Radiopharmaceutical dosage control system

Abstract

The invention relates to a radiopharmaceutical dosage control system, and belongs to the technical field of radiopharmaceutical measurement. The system comprises: an activity measuring unit for measuring the current radioactive activity of a drug in a target drug storage bottle; the input unit is used for acquiring related basic information of a current medication patient, and the related basic information comprises weight information and height information of the patient; and the analysis unit is used for determining the volume dose required by the currently injected and extracted medicine for the patient according to the radioactive activity of the medicine in the current medicine storage bottle and the related basic information of the current medication patient. The accuracy of medicine dose calculation is improved, and the operation efficiency and the user experience of the system are remarkably improved. Through accurate activity measurement and accurate input of patient information, the system can quickly generate a personalized dosage scheme, errors caused by manual operation are reduced, and the use safety and effect are improved.

Description

Technical Field

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

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

[0003] The radioactive isotopes of radiopharmaceuticals decay over time, and their activity gradually decreases. The half-lives of different radioactive isotopes vary greatly, for example, the half-life of 18F-FDG is about 110 minutes, the half-life of 99mTc is about 6 hours, the half-life of 131I is about 8 days, and the half-life of 68Ga is about 68 minutes. Therefore, the activity of radiopharmaceuticals changes at different rates over time, which puts different requirements on the use and management of drugs.

[0004] CN117631003A discloses a radiopharmaceutical activity meter and an activity calculation method. The structure of the activity meter includes: a shell, which is located at the outermost layer of the activity meter and is used to accommodate various components of the activity meter and prevent gamma rays from irradiating the surroundings; a built-in shielding layer, which is located in the shell, and the space surrounded by the built-in shielding layer can be embedded with a glass container for accommodating radioactive drugs, and the built-in shielding layer is used to shield the gamma rays emitted by the radioactive nuclides; a side collimation cavity and a bottom collimation cavity, both of which are located on the built-in shielding layer; the axis of the side collimation cavity is perpendicularly intersected with the cylindrical axis of the built-in shielding layer, and the axis of the bottom collimation cavity coincides with the cylindrical axis of the built-in shielding layer, and the side collimation cavity and the bottom collimation cavity are used for gamma rays emitted by the radioactive nuclides to pass through the built-in shielding layer, ensuring that the gamma rays can only pass through the built-in shielding layer from the collimation cavity; a side detector and a bottom detector, both of which are located between the shell and the built-in shielding layer, the side detector is directly opposite to the side collimation cavity, and the bottom detector is directly opposite to the bottom collimation cavity, and is used to detect the gamma rays passing through the collimation cavity; an electronic processing system, which is located between the shell and the built-in shielding layer, connects the side detector and the bottom detector, and is used to obtain the counting rate A1 of the side detector and the counting rate A2 of the bottom detector.

[0005] CN107462915A discloses a method and system for real-time measurement of radiopharmaceutical activity, and relates to the technical field of obtaining radiopharmaceutical activity. The system includes: a data entry module for entering initial information and current information of radiopharmaceuticals, wherein the initial information of radiopharmaceuticals includes initial activity, initial volume and activity detection time of radiopharmaceuticals, and the current information includes current time and activity required by the user; a processing module for calculating the volume of radiopharmaceuticals required by the user based on the initial information and current information of radiopharmaceuticals; and a display module for displaying the volume of radiopharmaceuticals required by the user.

[0006] The decay of the activity of radioactive drugs over time has a significant impact on the medical staff's use operation. In order to ensure the accuracy of drug dosage and the diagnostic / treatment effect, medical staff need to complete the use of drugs before the activity of the drugs drops to an unacceptable level, and each time they take the drugs, they need to measure not only the residual volume in the bottle, but also the decay of the drugs in the current ampoule. Therefore, accurate dosage calculations are required before each drug is extracted. However, the existing technology cannot achieve this precise calculation, and medical staff are required to repeatedly extract and measure clinically, which not only affects the patient's treatment timing, but also increases the workload of medical staff, and even causes great harm to the health of medical staff due to the prolonged contact time between medical staff and radioactive drugs.

[0007] In addition, on the one hand, there are differences in understanding among those skilled in the art; on the other hand, the applicant studied a large number of documents and patents when making the present invention, but due to space limitations, not all details and contents are listed in detail. However, this does not mean that the present invention does not have the characteristics of these prior arts. On the contrary, the present invention already has all the characteristics of the prior art, and the applicant reserves the right to add relevant prior art to the background technology. Summary of the invention

[0008] In view of the deficiencies of the prior art, the present invention provides a radiopharmaceutical dosage control system to solve at least part of the above technical problems.

[0009] The present invention discloses a radioactive drug dosage control system, which comprises: an activity measurement unit, used for measuring the current radioactivity of the drug in a target drug storage bottle; an input unit, used for obtaining relevant basic information of a patient currently taking the drug, wherein the relevant basic information includes the patient's weight information and height information; and an analysis unit, used for determining the volume of the drug currently injected and extracted for the patient according to the radioactivity of the drug in the current drug storage bottle and the relevant basic information of the patient currently taking the drug.

