A boron neutron capture therapy online dose monitoring alarm system and method

Abstract

This invention discloses an online dose monitoring and alarm system and method for boron neutron capture therapy, belonging to the field of radiation dose monitoring technology. It includes at least one set of integrated wireless monitoring probes and a central monitoring platform. The system highly integrates a radiation detection module, a photoelectric conversion module, a high-speed analog-to-digital / digital-to-analog conversion module, an FPGA module, a wireless communication module, and a built-in lithium battery. The FPGA executes a shape discrimination algorithm based on the difference between pulse rise time and / or decay time at the probe end using hardware logic to distinguish neutron / gamma events and calculate the count rate and dose rate in real time. When the monitored value exceeds a preset safety threshold, the high-speed digital-to-analog conversion module drives an LED indicator and / or a buzzer to issue a local audible and visual alarm. Compared with existing technologies, this invention achieves synchronous real-time monitoring of neutron flux and gamma dose, improves alarm response speed, facilitates flexible deployment near the treatment head or patient irradiation field in space-constrained locations, and enhances the safety and accuracy of treatment.

Description

Technical Field

[0001] This invention relates to the field of radiation dose monitoring technology, and more specifically, to an online dose monitoring and alarm system and method for boron neutron capture therapy. Background Technology

[0002] Boron neutron capture therapy, as an advanced binary targeted radiotherapy technique, relies heavily on precise control of the neutron beam and real-time dose monitoring for its therapeutic efficacy and safety. In clinical applications, existing monitoring systems face multiple technical challenges. Most systems can only monitor either neutrons or gamma rays, failing to achieve simultaneous real-time monitoring of neutron flux and gamma dose during treatment, resulting in an inability to comprehensively assess the actual radiation dose received by the patient. When neutron or gamma ray anomalies occur in the irradiation system, existing mechanisms lack rapid automatic response capabilities, relying on manual judgment, leading to delayed responses and potential safety hazards of insufficient or excessive radiation dose. Traditional monitoring systems use wired connections, resulting in complex wiring that occupies treatment room space and limits the flexible movement and installation of equipment, especially in multi-field treatment scenarios where deployment is difficult to adjust. Detectors are generally large and fixed in location, making flexible placement near the treatment head or patient irradiation field in space-constrained environments difficult, affecting the normal operation of the original treatment equipment and clinical workflow. The distributed design of signal acquisition, processing, and transmission modules lacks integrated high-speed data processing capabilities, resulting in slow system response speeds and an inability to meet real-time monitoring and alarm requirements. The closest existing technology uses a wired silicon diode detector for beam monitoring. While it can measure basic neutron flux, its functionality is limited and cannot deeply integrate neutron and gamma ray monitoring. The alarm mechanism is simplistic and has high latency. The wired connection exacerbates wiring problems, the detector is bulky and difficult to place close to critical monitoring locations, and low system integration results in a lengthy data processing chain. These shortcomings collectively restrict the safety and accuracy of boron neutron capture therapy, necessitating the development of novel monitoring solutions.

[0003] To address the aforementioned issues, existing technologies urgently need improvement. Summary of the Invention

[0004] The purpose of this invention is to provide an online dose monitoring and alarm system and method for boron neutron capture therapy, which has the advantages of enabling synchronous real-time monitoring of neutron flux and gamma dose, improving alarm response speed, reducing wiring hassles, and facilitating flexible deployment.

[0005] This invention provides an online dose monitoring and alarm system for boron neutron capture therapy, the technical solution of which is as follows: Includes at least one set of integrated wireless monitoring probes and a central monitoring platform; The integrated wireless monitoring probe includes a radiation detection module, a photoelectric conversion module, a high-speed analog-to-digital conversion module, a high-speed digital-to-analog conversion module, a field-programmable gate array (FPGA) module, a wireless communication module, and a power supply module. The radiation detection module consists of a group of three probes: a background light signal probe, a gamma-ray light signal probe, and a neutron light signal probe. The photoelectric conversion module is used to convert optical signals into electrical signals; High-speed analog-to-digital converter modules are used to convert electrical signals into digital signals; The FPGA module is connected to the high-speed analog-to-digital converter module and the wireless communication module, and is configured to perform pulse shape discrimination on digital signals to distinguish between neutron events and gamma events, and to perform count rate calculation and dose rate calculation. The wireless communication module is used to send the result data processed by the FPGA module to the central monitoring platform.

[0006] Furthermore, this invention also proposes that the neutron optical signal probe in the radiation detection module adopts a boron-containing polystyrene scintillator. 6 The gamma-ray optical signal probe uses at least one of Li glass scintillator or plastic scintillator, and employs LaBr3(Ce) scintillator or GAGG scintillator.

[0007] Furthermore, the present invention also proposes that the photoelectric conversion module includes a photomultiplier tube (PMT) or a silicon photomultiplier tube (SiPM).

[0008] Furthermore, the present invention also proposes that the FPGA module be configured to perform a pulse shape discrimination algorithm based on the difference between the rise time and / or decay time of the pulse waveform.

[0009] Furthermore, the present invention proposes that the FPGA module has a preset safety threshold and is configured to drive an LED indicator and / or a buzzer to issue an audible and visual alarm when the neutron count rate or gamma dose rate exceeds the safety threshold, and send an alarm signal to the central monitoring platform through a high-speed digital-to-analog converter module.

[0010] Furthermore, the present invention proposes that the wireless communication module only transmits the simplified result data processed by the FPGA module, and the simplified result data includes neutron count rate, gamma dose rate and alarm status.

[0011] Furthermore, the present invention proposes that the power module is a built-in rechargeable lithium battery; the integrated wireless monitoring probe is packaged as a cylindrical structure with a diameter of 4-5 cm and a length of 5-8 cm, with 3 probes at the front end and a signal antenna and data interface at the rear end; the system includes multiple integrated wireless monitoring probes forming a distributed monitoring network.

[0012] Furthermore, the present invention also proposes an online dose monitoring and alarm method, which involves running the above-mentioned system for monitoring, including the following steps: The three probes based on the radiation detection module detect the background light signal, the light signal generated by gamma rays, and the light signal generated by neutrons, respectively. Optical signals are converted into electrical signals based on a photoelectric conversion module; Electrical signals are converted into digital signals based on a high-speed analog-to-digital converter module; The FPGA module at the probe end performs pulse shape discrimination on the digital signal to distinguish between neutron events and gamma events, and calculates the neutron count rate and gamma dose rate. When an abnormal dose is detected, the high-speed digital-to-analog converter at the probe end drives the LED indicator and / or the buzzer to issue an alarm. The processed data is sent to the central monitoring platform via a wireless communication module.

[0013] Furthermore, the present invention also proposes that the step of the FPGA module at the probe end performing pulse shape identification on the digital signal to distinguish between neutron events and gamma events, and calculating the pulse shape identification in the neutron count rate and gamma dose rate is performed by the FPGA module at the hardware logic level.

