficiency of medical resources, contribute to optimizing the medical process, and enhancing the overall level of medical services.

[0008] According to a preferred embodiment, the activity measurement unit arranges corresponding detectors at dedicated measurement sites near the corresponding medicine storage bottles in the medicine storage bottle storage area, and the original signals collected by the detectors are sent to the processor of the activity measurement unit after conversion, so as to calculate the radioactive activity of the drug through signal processing.

[0009] By arranging detectors at dedicated measurement sites within the drug storage bottle storage area, the present invention can significantly improve the accuracy and stability of activity measurement. This design not only reduces interference and loss in the signal transmission path but also ensures that each sample to be measured is correctly placed in front of the detector, avoiding measurement errors caused by improper positioning. The design of dedicated measurement sites also enables multi-point synchronous measurement, further improving the consistency and reliability of measurement results. In addition, this high-precision measurement method can also provide more reliable data support for subsequent dose calculations, contributing to the realization of more refined and personalized diagnostic plans and enhancing the diagnostic effect and quality of life of patients.

[0010] According to a preferred embodiment, the processor of the activity measurement unit integrates the corrected signal using the gradient method to obtain the total energy or total count of the signal, and then calculates the radioactive activity of the drug based on the integration result and physical parameters, where the physical parameters include detector efficiency and / or calibration factor.

[0011] By integrating the corrected signal using the gradient method and combining physical parameters such as detector efficiency and calibration factor, the present invention can significantly improve the accuracy and stability of activity calculation. The gradient method can effectively eliminate noise and interference in the signal, improve the signal-to-noise ratio of the signal, thus ensuring high-precision activity measurement. The introduction of detector efficiency and calibration factor further corrects the measurement result, eliminates systematic errors, and ensures the reliability of activity calculation. This high-precision activity measurement method not only provides more reliable data support for dose calculation but also helps to realize real-time monitoring and dynamic adjustment of drug activity, improving the intelligent level of the system.

[0012] According to a preferred embodiment, the data processed by the processor of the activity measurement unit can be displayed to the user through a graphical interface, where the processor of the activity measurement unit can be communicatively connected to the medical staff terminal so that key parameters including the currently measured activity value and reference value range can be displayed on the interface of the medical staff terminal, and a historical data query function is provided.

[0013] Through the communication connection between the graphical interface and the medical staff terminal, the present invention not only provides an intuitive data display function but also realizes real-time data sharing and remote management. The graphical interface enables medical staff to intuitively view the current activity value and reference value range, timely understand the activity status of the drug, and improve the convenience and accuracy of operation. At the same time, the historical data query function provides detailed medication records and historical data, which helps medical staff with subsequent management and analysis and optimizes the diagnostic plan. In addition, the remote management function can also realize cross-regional data sharing and collaborative work, improve the utilization efficiency of medical resources, contribute to promoting the construction of medical informatization, and enhance the overall level of medical services.

[0014] According to a preferred embodiment, the input unit can be configured with a digital input device. The input unit can verify the accuracy of the relevant basic information input through the input device by setting the numerical range of the corresponding parameters, so that the correct relevant basic information entered in the input unit can be transmitted to the analysis unit through a secure protocol.

[0015] By configuring a digital input device and setting the numerical range of the parameters, the present invention can significantly improve the accuracy and integrity of patient information entry. The digital input device provides a user-friendly operation interface, reduces manual input errors, and ensures data accuracy and consistency. The numerical range verification mechanism of the parameters can automatically detect and correct input data errors, avoiding dosage calculation errors caused by inaccurate data. In addition, the secure protocol transmission ensures the security and integrity of data during transmission, preventing the risk of data being tampered with or leaked. This high-precision data entry and transmission mechanism not only improves the reliability and security of the system, but also helps to achieve standardized and normalized management of data, promotes the construction of medical informatization, and improves the overall level of medical services.

[0016] According to a preferred embodiment, after receiving the current radioactivity of the drug in the current medicine storage bottle sent by the activity measurement unit and the relevant basic information of the current patient receiving the drug sent by the input unit, the analysis unit can determine the volume of the drug required for the current injection extraction by retrieving the built-in data lookup table summarized according to experience for different types of radioactive drugs, and / or can determine the volume of the drug required for the current injection extraction by numerical calculation based on the patient's specific physiological parameters and the specific activity of the drug.

[0017] By combining the data lookup table and numerical calculation, the present invention provides a flexible dosage calculation method, significantly improving the accuracy and personalization level of dosage calculation. The data lookup table is based on rich clinical experience and data accumulation, ensuring the accuracy and reliability of dosage calculation; the numerical calculation method can perform personalized dosage calculation according to the patient's specific physiological parameters and drug characteristics, improving the precision of dosage and diagnostic effect. In addition, this flexible dosage calculation method can also adapt to different types of radioactive drugs and different diagnostic needs, improving the adaptability and scalability of the system.

[0018] According to a preferred embodiment, when the analysis unit determines the volume of the drug required for the current injection extraction by numerical calculation, the patient-specific physiological parameters it selects include the body surface area calculated based on the patient's height information and weight information. Based on the obtained body surface area, the total activity dose that the patient should receive is calculated in combination with the recommended dose of the corresponding drug.

[0019] By calculating the patient's body surface area and combining it with the recommended dose of the drug, the present invention can provide a more personalized dose calculation method, significantly improving the accuracy of dose calculation and the diagnostic effect. The body surface area is an important physiological parameter that can more accurately reflect the patient's metabolic needs and drug distribution characteristics, thereby improving the personalized level of dose calculation. This body surface area-based dose calculation method not only helps to achieve a more scientific and personalized diagnostic plan, but also reduces the diagnostic failure caused by inaccurate doses, improving the safety and effectiveness of use.