[0010] In the field of nuclear medicine, traditional radiopharmaceutical dose calculation often relies on manual operation. 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 in modern medicine. However, the radiopharmaceutical dosage control system of the present invention integrates an activity measurement unit, an input unit, and an analysis unit to realize the full process automation management from drug activity measurement to patient information acquisition to dose calculation. The system can not only measure the current activity of the radiopharmaceutical in the storage bottle in real time and accurately, but also automatically calculate the personalized injection volume according to the patient's weight, height, and other physiological parameters, ensuring the accuracy of each dose; at the same time, all data in the operation process are digitally recorded for future query and analysis, thereby providing medical staff with detailed historical medication record support, which helps to optimize the treatment plan. This design not only improves the accuracy of drug dose calculation, but also significantly improves the system's operating efficiency and user experience. Through accurate activity measurement and accurate entry of patient information, the system can quickly generate personalized dosage plans, reduce manual operation errors, reduce repeated extractions, reduce the time for medical staff to frequently contact radiopharmaceuticals, and improve the safety and effect of diagnosis / treatment. In addition, the system's automated management function can reduce the workload of medical staff, improve the utilization efficiency of medical resources, help optimize medical processes, and improve the overall level of medical services.

[0011] According to a preferred embodiment, the activity measurement unit arranges corresponding detectors at dedicated measurement sites close to corresponding medicine bottles in the medicine bottle storage area. The original signals collected by the detectors are converted and sent to the processor of the activity measurement unit to calculate the radioactivity of the drug through signal processing.

[0012] By arranging detectors at dedicated measurement sites in the storage area of ​​the medicine storage bottles, 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 tested can be correctly placed in front of the detector, avoiding measurement errors caused by improper positioning. The design of dedicated measurement sites can also achieve 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, help to achieve more sophisticated and personalized diagnosis / treatment plans, and improve patients' diagnosis / treatment effects and quality of life.

[0013] According to a preferred embodiment, the processor of the activity measurement unit integrates the corrected signal using a gradient method to obtain the total energy or total count of the signal, and then calculates the radioactivity of the drug based on the integration result and physical parameters, wherein the physical parameters include detector efficiency and / or calibration factor.

[0014] By integrating the corrected signal using the gradient method and combining physical parameters such as detector efficiency and calibration factors, 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 and improve the signal-to-noise ratio of the signal, thereby ensuring high precision of activity measurement. The introduction of detector efficiency and calibration factors further corrects the measurement results, 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 achieve real-time monitoring and dynamic adjustment of drug activity, improving the intelligence level of the system.

[0015] 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, wherein the processor of the activity measurement unit can be communicated with the medical end so that the interface of the medical end can display key parameters including the currently measured activity value and the reference value range, and provide a historical data query function.

[0016] Through the communication connection between the graphical interface and the medical end, the present invention not only provides an intuitive data display function, but also realizes real-time sharing and remote management of data. The graphical interface enables medical staff to intuitively view the current activity value and reference value range, and timely understand the activity status of the drug, which improves 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 to carry out subsequent management and analysis and optimize diagnosis / treatment plans. In addition, the remote management function can also realize cross-regional data sharing and collaborative work, improve the utilization efficiency of medical resources, help promote the construction of medical informatization, and improve the overall level of medical services.

[0017] According to a preferred embodiment, the input unit can be configured with a digital input device, and the input unit can verify the accuracy of the relevant basic information input through the input device by setting the numerical range of corresponding parameters, so that the correct relevant basic information entered into the input unit can be transmitted to the analysis unit through a secure protocol.

[0018] By configuring a digital input device and setting the numerical range of the parameters, the present invention can significantly improve the accuracy and completeness of patient information entry. The digital input device provides a user-friendly operation interface, reduces errors in manual input, and ensures the accuracy and consistency of the data. The numerical range verification mechanism of the parameters can automatically detect and correct errors in the input data, avoiding dosage calculation errors caused by inaccurate data. In addition, the secure protocol transmission ensures the security and integrity of the data during the transmission process, and prevents the risk of data tampering or leakage. This high-precision data entry and transmission mechanism not only improves the reliability and security of the system, but also helps to achieve standardization and standardized management of data, promote the construction of medical informatization, and improve the overall level of medical services.

[0019] According to a preferred embodiment, after receiving the current radioactive activity of the drug in the current medicine storage bottle sent by the activity measurement unit and the relevant basic information of the current patient using the drug sent by the input unit, the analysis unit can determine the required volume of the drug currently injected by retrieving the built-in data lookup table corresponding to different types of radioactive drugs summarized based on experience, and / or can determine the required volume of the drug currently injected by numerical calculation based on the patient's specific physiological parameters and the specific activity of the drug.

[0020] By combining a data lookup table with numerical calculation, the present invention provides a flexible dose calculation method, which significantly improves the accuracy and personalization level of dose calculation. The data lookup table is based on rich clinical experience and data accumulation, ensuring the accuracy and reliability of dose calculation; the numerical calculation method can perform personalized dose calculation based on the patient's specific physiological parameters and drug characteristics, improving the accuracy of the dose and the diagnostic / therapeutic effect. In addition, this flexible dose calculation method can also adapt to different types of radioactive drugs and different diagnostic / therapeutic needs, improving the adaptability and scalability of the system.