[0014] Furthermore, the present invention also proposes that the FPGA module has a preset safety threshold, and the anomaly detection includes comparing the calculated neutron count rate or gamma dose rate with the safety threshold.

[0015] As can be seen from the above, the present invention provides an online dose monitoring and alarm system and method for boron neutron capture therapy, including an integrated wireless monitoring probe and a central monitoring platform. Through real-time signal processing and wireless transmission, it solves the problems of incomplete monitoring and response delay in the prior art. It has the advantages of being able to realize synchronous real-time monitoring of neutron flux and gamma dose, improving alarm response speed, reducing wiring troubles, and facilitating flexible deployment. Attached Figure Description

[0016] Figure 1 This is a schematic diagram of the internal structure of an online dose monitoring and alarm system for boron neutron capture therapy. Figure 2 This is a schematic diagram of the external structure of an online dose monitoring and alarm system for boron neutron capture therapy. Figure 3 A topology diagram of the modules of an online dose monitoring and alarm system for boron neutron capture therapy; Figure 4 A schematic diagram of a single gamma and neutron probe structure in an online dose monitoring and alarm system for boron neutron capture therapy; Figure 5A schematic diagram of the algorithm logic framework of the detection module in an online dose monitoring and alarm system for boron neutron capture therapy. Figure 6 This is a flowchart illustrating an online dose monitoring and alarm method. Detailed Implementation

[0017] The technical solutions of this invention will now be clearly and completely described with reference to the accompanying drawings. Obviously, the described embodiments are merely some, not all, of the embodiments of this invention. The components of this invention described and shown in the accompanying drawings can generally be arranged and designed in various different configurations. Therefore, the following detailed description of the embodiments of the invention provided in the drawings is not intended to limit the scope of the claimed invention, but merely to illustrate selected embodiments of the invention. All other embodiments obtained by those skilled in the art based on the embodiments of this invention without inventive effort are within the scope of protection of this invention.

[0018] It should be noted that similar reference numerals and letters in the following figures indicate similar items; therefore, once an item is defined in one figure, it does not need to be further defined and explained in subsequent figures. Furthermore, in the description of this invention, terms such as "first," "second," etc., are used only to distinguish descriptions and should not be construed as indicating or implying relative importance.

[0019] In the clinical application of boron neutron capture therapy systems, the following issues arise: Limited monitoring capability: Existing systems can only monitor either neutrons or gamma rays, failing to achieve simultaneous real-time monitoring of neutron flux and gamma dose. This results in an inability to fully assess the actual radiation dose received by the patient. Delayed anomaly response: When anomalies occur in the irradiation system, there is a lack of rapid, automatic alarm mechanisms, relying on manual judgment by operators. This delayed response may lead to medical risks of insufficient or excessive radiation dose. Complex system deployment: Traditional monitoring systems use wired connections, resulting in numerous cables in the treatment room, occupying space and affecting cleanliness, limiting the flexibility of equipment movement and installation, especially in multi-field treatments. Inconvenient installation and space occupation: Due to the large size of the detectors and their fixed installation locations, flexible deployment near the treatment head or patient irradiation field is difficult, potentially affecting the normal operation of the original treatment equipment and clinical workflow. Dispersed data processing: Signal acquisition, processing, and transmission modules are scattered, lacking an integrated high-speed data processing pipeline, resulting in slow system response and an inability to achieve true real-time monitoring and alarm.

[0020] For example, during head and neck tumor treatment in a BNCT treatment room, the space around the treatment head is limited. Traditional detectors are too bulky to be installed in key locations close to the patient's body surface and can only be placed in a distant area. At the same time, the messy system wiring interferes with the operation process of medical staff. When abnormal fluctuations occur in the beam, the monitoring system only outputs neutron flux data and ignores changes in gamma dose. Moreover, the alarm response is delayed, and the operator fails to detect and intervene in time, resulting in dose calculation deviations, which affect the accuracy of treatment and patient safety.

[0021] If the above problems are not addressed, incomplete radiation dose assessment will lead to inaccurate treatment plan execution and increase the risk of damage to normal tissues; abnormal response delays may cause uncontrolled radiation doses and lead to serious medical accidents; complex system deployment and inconvenient installation will limit the widespread application of monitoring systems, especially in space-constrained treatment environments; and response delays caused by fragmented data processing will render real-time monitoring ineffective, failing to guarantee the safety and effectiveness of the treatment process.

[0022] In this regard Figure 1 , 2 As shown, the present invention proposes An online dose monitoring and alarm system for boron neutron capture therapy. Includes at least one set of integrated wireless monitoring probes 100 and a central monitoring platform; The integrated wireless monitoring probe 100 includes a radiation detection module 101, a photoelectric conversion module 102, a high-speed analog-to-digital conversion module 103A, a high-speed digital-to-analog conversion module 103B, a field-programmable gate array (FPGA) module 104, a wireless communication module 105, and a power supply module 106. The radiation detection module 101 includes a structure consisting of three probes: a background light signal probe, a gamma ray light signal probe, and a neutron light signal probe. The photoelectric conversion module 102 is used to convert optical signals into electrical signals; The high-speed analog-to-digital converter module 103A is used to convert electrical signals into digital signals; The FPGA module is connected to the high-speed analog-to-digital converter module 103A and the wireless communication module 105, and is configured to perform pulse shape discrimination on digital signals to distinguish between neutron events and gamma events, and to perform count rate calculation and dose rate calculation. The wireless communication module 105 is used to send the result data processed by the FPGA module to the central monitoring platform.

[0023] A central monitoring platform is a central system used to receive, display, store, and analyze data transmitted from one or more integrated wireless monitoring probes. This platform typically has a user interface that can present monitoring data and alarm information in real time and support the querying and management of historical data, as shown in the figure.

[0024] This embodiment proposes an online dose monitoring and alarm system for boron neutron capture therapy, which is designed to solve the problems of limited monitoring capabilities, delayed abnormal response, complex system deployment, inconvenient installation and space occupation, and scattered data processing in the prior art.

[0025] like Figure 3 As shown, the system includes at least one set of integrated wireless monitoring probes 100 and a central monitoring platform. The integrated wireless monitoring probes 100 are responsible for acquiring radiation data in real time at the treatment site and performing preliminary processing, while the central monitoring platform is responsible for receiving, displaying, and managing the data from the probes. As one implementation, the integrated wireless monitoring probes 100 can be placed at multiple key locations in the treatment area, such as near the treatment head or the patient's body surface, to obtain precise information about the local radiation field. The central monitoring platform can be a standalone computer system that displays real-time monitoring results to operators through a graphical user interface.

[0026] The integrated wireless monitoring probe 100 internally integrates a radiation detection module 101, a photoelectric conversion module 102, a high-speed analog-to-digital converter module 103A, a high-speed digital-to-analog converter module 103B, a field-programmable gate array (FPGA) module 104, a wireless communication module 105, and a power supply module 106. This highly integrated design allows the probe to operate as a standalone intelligent node without the need for complex external cabling. For example, all these modules can be packaged in a compact housing, forming a portable and deployable unit.