[0020] According to a preferred embodiment, the system includes a volume measurement unit for measuring the current remaining volume of the drug in the medicine storage bottle. Among them, the volume measurement unit can arrange electrodes outside the corresponding medicine storage bottle, so that the analysis unit can calculate the drug volume required by the patient by using the remaining volume of the drug obtained by the volume measurement unit based on the capacitive volume measurement technology.

[0021] By arranging (ring-shaped) electrodes outside the medicine storage bottle and using the capacitive volume measurement technology, the present invention can achieve non-contact volume measurement, significantly improving the accuracy and stability of the measurement. The design of the ring-shaped electrodes ensures the uniform distribution of the measurement signal, avoiding measurement errors caused by improper positions. This non-contact measurement method not only avoids drug contamination and the risk of radiation exposure to operators, but also enables multi-point synchronous measurement, further improving the consistency and reliability of the measurement results. In addition, this high-precision volume measurement method can also provide more reliable data support for dose calculation, helping to achieve a more refined and personalized diagnostic plan, and improving the patient's diagnostic effect and quality of life.

[0022] According to a preferred embodiment, the system includes a timing unit for starting timing when the analysis unit obtains the calculation result. The timing unit can set different interval durations for different types and different states of drugs. Among them, when the drug measurement is not completed after exceeding the set interval duration, it is determined that this drug measurement operation is invalid, and the timing unit sends an invalid signal to the analysis unit so that the analysis unit recalculates according to the current situation.

[0023] By monitoring the time intervals of drug measurement in real time and setting different interval durations, the present invention can significantly improve the accuracy of drug dosage and the diagnostic effect. By setting different interval durations for different types and states of drugs, it can better adapt to the activity change characteristics of different drugs, improving the accuracy of dosage and the diagnostic effect. When the set interval duration is exceeded, the system can issue an alarm in time and recalculate the dosage, avoiding diagnostic failures caused by too low activity and improving the reliability and safety of the system. In addition, this real-time monitoring and dynamic adjustment mechanism can also achieve full-process tracking and management of drug activity, improving the intelligence level of the system, helping to optimize the medical process, and enhancing the overall level of medical services.

[0024] According to a preferred embodiment, the timing unit can adjust the interval duration of each drug in real time based on parameters including the half-life of the drug, the current activity value, and the allowed maximum activity loss, wherein the allowed maximum activity loss can be calculated by the analysis unit according to a preset maximum error value when calculating the drug volume.

[0025] By adjusting the interval duration of each drug in real time based on parameters including the half-life of the drug, the current activity value, and the allowed maximum activity loss, the present invention can significantly improve the accuracy of drug dosage and the diagnostic effect. The introduction of the half-life and the current activity value makes the setting of the interval duration more scientific and reasonable, and can better adapt to the activity change characteristics of different drugs. The calculation method of the allowed maximum activity loss ensures the accuracy and reliability of dosage calculation and avoids diagnostic failures caused by too low activity. In addition, this dynamic adjustment timing mechanism can also achieve real-time monitoring and dynamic adjustment of drug activity, improving the intelligence level of the system. Brief Description of the Drawings

[0026] Figure 1 is a schematic diagram of the hardware connection of a radioactive drug dosage control system according to a preferred embodiment provided by the present invention;

[0027] Figure 2 is a schematic diagram of the data processing of the processor of the activity measurement unit according to a preferred embodiment provided by the present invention;

[0028] Figure 3 is a schematic diagram of the operation of the analysis unit according to a preferred embodiment provided by the present invention;

[0029] Figure 4 is a schematic diagram of the standard curve and safety interval according to a preferred embodiment provided by the present invention;

[0030] Figure 5 is a schematic diagram of the operation of the volume measurement unit according to a preferred embodiment provided by the present invention;

[0031] Figure 6It is a working schematic diagram of a timing unit according to a preferred embodiment provided by the present invention.

[0032] List of reference numerals

[0033] 100: Activity measurement unit; 110: Processor; 120: Detector; 200: Input unit; 210: Input device; 300: Analysis unit; 400: Medical staff side; 500: Medicine storage bottle; 600: Volume measurement unit; 610: Electrode; 700: Timing unit. Detailed implementation manners

[0034] The following will be described in detail with reference to the accompanying drawings.

[0035] As Figure 1 shown, the present invention discloses a radioactive drug dosage control system, which includes: an activity measurement unit 100 for measuring the current radioactivity of the drug in the target medicine storage bottle 500; an input unit 200 for obtaining relevant basic information of the current patient receiving the medicine; and an analysis unit 300 for determining the volume of the drug required for the current injection extraction for the patient according to the radioactivity of the drug in the current medicine storage bottle 500 and the relevant basic information of the current patient receiving the medicine. Preferably, the relevant basic information of the current patient receiving the medicine may include the patient's weight information and height information. Further preferably, the above-mentioned relevant basic information may also include the patient's age information. Preferably, the medicine storage bottle 500 of the present invention is usually a glass container and can be placed inside a lead can or a lead box to effectively shield the radiation released by radioactive substances and reduce the impact on the surrounding environment and personnel. Among them, the medicine storage bottle 500 may be, for example, a vial and an ampoule bottle.

[0036] Preferably, the activity measurement unit 100 relies on a high-precision radiation detector to complete the measurement of radioactive activity. According to different application scenarios and technical requirements, the activity measurement unit 100 can select different types of detectors 120, such as scintillation detectors and semiconductor detectors. Preferably, the scintillation detector utilizes the characteristic that a specific material (such as NaI(Tl) sodium iodide crystal) emits fluorescence after absorbing rays to achieve activity measurement. When the γ-rays released by radioactive substances pass through the crystal, it will excite the crystal to generate fluorescence, which is converted into an electrical signal by a photomultiplier tube and recorded after amplification. This method has high detection efficiency and good energy resolution, and is suitable for the measurement of various radionuclides. Preferably, semiconductor detectors, especially high-purity germanium (HPGe) detectors, are widely used in precise measurements due to their excellent energy resolution. The working principle of the HPGe detector is that at low temperature, when γ-rays enter the germanium crystal, electron-hole pairs are generated, and these carriers move under the action of an external electric field to form a current pulse. After amplification and processing, the energy information of the rays can be obtained. Compared with the scintillation detector, the HPGe detector can more accurately distinguish rays of different energies and is especially suitable for the precise measurement of low-activity samples.