[0021] According to a preferred embodiment, when the analysis unit determines the volume required for the current injection of the drug through 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, and the total active dose that the patient should receive is calculated based on the obtained body surface area combined with the recommended dose of the corresponding drug.

[0022] 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 / treatment effect. 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 personalization level of dose calculation. This dose calculation method based on body surface area not only helps to achieve a more scientific and personalized diagnosis / treatment plan, but also can reduce diagnosis / treatment failures caused by inaccurate doses, and improve the safety and effectiveness of use.

[0023] According to a preferred embodiment, the system includes a volume measuring unit for measuring the current residual volume of the drug in the medicine storage bottle, wherein the volume measuring unit is capable of disposing electrodes on the outside of the corresponding medicine storage bottle, so that the analysis unit can use the residual volume of the drug obtained by the volume measuring unit based on capacitive volume measurement technology to calculate the volume of medicine required by the patient.

[0024] By arranging (annular) electrodes on the outside of the medicine storage bottle and using 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 annular electrode ensures the uniform distribution of the measurement signal and avoids measurement errors caused by improper position. This non-contact measurement method not only avoids the contamination of the drug and the risk of radiation exposure to the operator, but also can achieve 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, which helps to achieve more sophisticated and personalized diagnosis / treatment plans, and improve the diagnosis / treatment effect and quality of life of patients.

[0025] 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 drugs of different types and states. When the set interval duration is exceeded and the drug measuring is not completed, the drug measuring operation is judged to be invalid, and the timing unit sends an invalid signal to the analysis unit so that the analysis unit recalculates according to the current situation.

[0026] By real-time monitoring of the time intervals for drug measurement and setting different interval durations, the present invention can significantly improve the accuracy of drug dosage and the diagnostic / therapeutic effect. Setting different interval durations for drugs of different types and states can better adapt to the activity change characteristics of different drugs, thereby improving the accuracy of dosage and the diagnostic / therapeutic effect. When the set interval duration is exceeded, the system can promptly issue an alarm and recalculate the dosage, thereby avoiding diagnosis / treatment failures due to 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 tracking and management of drug activity, thereby improving the intelligence level of the system, helping to optimize medical processes, and improving the overall level of medical services.

[0027] 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 maximum allowable activity loss, wherein the maximum allowable activity loss can be calculated by the analysis unit according to a preset maximum error value when calculating the drug volume.

[0028] By adjusting the interval duration of each drug in real time based on the half-life of the drug, the current activity value and the parameters of the maximum activity loss allowed, the present invention can significantly improve the accuracy of drug dosage and the diagnostic / therapeutic 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 maximum activity loss allowed ensures the accuracy and reliability of the dosage calculation and avoids the diagnosis / treatment failure caused by low activity. In addition, this dynamically adjusted timing mechanism can also realize real-time monitoring and dynamic adjustment of drug activity, improving the intelligence level of the system. BRIEF DESCRIPTION OF THE DRAWINGS

[0029] Figure 1 It is a hardware connection diagram of a radiopharmaceutical dosage control system according to a preferred embodiment of the present invention;

[0030] Figure 2 It is a data processing schematic diagram of a processor of an activity measurement unit according to a preferred embodiment of the present invention;

[0031] Figure 3 It is a working schematic diagram of an analysis unit according to a preferred embodiment of the present invention;

[0032] Figure 4 It is a standard curve and safety interval schematic diagram of a preferred embodiment provided by the present invention;

[0033] Figure 5 is a working schematic diagram of a volume measurement unit according to a preferred embodiment of the present invention;

[0034] Figure 6 It is a working schematic diagram of a timing unit according to a preferred embodiment of the present invention.

[0035] Reference numerals list

[0036] 100: activity measurement unit; 110: processor; 120: detector; 200: input unit; 210: input device; 300: analysis unit; 400: medical end; 500: medicine storage bottle; 600: volume measurement unit; 610: electrode; 700: timing unit. DETAILED DESCRIPTION

[0037] The following is a detailed description with reference to the accompanying drawings.

[0038] like Figure 1 As shown, the present invention discloses a radioactive drug dosage control system, which includes: an activity measurement unit 100, which is used to measure the current radioactivity of the drug in the target drug storage bottle 500; an input unit 200, which is used to obtain the relevant basic information of the patient currently taking the drug; an analysis unit 300, which is used to determine the volume of the drug currently injected and extracted for the patient according to the radioactivity of the drug in the current drug storage bottle 500 and the relevant basic information of the current drug taking patient. Preferably, the relevant basic information of the current drug taking patient 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 drug 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 the radioactive substance and reduce the impact on the surrounding environment and personnel, wherein the drug storage bottle 500 can be, for example, a vial and an ampoule.

[0039] Preferably, the activity measurement unit 100 relies on a high-precision radiation detector to complete the measurement of radioactivity. According to different application scenarios and technical requirements, the activity measurement unit 100 can select different types of detectors 120, such as scintillator detectors and semiconductor detectors. Preferably, the scintillator detector uses the property of a specific material (such as NaI (Tl) sodium iodine crystal) to emit fluorescence after absorbing radiation to achieve activity measurement. When the gamma rays released by the radioactive material pass through the crystal, the crystal will be stimulated to produce 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 a variety of radioactive nuclides. Preferably, semiconductor detectors, especially high-purity germanium (HPGe) detectors, are widely used in precise measurement due to their excellent energy resolution. The working principle of the HPGe detector is that under low temperature conditions, when gamma rays enter the germanium crystal, electron-hole pairs are generated. These carriers move under the action of an external electric field to form current pulses. After amplification and processing, the energy information of the rays can be obtained. Compared with scintillator detectors, HPGe detectors can more accurately distinguish rays of different energies and are particularly suitable for precise measurement of low-activity samples.