[0027] Among them, such as Figure 4 As shown, the radiation detection module 101 comprises a group of three probes: a background light signal probe, a gamma-ray light signal probe, and a neutron light signal probe. This multi-probe configuration allows the system to simultaneously monitor different types of signals. For example, the background light signal probe can employ a radiation-insensitive photosensitive element to measure ambient light intensity; the gamma-ray light signal probe can employ a scintillator material sensitive to gamma rays; and the neutron light signal probe can employ a scintillator material sensitive to neutrons. In this way, simultaneous detection of different types of radiation can be achieved, and radiation signals can be effectively distinguished from environmental noise.

[0028] The detector provided by this invention is often installed at the beam outlet, such as the BSA outlet, collimator outlet, etc.

[0029] The photoelectric conversion module 102 is used to convert the optical signal generated by the radiation detection module 101 into an electrical signal. This module can employ photoelectric conversion elements such as a photodiode array or a photomultiplier device. For example, when a scintillator material emits weak photons under radiation, the photoelectric conversion module 102 can capture these photons and convert them into current or voltage pulses that can be processed by electronic circuits.

[0030] The high-speed analog-to-digital converter module 103A is used to convert the electrical signal output from the photoelectric conversion module 102 into a digital signal. The conversion rate and resolution of this module are crucial for capturing the fine waveform of the radiation pulse. For example, a high-speed analog-to-digital converter module 103A can convert an analog voltage signal into a series of digital values ​​at a rate of hundreds of millions of samples per second, thereby preserving key information such as the rising edge, falling edge, and amplitude of the pulse.

[0031] The FPGA module is connected to the high-speed analog-to-digital converter module 103A and the wireless communication module 105. The FPGA module is configured to perform pulse shape discrimination on digital signals to distinguish between neutron and gamma events, and to calculate the count rate and dose rate. The FPGA's hardware parallel processing capability enables it to analyze the digital pulse waveforms output by the high-speed analog-to-digital converter module 103A in real time. For example, through a preset algorithm, the FPGA can identify the shape differences in the pulse waveforms generated by neutrons and gamma rays in the detector, thereby distinguishing them. After differentiation, the FPGA counts the respective events and calculates the neutron count rate and gamma dose rate according to a preset conversion factor. While conventional solutions have a response time of approximately 1 second, the solution provided by this invention, through FPGA computation, can complete the response within 30-50 milliseconds.

[0032] The wireless communication module 105 is used to send the processed data from the FPGA module to the central monitoring platform. This module can employ various wireless communication technologies, such as short-range radio transmission or cellular network communication. For example, the FPGA module packages calculated data such as count rate and dose rate into concise data frames, which are then transmitted via the wireless communication module 105. This "calculate-before-transmit" mode significantly reduces the amount of data that needs to be transmitted, thereby reducing the bandwidth requirements and latency of wireless transmission.

[0033] The power module 106 provides power to all the electronic components within the integrated wireless monitoring probe 100. This module can use a disposable or rechargeable battery. For example, a built-in battery pack can provide the probe with several hours or days of independent operation, ensuring continuous monitoring capability during treatment.

[0034] The following example will provide a more detailed explanation of the above technical solution: During boron neutron capture therapy, it is necessary to monitor the neutron flux and gamma dose within the patient's irradiation field in real time to ensure the safety and effectiveness of the treatment. Traditional monitoring systems, due to their wired connections, large size, and limited data processing capabilities, are difficult to deploy flexibly in the treatment area and provide immediate feedback.

[0035] To address this issue, the present invention proposes an online dose monitoring and alarm system for boron neutron capture therapy. Specifically, in the treatment room, multiple integrated wireless monitoring probes 100 are placed at several key locations near the patient's irradiation area. Each integrated wireless monitoring probe 100 operates as an independent monitoring node.

[0036] When the BNCT beam begins irradiation, neutrons and gamma rays enter the radiation detection module 101 of the integrated wireless monitoring probe 100. The neutron light signal probe, gamma ray light signal probe, and background light signal probe within this module operate synchronously. For example, the neutron light signal probe captures the light signal generated by the interaction of neutrons with the detection medium, the gamma ray light signal probe captures the light signal generated by the interaction of gamma rays with the detection medium, and the background light signal probe is used to monitor ambient light to subtract environmental interference in subsequent processing.

[0037] The captured optical signals are then transmitted to the photoelectric conversion module 102. The photoelectric conversion module 102 rapidly converts these weak optical signals into corresponding analog electrical signals. For example, a photoelectric conversion device converts each photon event into an electrical pulse with a specific waveform.

[0038] Next, these analog electrical signals are fed into the high-speed analog-to-digital converter module 103A. The high-speed analog-to-digital converter module 103A converts the analog electrical signals into digital signals with extremely high sampling rate and resolution. For example, the complete waveform of each electrical pulse, including its rising edge, falling edge, and peak value, is precisely digitized into a series of discrete digital points.

[0039] These digital signals are then transmitted to the FPGA module. The FPGA module, the "brain" of the probe, has pre-configured hardware logic circuitry. The FPGA module first performs a pulse shape discrimination algorithm on the received digital signals. By analyzing the waveform characteristics of each digital pulse, the FPGA module can accurately distinguish in real time which pulses are caused by neutron events and which by gamma events. For example, pulses generated by neutron events may have a longer decay time, while pulses generated by gamma events may have a shorter decay time; the FPGA module uses these differences for discrimination. After distinguishing between neutron and gamma events, the FPGA module counts them separately and calculates the current neutron count rate and gamma dose rate in real time based on preset calibration coefficients.

[0040] After completing the count rate and dose rate calculations, the FPGA module transmits the processed results, such as neutron count rate and gamma dose rate, to the central monitoring platform located outside the treatment room via the wireless communication module 105. The wireless communication module 105 uses radio waves for data transmission, avoiding the complex wiring of traditional wired connections.

[0041] Meanwhile, the power module 106 within the integrated wireless monitoring probe 100 provides a stable power supply to all the aforementioned components, ensuring the probe's continuous operation throughout the entire treatment process.

[0042] After receiving data from each integrated wireless monitoring probe 100, the central monitoring platform displays these monitoring results in real time on the screen interface, such as showing the dynamic changes in neutron count rate and gamma dose rate in chart or numerical form. Operators can gain a comprehensive understanding of the radiation dose distribution in the treatment area through the central monitoring platform.

[0043] Thus, by highly integrating radiation detection, signal conversion, high-speed processing, and wireless transmission functions into the probe, this system achieves synchronous, real-time, and accurate monitoring of neutrons and gamma rays during BNCT treatment. It can also wirelessly transmit the processed and simplified data to the central monitoring platform, thereby solving the problems of traditional systems such as limited monitoring capabilities, scattered data processing, complex system deployment, and inconvenient installation.