[0037] Preferably, the electrical signal generated by the detector 120 can be converted into a digital signal by an analog-to-digital converter (ADC) and then transmitted to the processor 110 of the activity measurement unit 100 through a standard interface (such as USB, Ethernet, or a dedicated data bus). Further, in this process, the stability and speed of signal transmission should be ensured to achieve real-time monitoring.

[0038] Preferably, the activity measurement unit 100 can also be equipped with a refrigeration device and a stable power supply to ensure that the detector 120 maintains its optimal performance throughout the usage cycle, especially for HPGe detectors that require a low-temperature environment to operate properly.

[0039] Preferably, in order to obtain the most accurate measurement results, the detector 120 of the activity measurement unit 100 can be arranged at a dedicated measurement site set within the storage area of the medicine storage bottle 500. This dedicated measurement site is as close as possible to the corresponding medicine storage bottle 500 to ensure that each sample to be measured can be correctly placed in front of the detector 120. Further, in order to protect the operator from unnecessary radiation exposure, sufficient radiation shielding, such as lead plates or other heavy shielding materials, should be provided around the detector 120.

[0040] Preferably, the original signal collected by the detector 120 is sent to the processor 110 of the activity measurement unit 100 after conversion, and signal processing is performed through an algorithm built in the processor 110 of the activity measurement unit 100, including steps such as noise filtering and baseline correction, to calculate the radioactivity of the drug. The process steps of data processing by the processor 110 of the activity measurement unit 100 can be as Figure 2 shown.

[0041] Preferably, in the noise filtering step, the processor 110 of the activity measurement unit 100 can use a combination of low-pass filtering and median filtering to complementarily remove different types of noise and improve the signal quality. Among them, low-pass filtering can remove high-frequency noise such as electromagnetic interference. In radioactive activity detection, the cut-off frequency is set to filter out signals higher than this frequency to effectively remove electronic noise and environmental interference; median filtering can remove spike noise such as instantaneous interference caused by cosmic rays. Median filtering smooths the median of the signals within a certain window to effectively remove spike noise.

[0042] Preferably, in the baseline correction step, the processor 110 of the activity measurement unit 100 can correct baseline drift and baseline offset respectively. Among them, baseline drift refers to the slow change of the signal baseline due to factors such as temperature change and power supply fluctuation, and baseline offset refers to the overall upward or downward movement of the signal. Preferably, the processor 110 of the activity measurement unit 100 can use the method of polynomial fitting to correct baseline drift because in radioactive activity detection, it can more flexibly adapt to the change of the baseline, especially in the case of relatively complex baseline drift. Among them, the method of polynomial fitting uses a low-order polynomial (such as a first-order or second-order polynomial) to fit the baseline, and then subtracts the fitted baseline from the original signal to obtain the corrected signal, thereby effectively removing the slowly changing baseline drift. Preferably, the processor 110 of the activity measurement unit 100 can use the method of reference signal correction to correct baseline drift because it can provide higher accuracy in radioactive activity detection, especially in the case of quantitative analysis. Among them, the method of reference signal correction uses a known reference signal for comparison and adjusts the signal baseline to be consistent with the reference signal to ensure high-precision measurement.

[0043] Preferably, in the step of calculating the radioactivity of the drug, the processor 110 of the activity measurement unit 100 can obtain the total energy or total count of the signal by integrating the corrected signal. Among them, in radioactive activity detection, the gradient method can be used for numerical integration because it is simple to calculate and can meet the accuracy requirements in most cases.

[0044] Preferably, the processor 110 of the activity measurement unit 100 can calculate the radioactivity of the drug based on the integration result and known physical parameters. The calculation formula is as follows: ,

[0045] Where A is the radioactivity, with the unit of mCi; N is the number of counts detected within time t; ε is the detector efficiency; and t is the measurement time.

[0046] Preferably, the detector efficiency refers to the ratio of the number of rays that the detector 120 can detect to the number of rays actually emitted. It reflects the response ability of the detector 120 to rays of specific energy and type. Usually, the detector efficiency can be determined through experimental calibration. Further, the processor 110 of the activity measurement unit 100 can also be provided with a calibration factor k for correcting the measurement result to compensate for possible systematic errors in the measurement process. These errors may stem from factors such as the characteristics of the detector 120 itself, environmental conditions, and measurement methods. Among them, the calibration factor can also be determined through experimental calibration. Therefore, the calculation formula for the corrected radioactivity is: ,

[0047] Where k is the calibration factor.

[0048] Preferably, the data processed by the processor 110 of the activity measurement unit 100 can be expressed in internationally common radioactivity units (usually mCi) and presented to the user through a graphical interface. Preferably, the processor 110 of the activity measurement unit 100 can be communicatively connected to the medical staff terminal 400 so that key parameters, such as the currently measured activity value and the reference value range, can be displayed on the interface of the medical staff terminal 400. At the same time, a historical data query function can also be provided to help users understand the change trend of the drug activity. Preferably, when the measurement result exceeds the preset safety range, the processor 110 of the activity measurement unit 100 can automatically trigger an alarm to alert the operator. Among them, the alarm can be presented visually (such as a red warning light), auditorily (such as a beeping sound), or in a combination of both to ensure that it can be quickly noticed even in a noisy environment. In addition, the alarm can also be reminded through the medical staff terminal 400.

[0049] Preferably, the activity measurement unit 100 can be communicatively connected to the analysis unit 300 so that the currently measured activity value of the activity detection unit can be sent to the analysis unit 300, thereby facilitating the analysis unit 300 to calculate the drug dosage.