[0040] Preferably, the electrical signal generated by the detector 120 can be converted into a digital signal through 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). Furthermore, in this process, the stability and speed of signal transmission should be ensured so as to achieve real-time monitoring.

[0041] Preferably, the activity measurement unit 100 may also be equipped with a refrigeration device and a stable power supply to ensure that the detector 120 maintains optimal performance throughout the entire use cycle, especially for HPGe detectors that require a low temperature environment to work properly.

[0042] 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 in the storage area of ​​the medicine storage bottle 500, and the dedicated measurement site is as close as possible to the corresponding medicine storage bottle 500 to ensure that each sample to be tested can be correctly placed in front of the detector 120. Furthermore, in order to protect the operator from unnecessary radiation exposure, sufficient radiation shielding should be provided around the detector 120, such as lead plates or other heavy shielding materials.

[0043] Preferably, the raw signal collected by the detector 120 is sent to the processor 110 of the activity measurement unit 100 after conversion, and the signal is processed by the algorithm built into the processor 110 of the activity measurement unit 100, including noise filtering, baseline correction and other steps, so as to calculate the radioactivity of the drug. The process steps of the processor 110 of the activity measurement unit 100 for data processing can be as follows: Figure 2 shown.

[0044] 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 signal quality, wherein low-pass filtering can remove high-frequency noise, such as electromagnetic interference, etc. In radioactive activity detection, the cutoff frequency is set to filter out signals above the frequency to effectively remove electronic noise and environmental interference; median filtering can remove peak noise, such as instantaneous interference caused by cosmic rays. Median filtering can effectively remove peak noise by smoothing the median of the signal within a certain window.

[0045] Preferably, in the baseline correction step, the processor 110 of the activity measurement unit 100 can correct the baseline drift and the baseline offset respectively, wherein the baseline drift refers to the slow change of the signal baseline due to factors such as temperature change and power supply fluctuation, and the 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 a polynomial fitting method to correct the baseline drift, because in the detection of radioactivity, it can more flexibly adapt to the change of the baseline, especially in the case of a more complex baseline drift, wherein the polynomial fitting method 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 a corrected signal, thereby effectively removing the slowly changing baseline drift. Preferably, the processor 110 of the activity measurement unit 100 can use a reference signal correction method to correct the baseline drift, because it can provide higher accuracy in the detection of radioactivity, especially in the case of quantitative analysis, wherein the reference signal correction method uses a known reference signal for comparison, and adjusts the signal baseline to make it consistent with the reference signal to ensure high-precision measurement.

[0046] 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, wherein, in the detection of radioactivity, the gradient method can be used for numerical integration because it is simple to calculate and can meet the accuracy requirements in most cases.

[0047] Preferably, the processor 110 of the activity measurement unit 100 can calculate the radioactivity of the drug according to the integration result and known physical parameters, and the calculation formula is:

[0048] ,

[0049] Where A is the radioactivity in mCi; N is the counts detected in time t; ε is the detector efficiency; and t is the measurement time.

[0050] 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, which reflects the response capability of the detector 120 to rays of a specific energy and type, and the detector efficiency can usually be determined by experimental calibration. Furthermore, the processor 110 of the activity measurement unit 100 may also be provided with a calibration factor k for correcting the measurement result to compensate for the systematic errors that may exist in the measurement process, which may be derived from the characteristics of the detector 120 itself, environmental conditions, measurement methods and other factors, wherein the calibration factor may also be determined by experimental calibration. Therefore, the calculation formula for the corrected radioactivity is:

[0051] ,

[0052] Where k is the calibration factor.

[0053] Preferably, the data processed by the processor 110 of the activity measurement unit 100 can be expressed in internationally accepted radioactivity units (usually mCi) and displayed to the user through a graphical interface. Preferably, the processor 110 of the activity measurement unit 100 can be connected to the medical end 400 in communication, so that key parameters such as the currently measured activity value, reference value range, etc. can be displayed on the interface of the medical end 400, and a historical data query function can also be provided to help users understand the changing trend of 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 remind the operator to pay attention, wherein the alarm can be presented in a visual (such as a red warning light), auditory (such as a buzzer) or a combination of the two, ensuring that it can quickly attract attention even in a noisy environment. In addition, the alarm can also be reminded by the medical end 400.

[0054] Preferably, the activity measurement unit 100 can be communicatively connected with the analysis unit 300, so that the activity value currently measured by the activity detection unit can be sent to the analysis unit 300, thereby facilitating the analysis unit 300 to calculate the amount of medicine to be taken.

[0055] Preferably, in order 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 be formulated, including cleaning, inspection and replacement of damaged parts, etc., to ensure long-term stable operation of the equipment.