[0044] In some embodiments of the present invention described above, a radiation detection module 101 is proposed for detecting optical signals. However, in its implementation, it is necessary to specifically select a suitable scintillator material to ensure efficient differentiation and accuracy of neutron detection and gamma detection, and to avoid signal confusion or insufficient sensitivity due to improper material selection, thereby affecting the accuracy of subsequent pulse shape identification and dose calculation.

[0045] To address this, the present invention further proposes that the neutron optical signal probe in the radiation detection module 101 adopts a boron-containing polystyrene scintillator. 6 The gamma-ray optical signal probe uses at least one of Li glass scintillator or plastic scintillator, and employs LaBr3(Ce) scintillator or GAGG scintillator.

[0046] The neutron optical signal probe is specifically designed to detect neutron radiation, generating an optical signal through the interaction between neutrons and the scintillator material. Its function is to convert undetectable neutron radiation into an optical signal that can be captured by the photoelectric conversion module 102, forming the basis for neutron event identification and counting. The boron-containing polystyrene scintillator, by incorporating boron into a polystyrene matrix, utilizes the neutron capture reaction of the boron-10 nucleus to generate charged particles, thereby exciting the scintillator to emit light, exhibiting high sensitivity to thermal neutrons. 6Li glass scintillators are inorganic scintillators enriched with lithium-6 isotopes. The charged particles generated by the reaction of lithium-6 nuclei with neutrons excite the glass matrix to emit light, exhibiting extremely high detection efficiency for thermal neutrons. Plastic scintillators are typically made of polymers such as polystyrene or polyethylene doped with fluorescent materials. They generate recoil protons through the elastic scattering of neutrons with hydrogen nuclei, which excite the scintillator to emit light, showing good response to fast neutrons. Gamma-ray optical signal probes are specifically designed to detect gamma rays, generating optical signals through the interaction between gamma rays and the scintillator material. Their function is to convert gamma-ray energy into optical signals that can be captured by the photoelectric conversion module 102, forming the basis for gamma event identification and dose calculation. LaBr3(Ce) scintillators are cerium-doped lanthanum bromide inorganic scintillators with extremely high light output, excellent energy resolution, and very fast decay time, making them outstanding in gamma spectroscopy measurements and high count rate applications. GAGG scintillators are cerium-doped gadolinium aluminum gallium garnet inorganic scintillators with high density, high light output, good energy resolution, and relatively fast decay time. They are stable and not prone to deliquescence in gamma-ray detection.

[0047] As a specific implementation, the radiation detection module 101 in the integrated wireless monitoring probe 100 can be configured such that the neutron optical signal probe can be a miniaturized unit. 6 A Li glass scintillator, which exhibits high detection efficiency for thermal neutrons, can be used as the gamma-ray optical signal probe. A miniaturized LaBr3(Ce) scintillator, with its high light output and rapid decay characteristics, can facilitate accurate identification of gamma events. Furthermore, to detect the background optical signal, a photoelectric converter without a scintillator can be used, or a radiation-insensitive transparent material can be used as the background optical signal probe. These probes can be closely arranged or encapsulated within the radiation detection module 101, ensuring they can simultaneously receive signals from the same radiation field. Each probe's photoelectric conversion module 102 converts the optical signal into an electrical signal, which is then digitized by the high-speed analog-to-digital converter module 103A.

[0048] Through the above technical solution, this invention significantly improves the system's ability to distinguish between neutrons and gamma rays and enhances detection accuracy by optimizing the selection of scintillator materials in the radiation detection module 101. The neutron optical signal probe uses a highly specific neutron scintillator, ensuring efficient capture and accurate identification of neutron events and avoiding the omission of neutron signals or confusion with gamma signals. The gamma ray optical signal probe uses a high-output, fast-attenuation scintillator, guaranteeing clear detection of gamma events and precise waveform feature extraction. This refined material selection provides high-quality raw signals for subsequent pulse shape identification in the FPGA module, thereby making the calculation of neutron count rate and gamma dose rate more accurate and reliable. Ultimately, this solution effectively overcomes the limitations of traditional monitoring systems in scintillator material selection, ensuring comprehensive, real-time, and accurate monitoring of key radiation doses during boron neutron capture therapy, greatly improving the safety and effectiveness of the treatment.

[0049] In some embodiments of the present invention described above, a photoelectric conversion module 102 is proposed to convert optical signals into electrical signals. However, in its implementation, traditional photoelectric converters, such as photomultiplier tubes, are large in size and consume a lot of power, which is not conducive to achieving system miniaturization and portability, and limits flexible deployment in space-constrained treatment environments. Therefore, the present invention further proposes that the photoelectric conversion module 102 includes a photomultiplier tube (PMT) or a silicon photomultiplier tube (SiPM).

[0050] A photomultiplier tube (PMT) is a highly sensitive photodetector that utilizes the photoelectric effect and secondary electron emission to convert weak light signals into measurable electrical signals. When a photon strikes a photocathode, it emits photoelectrons. These photoelectrons are accelerated by an electric field and bombard a series of dynamo electrodes. Each bombardment generates more secondary electrons, thus multiplying the current. PMTs have extremely high gain and fast response speed, capable of detecting single photons, making them advantageous in scenarios requiring high-sensitivity detection. Implementation can include using compact side-window or end-window PMTs with integrated voltage divider circuits. A silicon photomultiplier tube (SiPM) is a solid-state photodetector based on semiconductor technology, composed of a large array of avalanche photodiodes (APDs) operating in Geiger mode. Each micro-element can independently detect photons and generate a standardized electrical pulse upon detection. SiPMs offer advantages such as small size, low power consumption, insensitivity to magnetic fields, low operating voltage, and good mechanical stability, making them ideal for integration into miniaturized devices. The implementation can include using SiPM arrays of different sizes and pixel densities, and integrating corresponding bias circuits and signal readout circuits.

[0051] The present invention configures the photoelectric conversion module 102 in the integrated wireless monitoring probe 100 to include a photomultiplier tube (PMT) or a silicon photomultiplier tube (SiPM), thereby efficiently and accurately converting the weak light signal generated by the radiation detection module 101 into an electrical signal. Specifically, when the scintillator material in the radiation detection module 101 interacts with neutrons or gamma rays to generate scintillation light, these light signals are received by the photoelectric conversion module 102. If a silicon photomultiplier tube (SiPM) is used, its small size and low power consumption allow it to be tightly integrated after the radiation detection module 101, forming a highly integrated miniature detection unit, which is crucial for miniaturizing the entire integrated wireless monitoring probe 100. Simultaneously, the insensitivity of SiPM to magnetic fields allows it to operate stably in boron neutron capture therapy (BNCT) environments (where magnetic field interference may exist), ensuring the reliability of signal conversion. If a photomultiplier tube (PMT) is used, its high sensitivity allows even extremely weak scintillation light to be effectively captured and converted into an electrical signal, ensuring the accuracy of detection. Whether it's a PMT or a SiPM, the output electrical signal is then received by the high-speed analog-to-digital converter module 103A and converted into a digital signal, providing a data foundation for subsequent FPGA modules to perform pulse shape identification and count rate and dose rate calculations. This selective use of either a PMT or SiPM configuration allows the system to be optimized for different requirements in terms of sensitivity, size, power consumption, and resistance to magnetic field interference based on actual application scenarios. This effectively solves the problems of large size and high power consumption of traditional photoelectric converters while ensuring signal conversion quality, thereby supporting the miniaturization of the integrated wireless monitoring probe 100 and its flexible deployment in limited spaces.