[0050] Preferably, to ensure the accuracy of the measurement, the activity measurement unit 100 can be calibrated regularly, and the calibration process and results can be recorded. In addition, a detailed maintenance plan can also be formulated, including cleaning, inspection, and replacement of damaged components, etc., to ensure the long-term stable operation of the equipment.

[0051] Preferably, to ensure the efficiency of the system and the accuracy of data, the input unit 200 responsible for collecting and verifying the patient's basic information and medical history records can be designed with user-friendliness, data verification, and privacy protection in mind. Preferably, the input unit 200 can be configured with a digital input device 210, which can be particularly built into the medical staff terminal 400. Among them, the input device 210 can be, for example, a touch screen or a keyboard, etc. Preferably, when the input device 210 of the input unit 200 is a touch screen, the capacitive touch screen has better sensitivity and response speed, making it more suitable for use in a medical environment. Preferably, when the input device 210 of the input unit 200 is a keyboard, it can be a standard QWERTY keyboard or a simplified keyboard designed specifically for the medical environment to be applicable to situations where a large amount of text information needs to be input.

[0052] Preferably, the patient data input through the input unit 200 can be stored in a structured manner to facilitate data exchange with the analysis unit 300. Preferably, the data storage format can include relational databases (such as MySQL, PostgreSQL) and NoSQL databases (such as MongoDB). Among them, relational databases are suitable for structured data and support complex queries and transaction processing; NoSQL databases are suitable for unstructured or semi-structured data and support high-concurrency access and distributed storage.

[0053] Preferably, the input unit 200 can verify the accuracy of the relevant basic information input through the input device 210. For example, the input data can be restricted by setting reasonable numerical ranges to avoid the entry of incorrect data. Exemplarily, for age information, the input unit 200 can limit it to 0 - 130 years old; for weight information, the input unit 200 can limit it to 0 - 500 kilograms; for height information, the input unit 200 can limit it to 0 - 250 centimeters.

[0054] Preferably, the data transmission between the input unit 200 and the analysis unit 300 should adopt secure and reliable protocols, such as HTTPS, TLS, etc., to ensure the security and integrity of the data during transmission. At the same time, the system needs to comply with relevant medical data protection laws and regulations to ensure the security of patients' personal information.

[0055] Preferably, the analysis unit 300 can be configured with a high-performance CPU to process data from the activity measurement unit 100 and the input unit 200, so as to determine the required volume of the drug to be drawn for the current injection of the patient by calculation. Preferably, a multi-core CPU can process multiple tasks in parallel to improve the calculation efficiency, and a high-frequency CPU can execute a single task faster to shorten the calculation time. Preferably, the analysis unit 300 can be provided with sufficient memory (such as at least 16GB of RAM) to store and process a large amount of data. Among them, high-speed memory can improve the data reading and writing speed and enhance the system performance. Preferably, the analysis unit 300 can be provided with a reliable storage device to save patient data and calculation results. Among them, the storage device can have a large storage capacity (such as at least 500GB) to accommodate a large number of data files and log records.

[0056] Preferably, the analysis unit 300 can communicate with the activity measurement unit 100 and the input unit 200 in a wired and / or wireless manner. Among them, the wired connection can include an Ethernet connection suitable for long-distance transmission and a USB connection suitable for short-distance transmission; the wireless connection can include a Wi-Fi connection suitable for scenarios requiring mobility and a Bluetooth connection suitable for short-distance, low-power device communication. Preferably, the data reception of the analysis unit 300 can be achieved through a standardized communication protocol (such as TCP / IP, HTTP) to ensure the integrity and security of the data. Further, the analysis unit 300 can verify the received data to ensure the accuracy and integrity of the data. After the data is verified, it can be preprocessed through operations such as data cleaning, format conversion, and normalization to prepare for subsequent algorithm calculations. Among them, data cleaning is used to remove invalid or incorrect data to ensure data quality; format conversion is used to convert data from different sources into a unified format for easy processing; normalization is used to scale the data to the same range to improve the convergence speed and accuracy of the algorithm.