[0056] Preferably, in order to ensure the efficiency of the system and the accuracy of the 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 built into the medical end 400, wherein the input device 210 can be, for example, a touch screen or a keyboard. 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, and is 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 it can be a simplified keyboard specially designed for a medical environment, so as to be suitable for situations where a large amount of text information is input.

[0057] 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 may include a relational database (such as MySQL, PostgreSQL) and a NoSQL database (such as MongoDB), wherein the relational database is suitable for structured data and supports complex queries and transaction processing; the NoSQL database is suitable for unstructured or semi-structured data and supports high concurrent access and distributed storage.

[0058] Preferably, the input unit 200 can verify the accuracy of the relevant basic information input through the input device 210, for example, by setting a reasonable numerical range to limit the input data, thereby avoiding the entry of erroneous data. For example, 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.

[0059] Preferably, the data transmission between the input unit 200 and the analysis unit 300 should adopt a secure and reliable protocol, such as HTTPS, TLS, etc., to ensure the security and integrity of the data during transmission. At the same time, the system must comply with relevant medical data protection laws and regulations to ensure the security of patients' personal information.

[0060] Preferably, the analysis unit 300 may 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 volume of the drug required for the current injection extraction of the patient by calculation. Preferably, a multi-core CPU can process multiple tasks in parallel to improve computing efficiency, and a high-frequency CPU can execute a single task faster and shorten the computing time. Preferably, the analysis unit 300 may be provided with sufficient memory (e.g., at least 16GB of RAM) to store and process a large amount of data, wherein high-speed memory can increase the data reading and writing speed and improve system performance. Preferably, the analysis unit 300 may be provided with a reliable storage device to save patient data and calculation results, wherein the storage device may have a large capacity (e.g., at least 500GB) of storage space to accommodate a large number of data files and log records.

[0061] Preferably, the analysis unit 300 can achieve communication connection with the activity measurement unit 100 and the input unit 200 in a wired and / or wireless manner, wherein the wired connection may include an Ethernet connection suitable for long-distance transmission and a USB connection suitable for short-distance transmission; the wireless connection may 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 verification, the data can be pre-processed by data cleaning, format conversion and normalization to prepare for subsequent algorithm calculations, wherein data cleaning is used to remove invalid or erroneous 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.

[0062] Preferably, if Figure 3As shown, the analysis unit 300 may be built with a data lookup table summarized based on experience, and different types of radiopharmaceuticals may 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, and AV133, wherein 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 in cells, thereby showing the metabolic activity of cells in PET images. Preferably, TSPO is [18F] TSPO ligand, which is used for PET imaging, mainly for evaluating brain inflammation and neurodegenerative diseases, such as Alzheimer's disease and Parkinson's disease. TSPO ligand can bind to the translocator protein (TSPO) on mitochondria, thereby reflecting the degree of cell inflammation and damage. Preferably, AV45 is [18F]Florbetapir, which is a β-amyloid protein (Aβ) tracer for PET imaging, mainly used for the early diagnosis of Alzheimer's disease, and it can specifically bind to Aβ plaques in the brain, thereby showing the distribution of plaques in PET images. Preferably, AV133 is [18F]Flutemetamol, which is another β-amyloid protein (Aβ) tracer for PET imaging, mainly used for the diagnosis of Alzheimer's disease, and it can specifically bind to Aβ plaques in the brain, thereby showing the distribution of plaques in PET images. Exemplarily, the following is a partial data lookup table for the above four radiopharmaceuticals.

[0063]

[0064]

[0065]

[0066]

[0067] Preferably, if Figure 3 As shown, the analysis unit 300 can calculate the dose of the radiopharmaceutical according to the patient's specific physiological parameters and the specific activity of the drug, wherein the patient's specific physiological parameters can be, for example, the body surface area BSA. Preferably, the body surface area can be calculated by the following formula:

[0068] ,

[0069] Where BSA is body surface area in square meters; H is height in centimeters; W is weight in kilograms.

[0070] Preferably, once the body surface area is known, it can be used to calculate the dose of the radiopharmaceutical. Typically, the dose of a drug is given as the activity required per unit body surface area. Thus, if the recommended dose for a 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:

[0071] .

[0072] Furthermore, the recommended dose α of a drug can be determined by methods such as literature and guideline recommendations, clinical trial data and / or pharmacokinetic and pharmacodynamic models, wherein different types of drugs may have corresponding recommended doses α.

[0073] In nuclear medicine practice, the dosage calculation of radiopharmaceuticals is a key link to ensure diagnostic / therapeutic effects and patient safety. However, current technologies have obvious limitations in dealing with radiopharmaceuticals with different characteristics. On the one hand, due to the complexity of radiopharmaceuticals themselves - including but not limited to their half-life, emission particle types (such as gamma rays, beta particles), chemical properties and biodistribution characteristics, the dosage requirements of each drug are different. On the other hand, most of the existing dose calculation methods fail to fully consider the diversity of these drug characteristics, resulting in the recommended dose often being based on a fixed pattern or empirical formula, lacking a targeted correction mechanism. For example, when faced with radioisotopes with different half-lives, existing technologies are difficult to adjust in real time according to the activity of the drug changing over time; for another example, for radiopharmaceuticals with strong affinity for specific tissues, current practices do not provide sufficient flexibility to adapt to individualized diagnostic / therapeutic needs. In addition, traditional dose calculation methods usually rely on manual input of parameters and offline processing, which not only increases the risk of human error, but also limits the effective use of historical data and cannot support post-analysis and optimization.