[0052] Traditional boron neutron capture therapy (BNCT) systems suffer from problems during monitoring. An FPGA module was proposed to perform pulse shape discrimination on digital signals to distinguish between neutron and gamma events. However, ambiguity in the discrimination algorithm can lead to low efficiency and insufficient accuracy, affecting the real-time calculation of neutron count rate and gamma dose rate, and consequently delaying anomaly detection and alarm response.

[0053] To address this, the present invention further proposes an FPGA module configured to execute a pulse shape discrimination algorithm based on the difference between the rise time and / or decay time of the pulse waveform. An FPGA module is a semiconductor device integrating a large number of programmable logic units, memory, and digital signal processing (DSP) modules. Its core feature is that its hardware logic can be configured and reconfigured according to design requirements, thereby achieving highly parallel data processing capabilities and extremely low latency. In the field of radiation detection, FPGA modules can be used for high-speed data acquisition, real-time signal processing, pattern recognition, and control logic implementation. The rise time of a pulse waveform refers to the time required for the pulse signal to reach a certain percentage (e.g., 10%) of its peak amplitude before reaching another percentage (e.g., 90%). The decay time refers to the time required for the pulse signal to decrease from its peak amplitude to a certain percentage (e.g., 90%) before decreasing to another percentage (e.g., 10%). In scintillator detectors, different types of radiation particles (such as neutrons and gamma rays) interact with the scintillator material, exciting the scintillator to generate light pulses with different time characteristics. Neutron events typically produce light pulses with fast rise times but long decay times, while gamma events may produce light pulses with slow rise times but short decay times, or the two may have significant differences in decay times. These differences form the physical basis for distinguishing different radiation events. Pulse Shape Discrimination (PSD) algorithms are a technique that uses the differences in the temporal characteristics of detector output pulse waveforms to distinguish different types of particle events. This algorithm analyzes the shape characteristics of the pulse, such as rise time, decay time, pulse integral value, or its ratio, to determine the type of particle causing the pulse. Common PSD algorithms include the Charge Comparison Method (CCM), the Zero-Crossing Method (ZCM), and digital filtering. These algorithms can be implemented in the hardware logic of an FPGA module by processing the digital signal output from the high-speed analog-to-digital converter module 103A in real time, extracting pulse shape characteristics, and classifying them according to a preset discrimination threshold.

[0054] The present invention assigns the execution task of the pulse shape identification algorithm to the FPGA module and explicitly defines its identification basis as the difference in rise time and / or decay time of the pulse waveform, thereby achieving rapid and accurate differentiation between neutron events and gamma events at the hardware level. Specifically, in the integrated wireless monitoring probe 100, when the scintillator in the radiation detection module 101 is subjected to neutrons or gamma rays, it generates optical signals with different time characteristics. These optical signals are converted into electrical signals by the photoelectric conversion module 102, and then converted into digital signals by the high-speed analog-to-digital conversion module 103A. Subsequently, these digital signals are sent to the FPGA module. The FPGA module utilizes its highly parallel processing capabilities to analyze the rise time and / or decay time of each digital pulse waveform in real time. Since the pulse waveforms generated by neutron events and gamma events in the scintillator have inherent time characteristic differences, the FPGA module can determine whether the pulse is caused by a neutron or a gamma ray in a very short time based on these differences using a preset pulse shape identification algorithm. This real-time identification based on hardware logic avoids the delay of traditional software processing and ensures that neutron events and gamma events can be classified efficiently and accurately. Once the event type is identified, the FPGA module can immediately perform the corresponding count rate and dose rate calculations, providing accurate and real-time input data for subsequent anomaly detection and alarms. This processing method greatly improves the response speed and data accuracy of the entire monitoring system, effectively solving the problems of low identification efficiency and insufficient accuracy in traditional solutions, and ensuring the safety of the BNCT treatment process.

[0055] As a specific implementation method, the above-mentioned technical means can be implemented with reference to the following example. In the integrated wireless monitoring probe 100, the high-speed analog-to-digital conversion module 103A converts the analog electrical signal output by the photoelectric conversion module 102 into a digital signal at a high sampling rate (e.g., 1 GS / s), and streams these digital samples to the FPGA module. The FPGA module is pre-programmed with a pulse shape discrimination algorithm based on the Dual-Gate Integration Method. When a pulse signal arrives at the FPGA module, the FPGA module captures digital samples of the pulse in real time. The algorithm first defines two integration gates: a short integration gate (e.g., covering the pulse rise edge and near the peak, with a duration of tens of nanoseconds) and a long integration gate (e.g., covering the entire pulse decay process, with a duration of hundreds of nanoseconds). The FPGA module calculates the cumulative charge (i.e., the sum of digital samples) of the pulse signal within these two integration gates in parallel. Then, the FPGA module calculates the ratio between these two integral values, for example, the short integration value divided by the long integration value. Because the pulse waveforms generated by neutron and gamma events differ in rise and decay times, this ratio will exhibit different numerical ranges for neutron and gamma events. The FPGA module internally sets a discrimination threshold. By comparing the calculated ratio with this threshold, neutron events and gamma events can be distinguished in real time. For example, if the ratio is higher than a certain threshold, it is determined to be a neutron event; if it is lower than the threshold, it is determined to be a gamma event. The entire process is completed at high speed in a pipelined manner within the FPGA module's hardware logic, ensuring that each pulse signal can be discriminated within microseconds or even nanoseconds, thereby providing real-time and accurate event classification for subsequent count rate and dose rate calculations.

[0056] In some of the solutions described above in this invention, an FPGA module is proposed to perform pulse shape identification, count rate calculation, and dose rate calculation to monitor radiation signals in real time and distinguish between neutron events and gamma events. However, the lack of a built-in fast alarm mechanism in this process means that when radiation anomalies are detected, the response depends on external systems or manual judgment, resulting in alarm delays and safety hazards. It is impossible to immediately trigger local warnings and remote notifications at the probe end, thereby affecting the safety and real-time performance of treatment.

[0057] In response, the present invention further proposes to preset a safety threshold in the FPGA module and configure it so that when the neutron count rate or gamma dose rate exceeds the safety threshold, the high-speed digital-to-analog converter module 103B drives the LED indicator and / or buzzer to issue an audible and visual alarm, and sends an alarm signal to the central monitoring platform through the wireless communication module 105.