[0057] Preferably, as Figure 3As shown, the analysis unit 300 can be built-in with a data lookup table summarized based on experience, and different types of radiopharmaceuticals can have corresponding data lookup tables. Exemplarily, the radiopharmaceuticals applicable to the radiopharmaceutical dosage control system of the present invention may include, but are not limited to, 18F-FDG, TSPO, AV45, AV133. Among them, the radioisotopes of the above four radiopharmaceuticals are all 18F, and their half-life is about 110 minutes. Preferably, 18F-FDG is 2-[18F]fluoro-2-deoxy-D-glucose, which is the most commonly used positron emission tomography (PET) tracer, mainly used for the diagnosis of oncology, neurology, and cardiology. It simulates the metabolic pathway of glucose, is taken up by cells and phosphorylated intracellularly, thus showing the metabolic activity of cells in PET images. Studies have shown that fasting can significantly affect the metabolism and imaging contrast of 18F-FDG. During fasting, the metabolic substrate of the body changes from glucose to free fatty acids, and this metabolic shift can be used to inhibit the physiological uptake of the myocardium, thereby improving the contrast of 18F-FDG in cardiology and cancer imaging. (Ahmadpour, S., Hosseinimehr, S., & Habibi, M. (2022). Various Aspects of Fasting on the Biodistribution of Radiopharmaceuticals.. Current drug metabolism . https: / / doi.org / 10.2174 / 1389200223666220919121354.) Preferably, TSPO is the [18F]TSPO ligand, which is used for PET imaging and is mainly used to evaluate brain inflammation and neurodegenerative diseases such as Alzheimer's disease and Parkinson's disease. The TSPO ligand can bind to the translocator protein (TSPO) on the mitochondria, thereby reflecting the degree of cell inflammation and damage. Research on TSPO radiopharmaceuticals mainly focuses on the optimization of pharmacokinetic parameters of other radiopharmaceuticals. Through the physiologically based pharmacokinetic (PBPK) model, the distribution and uptake of radiopharmaceuticals in the body can be simulated and predicted, and then the treatment plan can be optimized. (Abdollahi, H., Fele-Paranj, A., Saboury, B., Uribe, C., & Rahmim, A. (2023). Radiobiological-guided radiopharmaceutical therapy: Radiopharmacokinetic parameter optimization using PBPK modeling. 2023 IEEE Nuclear Science Symposium, Medical Imaging Conference and International Symposium on Room- Temperature Semiconductor Detectors (NSS MIC RTSD), 1-1. https: / / doi.org / 10.1109 / NSSMICRTSD49126.2023.10338502.). Preferably, AV45 is [18F]Florbetapir, a beta-amyloid (Aβ) tracer for PET imaging, mainly used for the early diagnosis of Alzheimer's disease. It can specifically bind to Aβ plaques in the brain, thus showing the distribution of plaques in PET images. AV45 is mainly used for imaging studies of Alzheimer's disease. Similar radiopharmaceutical studies have shown that pharmacokinetic parameters such as binding rate, internalization rate, and serum protein binding rate have a significant impact on the biodistribution and effective dose of the drug. (Siebinga, H., De Wit-Van DerVeen, B., Stokkel, M., Huitema, A.,&Hendrikx, J. (2022). Current use andfuture potential of (physiologically based) pharmacokinetic modelling ofradiopharmaceuticals: a review. Theranostics, 12, 7804 - 7820. https: / / doi.org / 10.7150 / thno.77279.). Preferably, AV133 is [18F]Flutemetamol, and AV133 is another β-amyloid (Aβ) tracer for PET imaging, mainly used for the diagnosis of Alzheimer's disease. It can specifically bind to Aβ plaques in the brain, thus showing the distribution of plaques in PET images. The metabolism and enrichment of these four radiopharmaceuticals are significantly affected by the patient's physiological parameters: 18F-FDG: requires correction of blood glucose (CBG) and insulin sensitivity (CISI); TSPO ligand: requires correction of liver enzyme activity (CLEA); AV45 and AV133: require correction of renal function (CGFR) and blood glucose (CBG). (Abdollahi, H., Yousefirizi, F., Shiri, I., Brosch-Lenz, J., Mollaheydar, E., Fele-Paranj, A., Shi, K., Zaidi, H., Alberts, I., Soltani, M., Uribe, C., Saboury, B., & Rahmim, A. (2024). Theranostic digital twins: Concept, framework and roadmap towards personalized radiopharmaceutical therapies. Theranostics , 14, 3404 - 3422. https: / / doi.org / 10.7150 / thno.93973.). Exemplarily, the following is a partial data lookup table for the above four radiopharmaceuticals.

[0058]

[0059]

[0060]

[0061]

[0062] Preferably, as Figure 3 shown, the analysis unit 300 can calculate the dose of the radiopharmaceutical according to the patient-specific physiological parameters and the specific activity of the drug. Among them, the patient-specific physiological parameters can be, for example, the body surface area BSA. Preferably, the body surface area can be calculated by the following formula: ,

[0063] In the formula, BSA is the body surface area in square meters; H is the height in centimeters; and W is the weight in kilograms.

[0064] Preferably, after obtaining the body surface area, it can be used to calculate the dose of the radiopharmaceutical. Usually, the dose of the drug is given as the activity required per unit body surface area. Therefore, if the recommended dose of a certain drug is α mCi / m 2 , then the total activity dose D that the patient should receive can be calculated using the total activity dose formula: .

[0065] Furthermore, the recommended dose α of the drug can be determined by methods such as literature and guideline recommendations, clinical trial data, and / or pharmacokinetic and pharmacodynamic models. Among them, different types of drugs may have corresponding recommended doses α.

[0066] In nuclear medicine practice, the calculation of the dosage of radiopharmaceuticals is a key link to ensure the diagnostic effect and patient safety. However, the current technology has obvious limitations in dealing with radiopharmaceuticals with different characteristics. On the one hand, due to the complexity of the radiopharmaceuticals themselves - including but not limited to their half-life, the type of emitted particles (such as gamma rays, beta particles), chemical properties, and biodistribution characteristics, etc. - each drug has different dosage requirements. On the other hand, most of the existing dosage calculation methods do not fully consider the diversity of these drug characteristics, resulting in recommended doses often being based on fixed patterns or empirical formulas, lacking a targeted correction mechanism. For example, when facing radioactive isotopes with different half-lives, the current technology is difficult to make real-time adjustments according to the activity of the drug changing over time; another example is that for radiopharmaceuticals with strong affinity for specific tissues, the current practice does not provide enough flexibility to meet the individualized diagnostic needs. In addition, the traditional dosage calculation method usually relies on manual input of parameters and offline processing, which not only increases the risk of human error but also limits the effective utilization of historical data and cannot support post-event analysis and optimization.

[0067] Preferably, the analysis unit 300 of the present invention can accurately determine the total activity dose D that the patient should receive by simultaneously using the above data lookup table and numerical calculation method. Among them, for different types of radiopharmaceuticals, the analysis unit 300 can generate at least two standard curves through different data sources. Further, the analysis unit 300 can generate a first standard curve based on the data in the corresponding data lookup table, and can generate a second standard curve based on the total activity dose formula with the standard recommended dose preset by the specific drug type and diagnostic purpose as the coefficient. Among them, both the first standard curve and the second standard curve can use the body surface area BSA as the abscissa and the total activity dose D as the ordinate, so as to form two non-overlapping standard curves in the same coordinate system, and form a safety interval through the envelope of these two standard curves.