[0074] Preferably, the analysis unit 300 of the present invention can simultaneously use the above-mentioned data lookup table and numerical calculation method to accurately determine the total activity dose D that the patient should receive, wherein for different types of radioactive drugs, 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 pre-set by the specific drug type and the diagnostic / therapeutic purpose as a coefficient, wherein the first standard curve and the second standard curve can both use the body surface area BSA as the horizontal coordinate and the total activity dose D as the vertical coordinate, thereby forming two incompletely overlapping standard curves in the same coordinate system, and a safety interval is formed by the envelope of these two standard curves.

[0075] Preferably, the total activity dose D that a patient should receive is not very accurate if it is simply determined by a data lookup table or numerical calculation. This is because the above single methods are relatively dependent on clinical experience data, but are not corrected based on the patient's individual situation, 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 may lead to problems such as poor imaging effects during PET-CT, as described in the following paper: Botkin CD, Osman MM. 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 total activity dose D obtained 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 type of medicine and the individual situation of the patient, especially to correct the calculation result of the total activity dose D by correcting the recommended dose α, and then judge whether the corrected calculation result falls into the safety interval, wherein, if the corrected calculation result falls into the safety interval, the corrected calculation result can be used as the dose of the radioactive drug; if the corrected calculation result does not fall into the safety interval, an alarm is issued, and the medical staff re-evaluates the patient carefully. Furthermore, the analysis unit 300 can set a neutral interval outside the safety interval between the two standard curves, and the neutral interval can exist as an additional safety margin to cope with potential uncertainties and changes, wherein the deviation 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 of the neutral interval from the boundary value of the safety interval can be set to ±5%~±10%, where +5%~+10% is the deviation of the upper boundary value of the neutral interval from the upper boundary value of the safety interval, -5%~-10% is the deviation of the lower boundary value of the neutral interval from the lower boundary value of the safety interval, and the area between the upper boundary value and the lower boundary value of the neutral interval minus the area of ​​the safety interval is the area of ​​the neutral interval. In scenarios where the diagnostic purpose is relatively easier, the combined interval formed by the neutral interval and the safety interval can be used as the basis for judging the corrected calculation results.

[0076] Preferably, the analysis unit 300 can correct the recommended dose α or directly correct the total activity dose D according to the drug type and the patient's personalized situation, wherein the patient's personalized situation is a physiological parameter related to the drug type, which mainly considers 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 ranked by the degree of influence to screen out one or more physiological parameters with a relatively higher degree of influence, so as to use these physiological parameters to correct the recommended dose α or the total activity dose D.

[0077] Exemplarily, the patient's blood glucose level and insulin sensitivity have a significant effect on the metabolism and enrichment of 18F-FDG (2-[18F]fluoro-2-deoxy-D-glucose); the patient's liver enzyme activity has a significant effect on the metabolism and enrichment of TSPO (translocase protein); the patient's renal clearance and blood glucose have a significant effect on the metabolism and enrichment of AV45 ([18F]Florbetapir); the patient's renal clearance and blood glucose have a significant effect on the metabolism and enrichment of AV133 ([18F]Flutemetamol). Further, the physiological parameters associated with the above four radiopharmaceuticals may include blood glucose level (BG), insulin sensitivity index (ISI), liver enzyme activity (LEA), and glomerular filtration rate (GFR), to form blood glucose level correction coefficients (C BG ), insulin sensitivity index (C ISI ), liver enzyme activity correction factor (C LEA ), glomerular filtration rate correction factor (C GFR ). Exemplarily, the above four correction coefficients can be set as:

[0078] ,

[0079] ,

[0080] ,

[0081] .

[0082] Therefore, for 18F-FDG (2-[18F]fluoro-2-deoxy-D-glucose), the total correction factor is: C 18F-FDG =C BG ×C ISI ; For TSPO (translocation protein), the total correction factor is: C TSPO =C LEA ; For AV45 ([18F]Florbetapir), the total correction factor is: C AV45 =C BG ×CGFR ; For AV133 ([18F]Flutemetamol), the 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 the individual patient situation.

[0083] like Figure 4 As shown, in a coordinate system with body surface area BSA as the horizontal coordinate and total activity dose D as the vertical coordinate, a first standard curve is generated based on the data in the corresponding data lookup table, and a second standard curve is generated based on the total activity dose formula with the standard recommended dose pre-set by the specific drug type and diagnostic purpose as the coefficient; then the first standard curve and the second standard curve are enveloping to form a safety interval; finally, the total activity dose D can be corrected according to the drug type and the individual situation of the patient to determine whether the corrected total activity dose D is above, within or below the safety interval. Further, the judgment result is that the corrected total activity dose D is within the safety interval, indicating that the corrected dose is within the recommended safety range, which means that under the given body surface area and patient characteristics, the dose is considered to be in compliance with the standard and has a reasonable balance of risks and benefits, that is, under normal circumstances, this dose is acceptable and can continue to be used. The judgment result is that the corrected total activity dose D is above the safety interval, which means that the corrected dose is higher than the recommended safety range, which may bring higher toxicity risks or adverse reactions, exceeding the safety limit of 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 potential risks, or to evaluate whether such a high dose is really needed. The judgment result is that the corrected total activity dose D is below the safety interval, which 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 enough to achieve the desired therapeutic effect. 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 staying within the safety limit. Further, the total activity dose D corrected by the above method can be used for comparison with the safety interval. Preferably, the above safety interval can also be replaced by a combined interval consisting of a neutral interval and a safety interval.