[0058] The safety threshold refers to the pre-set upper limit or safe range of neutron count rate or gamma dose rate during boron neutron capture therapy to ensure patient safety and treatment efficacy. These thresholds are determined based on clinical experience, physical dosimetry calculations, and safety regulations, and are used to determine whether the radiation level is within a normal or acceptable range. This safety threshold can be treated as constant data and directly programmed into the FPGA's internal memory using a hardware description language during the FPGA module configuration process. Alternatively, the safety threshold can be loaded into the FPGA module's internal RAM or registers by the central monitoring platform during system startup via an external interface, allowing for flexible adjustment without reprogramming the FPGA hardware logic. The FPGA module is configured to continuously compare the real-time calculated neutron count rate and gamma dose rate with the preset safety threshold when the neutron count rate or gamma dose rate exceeds the safety threshold. Once either monitored value exceeds its corresponding safety threshold, the FPGA module will immediately trigger an internal abnormal signal or status flag. The FPGA module can include a comparator logic unit that receives real-time data of the neutron count rate and gamma dose rate in parallel and compares them with a stored safety threshold. When the comparison result indicates that the threshold is exceeded, the comparator outputs a high-level signal. Alternatively, the FPGA module can implement a state machine that reads the current neutron count rate and gamma dose rate in each monitoring cycle and executes a series of conditional judgment instructions. If the judgment result indicates that the threshold is exceeded, the state machine switches to an alarm state and activates the corresponding alarm output logic. The high-speed digital-to-analog converter module 103B drives the LED indicator and / or buzzer to emit an audible and visual alarm. The audible and visual alarm is an intuitive and immediate local warning method used to directly send an abnormal signal to the operator at the probe end. The high-speed digital-to-analog converter module 103B here converts the digital alarm signal generated by the FPGA module into an analog electrical signal to drive external actuators such as LED indicator and / or buzzer. The high-speed digital-to-analog converter module 103B can receive the digital control signal output by the FPGA module and convert it into a specific voltage or current to directly drive the LED indicator to light up or flash, and simultaneously drive the buzzer to emit a continuous or intermittent sound. Alternatively, the high-speed digital-to-analog converter module 103B can serve as the interface between the FPGA module and the alarm actuator. The FPGA module directly controls the enable or output mode of the high-speed digital-to-analog converter module 103B through its digital output pins. The high-speed digital-to-analog converter module 103B then generates the audio-visual effects according to the preset analog output mode. The alarm signal is sent to the central monitoring platform via the wireless communication module 105. In addition to the local audio-visual alarm, the system also needs to remotely transmit alarm information to the central monitoring platform to achieve centralized management and a higher level of response.The wireless communication module 105 is responsible for encapsulating the alarm status data generated by the FPGA module and transmitting it via radio waves. The wireless communication module 105 can use the Wi-Fi protocol, where the FPGA module packages the alarm status data into TCP / IP or UDP packets and sends them to a designated IP address or port on the central monitoring platform via Wi-Fi. Alternatively, the wireless communication module 105 can use the Bluetooth Low Energy protocol, where the FPGA module sends the alarm status data as BLE broadcast packets or via the GATT service to paired devices on the central monitoring platform.

[0059] The present invention further enhances the localized anomaly response capability of the integrated wireless monitoring probe 100 described above. When the radiation detection module 101, photoelectric conversion module 102, and high-speed analog-to-digital conversion module 103A work together to convert neutron and gamma-ray events into digital signals and send them to the FPGA module, the FPGA module not only performs pulse shape identification, count rate calculation, and dose rate calculation, but also has a built-in preset safety threshold. The FPGA module is configured to perform high-speed comparison of the calculated neutron count rate or gamma dose rate with these preset safety thresholds in real time. Once any monitored value exceeds the safety threshold, the hardware logic of the FPGA module will immediately trigger an alarm mechanism. At this time, the FPGA module generates a corresponding digital control signal and converts it into an analog signal through the high-speed digital-to-analog conversion module 103B, thereby driving the LED indicator and / or buzzer integrated on the probe to emit an intuitive audible and visual alarm, achieving immediate local warning. Simultaneously, the FPGA module also encapsulates the current alarm status information through the wireless communication module 105 and quickly sends it to the remote central monitoring platform. This closed-loop mechanism of "sensing-decision-local alarm-remote notification" integrated at the probe end enables the system to issue a warning locally and simultaneously notify the central platform at the first moment when a radiation anomaly occurs, without waiting for instructions from the central platform. This greatly shortens the anomaly response time and effectively solves the problems of delayed alarms and reliance on manual judgment in traditional systems, significantly improving the real-time safety and reliability of the boron neutron capture therapy process.

[0060] As a specific implementation, the FPGA module within the integrated wireless monitoring probe 100 can utilize a high-performance FPGA chip. Within the FPGA module's internal logic, a dedicated "threshold comparison and alarm control" module can be designed. This module contains multiple registers for storing preset safe upper limits for neutron count rate and gamma dose rate. These thresholds can be loaded from external configuration memory via JTAG or SPI interfaces when the FPGA is powered on, or defined directly in the FPGA's hardware description language. When the FPGA module calculates the neutron count rate and gamma dose rate in real time, these two values ​​are input in parallel to the "threshold comparison and alarm control" module. The module's internal comparator logic immediately compares the neutron count rate with the neutron safety upper limit and the gamma dose rate with the gamma safety upper limit. If either comparison result shows that the current value is greater than the corresponding safety upper limit, the module immediately outputs a digital alarm signal. This digital alarm signal is then sent to a high-speed digital-to-analog converter (DAC) module 103B, which converts the digital signal into analog voltage or current, thereby driving a high-brightness LED indicator to flash and a miniature piezoelectric buzzer to emit a high-frequency sound. Simultaneously, the FPGA module also sends a simplified data packet containing the alarm type and the current out-of-limit value to the central monitoring platform via the wireless communication module 105. Upon receiving this data packet, the central monitoring platform can immediately display the alarm information on the user interface and record the event.

[0061] In some of the above-mentioned solutions of the present invention, a wireless communication module 105 is proposed to send the processed result data to the central monitoring platform. However, in this process, if the amount of data transmitted is too large, it will lead to insufficient wireless transmission bandwidth and increased latency, affecting the real-time response capability and efficiency of the system, and failing to meet the requirements of high real-time monitoring.

[0062] In response, the present invention further proposes that the wireless communication module 105 transmits only the simplified result data processed by the FPGA module, the simplified result data including neutron count rate, gamma dose rate and alarm status.