[0068] Preferably, the accuracy of the total activity dose D that a patient should receive, which is simply determined by using a data lookup table or numerical calculation, is not very high. This is because the above single methods rely relatively heavily on clinical experience data and do not make corrections based on the individual conditions of the patient, resulting in a mismatch between the total activity dose actually received by the patient and the total activity dose that the patient needs to receive. This situation may lead to problems such as poor imaging effects during PET-CT, as recorded in the following paper: Botkin C D, Osman M M. Prevalence, challenges, and solutions for (18)F-FDG PET studies of obese patients: a technologist's perspective. [J]. Journal of Nuclear Medicine Technology, 2007, 35(2):80. However, if the obtained total activity dose D is simply corrected, it is difficult to determine whether the corrected value is reasonable. Therefore, the purpose of setting a safety interval in the present invention is to correct the total activity dose D according to the drug type and in combination with the individual conditions of the patient. In particular, the calculation result of the total activity dose D can be corrected by correcting the recommended dose α, and then it is determined whether the corrected calculation result falls within the safety interval. Among them, if the corrected calculation result falls within the safety interval, the corrected calculation result can be used as the dosage of the radiopharmaceutical; if the corrected calculation result does not fall within the safety interval, an alarm is issued, and the medical staff re-evaluates the patient carefully. Further, the analysis unit 300 can set a neutral interval outside the safety interval between the two standard curves. This neutral interval can exist as an additional safety margin to cope with potential uncertainties and changes. The deviation amount of the neutral interval relative to the boundary value of the safety interval can be determined according to specific clinical experience and practice. Optionally, considering the safety and effectiveness of nuclear medicine, the deviation amount of the neutral interval relative to the boundary value of the safety interval can be set to ±5% to ±10%. Among them, +5% to +10% is the deviation amount of the upper boundary value of the neutral interval relative to the upper boundary value of the safety interval, and -5% to -10% is the deviation amount of the lower boundary value of the neutral interval relative to the lower boundary value of the safety interval. The area between the upper boundary value and the lower boundary value of the neutral interval excluding the area of the safety interval is the area of the neutral interval. In a scenario where the diagnostic purpose is relatively easier, the combined interval composed of the neutral interval and the safety interval can be used as the basis for judging the corrected calculation result.

[0069] Preferably, the analysis unit 300 can modify the recommended dose α or directly modify the total activity dose D according to the drug type in combination with the patient's individual conditions, where the patient's individual conditions are physiological parameters related to the drug type, which mainly consider one or more physiological parameters that have the most significant impact on the metabolism and enrichment of the corresponding type of radiopharmaceutical. Preferably, several physiological parameters that affect the metabolism and enrichment of a certain type of drug can be sorted according to the degree of influence to screen out one or more physiological parameters with relatively higher degrees of influence, so as to use these physiological parameters to modify the recommended dose α or the total activity dose D.

[0070] Exemplarily, the patient's blood glucose level and insulin sensitivity have a significant impact on the metabolism and enrichment of 18F-FDG (2-[18F]fluoro-2-deoxy-D-glucose); the patient's liver enzyme activity has a significant impact on the metabolism and enrichment of TSPO (translocator protein); the patient's renal clearance rate and blood glucose have a significant impact on the metabolism and enrichment of AV45 ([18F]Florbetapir); the patient's renal clearance rate and blood glucose have a significant impact on the metabolism and enrichment of AV133 ([18F]Flutemetamol). Further, the physiological parameters related to the above four radiopharmaceuticals may include blood glucose level (BG), insulin sensitivity index (ISI), liver enzyme activity (LEA), and glomerular filtration rate (GFR), so as to form a blood glucose level correction coefficient (C BG ), insulin sensitivity index (C ISI ), liver enzyme activity correction coefficient (C LEA ), and glomerular filtration rate correction coefficient (C GFR ). Exemplarily, the above four correction coefficients can be set as follows: ,

[0071] ,

[0072] ,

[0073] .

[0074] Therefore, for 18F-FDG (2-[18F]fluoro-2-deoxy-D-glucose), its total correction coefficient is: C 18F-FDG =C BG ×C ISI ; for TSPO (translocator protein), its total correction coefficient is: C TSPO =C LEA ; for AV45 ([18F]Florbetapir), its total correction coefficient is: C AV45 =C BG ×C GFR; For AV133 ([18F]Flutemetamol), its total correction factor is: C AV133 = C BG × C GFR . Based on this, the corrected total activity dose D can be obtained according to the drug type and combined with the patient's individual conditions.

[0075] As Figure 4 shown, in the coordinate system with body surface area BSA as the abscissa and total activity dose D as the ordinate, the first standard curve is generated based on the data in the corresponding data lookup table, and the second standard curve is generated based on the total activity dose formula with the standard recommended dose preset according to the specific drug type and diagnostic purpose as the coefficient; then the safety interval is formed by the envelope of the first standard curve and the second standard curve; finally, the total activity dose D can be corrected according to the drug type and combined with the patient's individual conditions to determine whether the corrected total activity dose D is above, within, or below the safety interval. Further, when the judgment result is that the corrected total activity dose D is within the safety interval, it means that the corrected dose is within the recommended safety range, indicating that under the given body surface area and patient characteristics, the dose is considered to meet the standard and has a reasonable balance of risks and benefits, that is, usually, such a dose is acceptable and can be continued to be used. When the judgment result is that the corrected total activity dose D is above the safety interval, it means that the corrected dose is higher than the recommended safety range, which may bring a higher risk of toxicity or adverse reactions and exceed the safety limit of the diagnosis, and a first alarm needs to be issued to remind medical staff to carefully consider whether the dose can be adjusted or other measures can be taken to reduce the potential risk, or evaluate whether such a high dose is really needed. When the judgment result is that the corrected total activity dose D is below the safety interval, it means that the corrected dose is lower than the recommended safety range, which may lead to insufficient diagnostic effect because the dose may not be sufficient to achieve the required therapeutic effect, and a second alarm needs to be issued to remind medical staff to evaluate whether the dose should be increased to ensure the effectiveness of the diagnosis while remaining within the safe limit. Further, the total activity dose D corrected by the above method can be used to compare with the safety interval. Preferably, the above safety interval can also be replaced by a combined interval composed of a neutral interval and a safety interval.