[0084] Preferably, if Figure 5As shown, the radioactive drug dosage control system of the present invention may also include a volume measurement unit 600 for measuring the current residual volume of the drug in the drug storage bottle 500, wherein the volume measurement unit 600 may use ultrasonic volume measurement technology, capacitive volume measurement technology, or optical volume measurement technology to achieve volume measurement of the drug. Further, considering that a rubber plug and aluminum foil are provided on the top of the drug storage bottle 500 containing the radioactive drug, when using ultrasonic volume measurement technology and optical volume measurement technology, the sensor needs to be vertically aligned with the liquid surface to emit ultrasonic waves or light, which is difficult to penetrate the rubber plug and aluminum foil on the top of the drug storage bottle 500, affecting the measurement accuracy. Therefore, the non-contact capacitive volume measurement technology can arrange the electrode 610 on the outside of the drug 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, which reduces the risk of contamination of the liquid and is suitable for the measurement of sensitive liquids (such as radioactive drugs). Further, as Figure 5 As shown, the electrode 610 arranged outside the medicine storage bottle 500 can be a ring electrode so as to evenly surround the bottle body.

[0085] Preferably, the analysis unit 300 can calculate the current activity concentration of the drug in the drug storage bottle 500 according to the current activity and volume of the drug in the drug storage bottle 500, and the calculation formula is:

[0086] ,

[0087] Wherein, C is the current activity concentration of the drug in the drug storage bottle 500, A is the current activity of the drug in the drug storage bottle 500, V 残余 It is the residual volume of the medicine in the medicine storage bottle 500.

[0088] Furthermore, the analysis unit 300 can calculate the volume of medicine required by the patient according to the total activity of the medicine that the patient should receive and the current activity concentration of the medicine in the medicine storage bottle 500, and the calculation formula is:

[0089] ,

[0090] Where V 所需 is the volume of medicine required by the patient, D is the total activity of the medicine that the patient should receive, and C is the current activity concentration of the medicine in the medicine storage bottle 500.

[0091] Preferably, the radioactive drug dosage control system of the present invention may be provided with a separate display unit near the storage area of ​​the drug storage bottle 500, and / or a display unit may be integrated on the medical end 400, so as to display the calculation results to the medical staff through the display unit, thereby facilitating the medical staff to manually complete the drug measurement according to the calculated drug volume required by the patient.

[0092] Preferably, the radiopharmaceutical dosage control system of the present invention may also be provided with a drug taking robot arm for automatically completing the drug dosage according to the control signal generated by the analysis unit 300, wherein the analysis unit 300 may generate a control signal for driving the drug taking robot arm according to the volume of drug required by the patient in the calculation result. Preferably, the drug taking robot arm may include a stepper motor for accurately controlling the movement of the piston to achieve the extraction of a specified volume of drug. Preferably, the drug taking robot arm may include acquisition elements such as position sensors and pressure sensors for real-time monitoring of the position and pressure of the piston. Preferably, the drug taking robot arm may include a microcontroller in communication with the analysis unit 300 to control the stepper motor and the sensor to execute the control logic according to the control signal.

[0093] Preferably, medical staff can input and modify prescription information through the operation interface of the medical 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 of important updates or alarms about drug dosage in real time.

[0094] Preferably, if Figure 6 As shown, the radioactive drug dosage control system of the present invention may be provided with a timing unit 700, which is used to start timing when the analysis unit 300 obtains the calculation result, wherein the timing unit 700 may set different interval durations for drugs of different types and states. When the set interval duration is exceeded and the drug measurement is not completed, it is judged that the drug measurement 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 maximum allowable activity loss, wherein the maximum allowable activity loss can be calculated by the analysis unit 300 according to the preset maximum error value when calculating the drug volume.

[0095] The decay formula for radiopharmaceuticals is:

[0096] ,

[0097] Where 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 time, and e is the base of the natural logarithm.

[0098] Decay constant λ and half-life T 1 / 2 The relationship is:

[0099] .

[0100] Therefore, the timing unit 700 can set the interval duration according to the following formula:

[0101] ,

[0102] Where, T 1 / 2 is 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.

[0103] For example, if the maximum allowable activity loss is simply set to 0.03A, it can be calculated that drugs such as 18F-FDG with a half-life of 110 minutes need to be taken within about 5 minutes after the analysis unit 300 outputs the calculation result; drugs such as 68Ga with a half-life of 68 minutes need to be taken within about 3 minutes after the analysis unit 300 outputs the calculation result.

[0104] The radioactive drug dosage control system provided with a timing unit 700 of the present invention is particularly suitable for drugs with a short half-life. Such drugs have extremely high requirements for dosage accuracy when used. Therefore, the timing unit 700, which can flexibly set an appropriate interval length 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 requirement.