[0063] The wireless communication module 105 is responsible for wirelessly transmitting the data processed at the probe end. Its implementation can be varied; the field-programmable gate array (FPGA) module 104 is a reconfigurable integrated circuit whose internal logic can be programmed as needed to achieve specific functions. In this system, the FPGA module is configured to perform high-speed, parallel processing of digital signals, including complex algorithms such as pulse shape identification, count rate calculation, and dose rate calculation, thereby enabling real-time data preprocessing and decision-making at the probe end. The simplified result data refers to the core information extracted from the original detection signal after processing by the FPGA module, used to characterize the radiation field state. This data format aims to minimize transmission volume, containing only parameters crucial for monitoring and alarming, rather than raw, unprocessed waveform data or a large number of intermediate calculation results. The neutron count rate refers to the number of neutron events detected per unit time, directly reflecting the neutron flux; the gamma dose rate refers to the gamma ray energy absorbed by the patient or a specific area per unit time, a key indicator for assessing gamma radiation risk; and the alarm status is a sign indicating whether the system is currently in an abnormal or warning state. These three types of data are the core outputs of online dose monitoring for boron neutron capture therapy (BNCT), and together they constitute the key assessment basis for the safety and effectiveness of the treatment process.

[0064] In some of the above embodiments, the integrated wireless monitoring probe 100 converts the radiation signal into a digital signal through a radiation detection module 101, a photoelectric conversion module 102, and a high-speed analog-to-digital conversion module 103A. Subsequently, the field-programmable gate array (FPGA) module 104 performs pulse shape discrimination on these digital signals to distinguish between neutron and gamma events, and further calculates the neutron count rate and gamma dose rate. To address the problem of insufficient bandwidth and increased latency caused by excessive data volume in wireless transmission, this invention proposes an optimization scheme. Specifically, the FPGA module performs in-depth processing of the original digital signal at the probe end, not only distinguishing between neutron and gamma events but also directly calculating the neutron count rate and gamma dose rate, and generating an alarm status according to preset logic. Subsequently, the wireless communication module 105 no longer transmits the original, massive digital signal or intermediate processed data, but only transmits the highly simplified result data processed by the FPGA module. This simplified result data contains only three core parameters: neutron count rate, gamma dose rate, and alarm status. By combining edge computing with streamlined transmission, the FPGA module completes most of the data processing locally, significantly reducing the amount of data that needs to be transmitted through the wireless communication module 105. This synergy significantly reduces the transmission burden on the wireless communication module 105, effectively avoiding the problems of insufficient wireless transmission bandwidth and increased latency, and ensuring that the system can send critical monitoring information to the central monitoring platform with high real-time performance.

[0065] In one specific implementation, after the integrated wireless monitoring probe 100 completes the detection and processing of the radiation signal, the FPGA module generates a data packet containing simplified result data. For example, this data packet can be a compact binary structure or a simplified JSON string. The data packet may contain a field representing the current neutron count rate, such as "N_Rate: 1.2e5 cps"; another field representing the gamma dose rate, such as "G_Dose: 0.05Gy / h"; and a Boolean or enumerated field indicating the current alarm status, such as "Alarm_Status: Normal" or "Alarm_Status: High_Neutron". Upon receiving this simplified data packet, the wireless communication module 105 immediately transmits it via the wireless network. Due to the small size of the data packet and the extremely short transmission time, high transmission efficiency and reliability are maintained even in complex electromagnetic environments. After receiving this simplified data, the central monitoring platform can directly parse and display the neutron count rate, gamma dose rate, and alarm status without complex backend calculations, thus achieving rapid response and real-time monitoring.

[0066] In some of the above-mentioned solutions of the present invention, an integrated wireless monitoring probe 100 is proposed to realize radiation monitoring. However, in its implementation, the size and structural design of the probe may not be suitable for installation in limited space, the power supply may limit its wireless portability, and a single probe cannot realize multi-location distributed monitoring.

[0067] In this regard, the present invention further proposes that the power module 106 is a built-in rechargeable lithium battery; the integrated wireless monitoring probe 100 is encapsulated as a cylindrical structure with a diameter of 4-5 cm and a length of 5-8 cm, the front end of the cylinder is provided with the three probes, and the rear end is provided with a signal antenna and a data interface; the system includes multiple integrated wireless monitoring probes 100 forming a distributed monitoring network.

[0068] In another embodiment, such as Figure 6As shown, this invention proposes an online dose monitoring and alarm method, using the aforementioned system for monitoring. The method includes the following steps: Three probes in the radiation detection module 101 detect background light signals, gamma-ray generated light signals, and neutron-generated light signals, respectively; the photoelectric conversion module 102 converts the light signals into electrical signals; the high-speed analog-to-digital converter module 103A converts the electrical signals into digital signals; the FPGA module at the probe end performs pulse shape discrimination on the digital signals to distinguish between neutron and gamma events, and calculates the neutron count rate and gamma dose rate; when a dose abnormality is detected, the high-speed analog-to-digital converter module 103B at the probe end drives an LED indicator and / or a buzzer to issue an alarm; the processed result data is transmitted to the central monitoring platform via the wireless communication module 105.

[0069] Through the above technical solutions, the system can comprehensively assess the actual radiation dose received by the patient, reducing the response time from seconds in traditional systems to milliseconds, greatly improving treatment safety. Its miniaturized and wireless design allows for flexible installation in space-constrained treatment areas. For example, during boron neutron capture therapy, multiple integrated wireless monitoring probes 100 can be deployed near the treatment head or the patient's body surface to monitor neutron flux and gamma dose in real time. When beam abnormalities occur, the FPGA at the probe end quickly identifies the type of abnormality and triggers a local alarm, while simultaneously wirelessly transmitting the processed data to the central monitoring platform, ensuring that operators can take timely measures to avoid the medical risks of insufficient or excessive radiation dose.

[0070] In some of the solutions described above in this invention, an FPGA module is used at the probe end to perform pulse shape identification to distinguish between neutron and gamma events, and to calculate the count rate and dose rate, in order to achieve real-time monitoring and rapid alarm. However, if the pulse shape identification is performed in software, the processing speed may be slow, failing to achieve a millisecond-level response time, thus affecting the real-time performance and security of the system. Therefore, this invention further proposes that the pulse shape identification of the digital signal to distinguish between neutron and gamma events, and the calculation of the neutron count rate and gamma dose rate, performed by the FPGA module at the probe end, be executed at the hardware logic level.

[0071] The present invention solves the latency problem that may be caused by traditional software processing by executing the key processing step of pulse shape identification at the hardware logic level in the FPGA module at the probe end. Specifically, when the radiation detection module 101 receives neutrons or gamma rays and converts them into digital signals through the photoelectric conversion module 102 and the high-speed analog-to-digital conversion module 103A, these digital signals are directly sent to the FPGA module. The pre-configured hardware logic circuits inside the FPGA module perform parallel and high-speed real-time analysis on each digital pulse signal. For example, by calculating parameters such as the rise time of the pulse or the charge integral ratio in different time windows, and comparing them with preset identification thresholds, the system can accurately distinguish whether the pulse is caused by a neutron event or a gamma event in a very short time. This hardware-level identification mechanism avoids the latency of data transmission to the central processing unit for software analysis and also avoids the nondeterminism of software execution, ensuring that each event can be classified instantly. Based on these real-time classification results, the FPGA module can immediately update the neutron counter and gamma counter, and further calculate the current neutron count rate and gamma dose rate. This highly integrated on-chip real-time processing capability enables the system to respond to changes in the radiation field at a millisecond-level response speed, providing a timely and accurate data foundation for subsequent anomaly detection and alarm.