[0076] Preferably, as Figure 5As shown, the radioactive drug dosage control system of the present invention may further include a volume measurement unit 600 for measuring the current residual volume of the drug in the medicine storage bottle 500. Among them, the volume measurement unit 600 can use technologies such as ultrasonic volume measurement technology, capacitive volume measurement technology, or optical volume measurement technology to achieve the volume measurement of the drug. Further, considering that there is a rubber stopper and aluminum foil paper on the top of the medicine storage bottle 500 containing radioactive drugs, when using ultrasonic volume measurement technology and optical volume measurement technology, it is necessary for the sensor to vertically align with the liquid surface to emit ultrasonic waves or light, which is difficult to penetrate the rubber stopper and aluminum foil paper on the top of the medicine storage bottle 500, affecting the measurement accuracy. Therefore, the non-contact capacitive volume measurement technology can arrange the electrode 610 outside the medicine storage bottle 500 and judge the volume of the liquid by measuring the influence of the liquid on the electric field. This method does not require the electrode 610 to directly contact the liquid, reducing the risk of contamination to the liquid and being suitable for the measurement of sensitive liquids (such as radioactive drugs). Further, as Figure 5 shown, the electrode 610 arranged outside the medicine storage bottle 500 can adopt a ring electrode to facilitate uniformly surrounding the bottle body.

[0077] Preferably, the analysis unit 300 can calculate the current activity concentration of the drug in the medicine storage bottle 500 according to the current activity and volume of the drug in the medicine storage bottle 500, and its calculation formula is: ,

[0078] In the formula, C is the current activity concentration of the drug in the medicine storage bottle 500, A is the current activity of the drug in the medicine storage bottle 500, and V 残余 is the residual volume of the drug in the medicine storage bottle 500.

[0079] Further, the analysis unit 300 can calculate the volume of the drug required by the patient according to the total activity of the drug that the patient should receive and the current activity concentration of the drug in the medicine storage bottle 500, and its calculation formula is: ,

[0080] In the formula, V 所需 is the volume of the drug required by the patient, D is the total activity of the drug that the patient should receive, and C is the current activity concentration of the drug in the medicine storage bottle 500.

[0081] Preferably, the radioactive drug dosage control system of the present invention can be separately provided with a display unit near the storage area of the medicine storage bottle 500, and / or integrated with a display unit on the medical staff side 400 to display the calculation results to the medical staff through the display unit, so as to facilitate the medical staff to manually complete the drug measurement according to the calculated volume of the drug required by the patient.

[0082] Preferably, the radioactive drug dosage control system of the present invention may also be provided with a drug dispensing robotic arm for automatically completing drug dispensing according to the control signal generated by the analysis unit 300. Among them, the analysis unit 300 can generate a control signal for driving the drug dispensing robotic arm according to the drug volume required by the patient in the calculation result. Preferably, the drug dispensing robotic arm may include a stepper motor for precisely controlling the movement of the piston to achieve the extraction of a specified volume of drug. Preferably, the drug dispensing robotic arm may include acquisition elements such as a position sensor and a pressure sensor for real-time monitoring of the position and pressure of the piston. Preferably, the drug dispensing robotic arm may include a microcontroller communicatively connected to the analysis unit 300 to control the stepper motor and the sensor to execute the control logic according to the control signal.

[0083] Preferably, medical staff can input and modify prescription information through the operation interface of the medical staff terminal 400, and patients can view their own examination information and drug dosage through the interface of the patient terminal. When the system is running, it should be able to notify doctors and patients in real time about important updates or alerts regarding drug dosage.

[0084] Preferably, as Figure 6 shown, the radioactive drug dosage control system of the present invention may be provided with a timing unit 700 for starting timing when the analysis unit 300 obtains the calculation result. Among them, the timing unit 700 can set different interval durations for different types and different states of drugs. When the drug dispensing is not completed beyond the set interval duration, it is determined that this drug dispensing operation is invalid, and the timing unit 700 sends an invalid signal to the analysis unit 300 so that the analysis unit 300 recalculates according to the current situation. Preferably, the timing unit 700 can adjust the interval duration of each drug in real time based on parameters such as the half-life of the drug, the current activity value, and the allowable maximum activity loss. Among them, the allowable maximum activity loss can be calculated by the analysis unit 300 according to the preset maximum error value when calculating the drug volume.

[0085] The decay formula of the radioactive drug is: ,

[0086] In the formula, A(t) is the activity of the drug at time t, A is the current activity of the drug, λ is the decay constant, t is the time, and e is the base of the natural logarithm.

[0087] The decay constant λ and the half-life T 1 / 2 are related as: .

[0088] Therefore, the timing unit 700 can set the interval duration according to the following formula:

[0089] ,

[0090] In the formula, T 1 / 2is the half-life of the drug, A is the current activity of the drug, and A target is the deviation activity of the drug. Further, the deviation activity of the drug can be obtained by subtracting the preset maximum allowable activity loss from the current activity of the drug.

[0091] Exemplarily, if the maximum allowable activity loss is simply set to 0.03A, it can be calculated that for drugs with a half-life of 110 minutes such as 18F-FDG, the drug needs to be taken within about 5 minutes after the analysis unit 300 outputs the calculation result; for drugs with a half-life of 68 minutes such as 68Ga, the drug needs to be taken within about 3 minutes after the analysis unit 300 outputs the calculation result.

[0092] The radioactive drug dosage control system provided with the timing unit 700 of the present invention is particularly applicable to drugs with a short half-life. Such drugs have extremely high requirements for dosage accuracy during use. Therefore, the timing unit 700 that can flexibly set an appropriate interval duration according to the type and state of the measured drug can well ensure that the measuring operation performed according to the calculation result output by the analysis unit 300 can meet the accuracy requirements.