[0105] Preferably, the radioactive drug dosage control system of the present invention may be provided with a radioactive surface contamination measuring device to measure the radioactive residue on the table where the medicine storage bottle 500 is located to ensure the safety of the operating environment. Through real-time monitoring, radioactive contamination can be discovered and handled in time to avoid environmental pollution and radiation hazards to operators. Preferably, the radioactive surface contamination measuring device can use a Geiger-Müller (GM) counter or a semiconductor detector, wherein 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 and generate electrical signals. The GM counter has a high sensitivity to α and β particles; the semiconductor detector (such as a silicon PIN detector) measures the radioactivity 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 device can be installed near the table where the medicine storage bottle 500 is located to ensure that the entire operating area is covered. Preferably, the data obtained by the radioactive surface contamination measuring device can be sent to the analysis unit 300 for data processing to judge the radioactive residue on the table through the threshold set by the analysis unit 300, and when the radioactivity level exceeds the threshold, an alarm is triggered.

[0106] It should be noted that the above-mentioned specific embodiments are exemplary, and those skilled in the art can come up with various solutions inspired by the disclosure of the present invention, and these solutions also belong to the disclosure scope of the present invention and fall within the protection scope of the present invention. Those skilled in the art should understand that the present invention specification and its drawings are illustrative and do not constitute a limitation of the claims. The scope of protection of the present invention is defined by the claims and their equivalents. The present invention specification contains multiple inventive concepts, such as "preferably" or "according to a preferred embodiment", which means that the corresponding paragraph discloses an independent concept, and the applicant reserves the right to file a divisional application based on each inventive concept. Throughout the text, the features guided by "preferably" are only an optional method and should not be understood as a must-have setting. Therefore, the applicant reserves the right to abandon or delete the relevant preferred features at any time.

Claims

1. A radiopharmaceutical dosage control system, characterized in that: It includes: An activity measurement unit (100) for measuring the current radioactivity of the medicine in the target medicine storage bottle (500); An input unit (200) is used to obtain relevant basic information of a patient currently taking medication, wherein the relevant basic information includes the patient's weight information and height information; The analysis unit (300) is used to determine the volume of the medicine currently injected and extracted for the patient according to the radioactivity of the medicine in the current medicine storage bottle (500) and the relevant basic information of the patient currently taking the medicine.

2. The system according to claim 1, characterized in that The activity measurement unit (100) is configured by arranging a corresponding detector (120) at a dedicated measurement site close to a corresponding medicine storage bottle (500) in a storage area of ​​the medicine storage bottle (500); the original signal collected by the detector (120) is converted and sent to the processor (110) of the activity measurement unit (100), so as to calculate the radioactivity of the medicine 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 signal using a gradient method to obtain the total energy or total count of the signal, and then calculates the radioactivity of the drug based on the integration result and physical parameters, wherein the physical parameters include detector efficiency and / or calibration factor.

4. The system according to claim 3, characterized in that The data processed by the processor (110) of the activity measurement unit (100) can be displayed to the user through a graphical interface, wherein the processor (110) of the activity measurement unit (100) can be connected to the medical end (400) for communication, so that the interface of the medical end (400) can display key parameters including the currently measured activity value and the reference value range, and provide a historical data query function.

5. The system according to claim 1, characterized in that The input unit (200) can be configured with a digital input device (210), and the input unit (200) can verify the accuracy of the relevant basic information input through the input device (210) by setting the numerical range of the 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, characterized in that After receiving the current radioactivity of the drug in the current drug storage bottle (500) sent by the activity measurement unit (100) and the relevant basic information of the patient currently taking the drug sent by the input unit (200), the analysis unit (300) can determine the volume of the drug currently injected and extracted by retrieving a built-in data lookup table corresponding to different types of radioactive drugs summarized based on experience, and / or can determine the volume of the drug currently injected and extracted by numerical calculation based on the patient's specific physiological parameters and the specific activity of the drug.

7. The system according to claim 6, characterized in that When the analysis unit (300) determines the volume required for the current injection of the drug by numerical calculation, the patient-specific physiological parameters selected include the body surface area calculated based on the patient's height information and weight information, and the total active dose that the patient should receive is calculated based on the obtained body surface area in combination with the recommended dose of the corresponding drug.

8. The system according to claim 1 or 7, characterized in that: It comprises a volume measurement unit (600) for measuring the current residual volume of a drug in a drug storage bottle (500), wherein the volume measurement unit (600) can arrange electrodes (610) outside the corresponding drug storage bottle (500), so that the analysis unit (300) can use the residual volume of the drug obtained by the volume measurement unit (600) based on the capacitive volume measurement technology to calculate the volume of the drug required by the patient.

9. The system according to claim 1, characterized in that It comprises a timing unit (700) for starting timing when the analysis unit (300) obtains a calculation result. The timing unit (700) can set different interval lengths for drugs of different types and states. When the set interval length is exceeded and the drug measurement is not completed, it is judged that the 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.

10. The system according to claim 9, characterized in that 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 maximum allowable activity loss, wherein the maximum allowable activity loss can be calculated by the analysis unit (300) according to a preset maximum error value when calculating the drug volume.

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