[0093] Preferably, the radioactive drug dosage control system of the present invention may be provided with radioactive surface contamination measuring equipment for measuring the radioactive residue on the tabletop where the medicine storage bottle 500 is located to ensure the safety of the operating environment. Through real-time monitoring, radioactive contamination can be detected and processed in a timely manner to avoid environmental pollution and radiation hazards to operators. Preferably, the radioactive surface contamination measuring equipment may use a Geiger-Müller (GM) counter or a semiconductor detector. Among them, the GM counter is a gas discharge tube. When radioactive particles pass through the gas in the tube, it will cause the release and amplification of electrons, generating an electrical signal. The GM counter has high sensitivity to α and β particles; the semiconductor detector (such as a silicon PIN detector) measures the radioactive level by detecting the charge generated by radioactive particles in the semiconductor material. The semiconductor detector has higher energy resolution and sensitivity. Preferably, the radioactive surface contamination measuring equipment may be installed near the tabletop where the medicine storage bottle 500 is located to ensure coverage of the entire operating area. Preferably, the data obtained by the radioactive surface contamination measuring equipment can be sent to the analysis unit 300 for data processing to judge the radioactive residue on the tabletop through the threshold set by the analysis unit 300. When the radioactive level exceeds the threshold, an alarm is triggered.

[0094] It should be noted that the above specific embodiments are exemplary. Those skilled in the art can come up with various solutions inspired by the disclosure of the present invention, and these solutions also fall within the scope of the disclosure of the present invention and within the protection scope of the present invention. Those skilled in the art should understand that the description and drawings of the present invention are illustrative and do not constitute a limitation on the claims. The protection scope of the present invention is defined by the claims and their equivalents. The description of the present invention contains multiple inventive concepts. For example, "preferably" or "according to a preferred embodiment" indicates that the corresponding paragraph discloses an independent concept. The applicant reserves the right to file divisional applications based on each inventive concept. Throughout the text, the features guided by "preferably" are only optional and should not be understood as must-be-set. Therefore, the applicant reserves the right to waive or delete relevant preferred features at any time.

Claims

1. A radioactive drug dosage control system for pre-injection imaging analysis, characterized in that, It includes: An activity measurement unit (100) for measuring the current radioactivity of the drug in the target medicine storage bottle (500); An input unit (200) for obtaining relevant basic information of the current patient taking the medicine, where the relevant basic information includes the patient's weight information and height information; An analysis unit (300) for determining the volume of the drug required for the current injection extraction for the patient according to the radioactivity of the drug in the current medicine storage bottle (500) and the relevant basic information of the current patient taking the medicine; where After receiving the current radioactivity, the weight and height of the current patient taking the medicine sent by the activity measurement unit (100), for different types of radioactive drugs, the analysis unit (300) generates a first standard curve based on retrieving the data in the built-in data lookup table corresponding to different types of radioactive drugs summarized according to experience, and generates a second standard curve based on the total activity dose formula with the standard recommended dose preset according to the specific drug type and treatment purpose as a coefficient. Both the first standard curve and the second standard curve take the body surface area as the abscissa and the total activity dose as the ordinate, so as to form two non-overlapping standard curves that enclose the safety interval of medication in the same coordinate system. Among them, the recommended dose or the total activity dose is corrected according to the drug type and combined with the patient's individual conditions, where the individual conditions are physiological parameters related to the patient's metabolism and enrichment of radioactive drugs, including blood glucose level, insulin sensitivity, liver enzyme activity, and / or renal clearance rate.

2. The system according to claim 1, characterized in that, The activity measurement unit (100) arranges corresponding detectors (120) at dedicated measurement sites close to the corresponding medicine storage bottle (500) in the storage area of the medicine storage bottle (500). The original signals collected by the detectors (120) are sent to the processor (110) of the activity measurement unit (100) after conversion, so as to calculate the radioactivity of the drug through signal processing.

3. The system according to claim 2, characterized in that, The processor (110) of the activity measurement unit (100) integrates the corrected signals using the gradient method to obtain the total energy or total count of the signals, and then calculates the radioactivity of the drug according to the integration result and physical parameters, where the physical parameters include detector efficiency and / or calibration factor.

4. The system according to claim 3, wherein The data processed by the processor (110) of the activity measurement unit (100) can be displayed to the user through a graphical interface. Among them, the processor (110) of the activity measurement unit (100) can be communicatively connected to the medical staff terminal (400), so that key parameters including the currently measured activity value and the reference value range can be displayed on the interface of the medical staff terminal (400), and a historical data query function is provided.

5. The system according to claim 1, wherein The input unit (200) can be configured with a digital input device (210). The input unit (200) can verify the accuracy of relevant basic information input through the input device (210) by setting the numerical range of corresponding parameters, so that the correct relevant basic information entered in the input unit (200) can be transmitted to the analysis unit (300) through a secure protocol.

6. The system according to claim 1 or 5, characterized in that, It includes a volume measurement unit (600) for measuring the current residual volume of the drug in the medicine storage bottle (500). Among them, the volume measurement unit (600) can arrange electrodes (610) outside the corresponding medicine storage bottle (500), so that the analysis unit (300) can calculate the drug volume required by the patient by using the residual volume of the drug obtained by the volume measurement unit (600) based on the capacitive volume measurement technology.

7. The system according to claim 1, wherein It includes a timing unit (700) for starting timing when the analysis unit (300) obtains the calculation result. The timing unit (700) can set different interval durations for different types and different states of drugs. Among them, when the drug measurement is not completed after exceeding the set interval duration, it is determined that the current drug measurement operation is invalid. The timing unit (700) sends an invalid signal to the analysis unit (300) so that the analysis unit (300) recalculates according to the current situation.

8. The system according to claim 7, wherein The timing unit (700) can adjust the interval duration of each drug in real time based on parameters including the half-life of the drug, the current activity value, and the allowable maximum activity loss. Among them, the allowable maximum activity loss can be calculated by the analysis unit (300) according to the preset maximum error value when calculating the drug volume.

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