[0072] As a specific implementation, the FPGA module at the probe end can perform pulse shape identification at the hardware logic level using digital charge integration. After the high-speed analog-to-digital converter 103A converts the analog electrical signal output from the photoelectric conversion module 102 into a digital signal, these digital sampling point sequences are sent to the FPGA module. The FPGA module can be configured with two parallel digital integrators: one accumulates the digital sampling points within a short time window of the pulse (e.g., from the pulse start point to the peak point) to obtain a short integral value; the other accumulates them within a longer time window (e.g., from the pulse start point to the end of pulse decay) to obtain a long integral value. Subsequently, the hardware logic circuit within the FPGA module calculates a pulse shape identification parameter in real time, such as the ratio of the short integral value to the long integral value. Since neutron and gamma events produce different pulse shapes, their ratios will also differ significantly. The comparator inside the FPGA module compares the calculated ratio with a preset hardware threshold, thereby completing the event type determination within a single clock cycle. For example, if the ratio is higher than a certain threshold, it is determined to be a neutron event; if it is lower than the threshold, it is determined to be a gamma event. These judgment results will immediately trigger the corresponding hardware counters to accumulate, which will then be used to calculate the neutron count rate and gamma dose rate in real time.

[0073] In some of the solutions described above in this invention, an FPGA module is proposed for anomaly detection to achieve rapid alarm. However, in this process, the lack of a preset safety threshold may lead to inaccurate and untimely anomaly judgment, thereby affecting the reliability and response speed of the alarm.

[0074] In response, this invention further proposes that the FPGA module has a preset safety threshold, and the anomaly detection includes comparing the calculated neutron count rate or gamma dose rate with the safety threshold.

[0075] The safety thresholds are pre-set critical values ​​used to determine whether the neutron count rate or gamma dose rate is within a safe range. These safety thresholds can be fixed as constants in the configuration logic of the FPGA module, or loaded or updated during FPGA module runtime via external interfaces (such as JTAG, SPI interfaces, or by receiving commands through the wireless communication module 105). The safety threshold can be a single upper limit or a range of upper and lower limits, and different safety thresholds can be set for neutron count rate and gamma dose rate. The purpose of pre-setting safety thresholds is to provide a clear basis for anomaly detection, ensuring the objectivity and consistency of the detection. Anomaly detection involves comparing the calculated neutron count rate or gamma dose rate with the safety thresholds; this is the core logic of anomaly judgment. By comparing real-time monitoring data with preset safety standards, potential dangerous situations can be quickly identified. The logic circuits inside the FPGA module can implement a comparator function, comparing the real-time calculated neutron count rate or gamma dose rate with the stored safety thresholds cycle-by-cycle or periodically. The comparison logic can include various judgment conditions such as "greater than," "less than," and "out of range." Once the comparison result meets the abnormal conditions, the FPGA module can immediately trigger the corresponding alarm signal.

[0076] This solution addresses the issues of inaccurate and untimely anomaly detection by pre-setting safety thresholds within the FPGA module and directly comparing the calculated neutron count rate or gamma dose rate to these thresholds during anomaly detection. Specifically, upon receiving a digital signal, the FPGA module performs pulse shape discrimination to distinguish between neutron and gamma events and calculates the neutron count rate and gamma dose rate. Based on this, the internal logic circuitry of the FPGA module compares the real-time calculated neutron count rate with the preset neutron safety threshold, and simultaneously compares the gamma dose rate with the preset gamma safety threshold. This comparison is continuous; if any calculated value exceeds its corresponding safety threshold, the FPGA module immediately identifies it as an anomaly. This real-time comparison at the FPGA module hardware level ensures the speed and accuracy of anomaly detection, avoiding the delays caused by manual judgment or backend software processing in traditional solutions, thereby significantly improving the overall system's response speed and security.

[0077] This invention constructs an integrated monitoring network combining distributed sensing, edge computing, and wireless transmission. Each probe is an independent monitoring node, internally integrating: Radiation detection module 101: Employs a miniaturized scintillator + photomultiplier tube (PMT) or silicon photomultiplier tube (SiPM) combination. For example, a boron-containing polystyrene scintillator or a thermal neutron-sensitive scintillator can be used. 6 Li glass scintillators or fast neutron-sensitive plastic scintillators are used, along with gamma-ray-sensitive LaBr3(Ce) or GAGG scintillators. PMTs or SiPMs are responsible for converting the weak light signals generated by the scintillators into electrical signals.

[0078] AD / DA module (high-speed analog-to-digital / digital-to-analog converter): The AD converter directly receives the analog electrical signal output from the PMT and converts it into a digital signal at a high sampling rate (e.g., 1 GS / s). This is crucial to ensuring no loss of signal detail. The DA converter will activate audible and visual alarms (e.g., LED warning lights, buzzers).

[0079] FPGA (Field-Programmable Gate Array) Module: This is the "brain" of the probe. The FPGA is configured to perform the following functions: Real-time Pulse Shape Discrimination (PSD): Utilizing the differences in pulse waveform characteristics (rise time, decay time, etc.) generated by neutrons and gamma rays in the scintillator, neutron and gamma events are distinguished in real time at the hardware logic level. Count Rate and Dose Calculation: The identified neutron and gamma events are counted separately, and the neutron flux rate and gamma dose rate are calculated in real time based on preset conversion coefficients. Anomaly Detection Algorithm: The hardware logic running on the FPGA continuously compares the current count rate with a preset safety threshold, or monitors for sudden changes in the count rate. Once an anomaly is detected, an alarm is immediately triggered.

[0080] Real-time Pulse Shape Discrimination (PSD) is specifically as follows: a neutron or gamma ray triggers a probe to generate an optical signal (signal generation) → the PMT acquires the optical signal and converts it into an electrical signal (signal acquisition and conversion) → the AD / DA module acquires the electrical signal (signal collection) → the algorithm in the FPGA extracts signal features (feature extraction) → the FPGA analyzes the signal (threshold comparison) → the FPGA performs statistical counting (event classification) → the FPGA transmits the statistical and calculation results to the wireless module → the wireless module sends the results.

[0081] The specific logic framework for real-time pulse shape identification is as follows: Figure 5 As shown.

[0082] LED and Buzzer Module: The LED indicator group will display data results through different colors (red, yellow, green) and different states (solid on, flashing). When an abnormal dosage is detected, the buzzer will sound an alarm.

[0083] Wireless communication module 105: integrates a Wi-Fi or Bluetooth module. It is responsible for wirelessly transmitting the results data (such as neutron count rate, gamma dose rate, alarm status, etc.) after FPGA calculation and processing, instead of transmitting the raw, large-volume analog or digital waveforms, which greatly reduces the transmission load and latency.

[0084] Power module 106: Powered by a rechargeable lithium battery, ensuring complete wireless operation of the probe.

[0085] The system workflow of this technical solution: Signal sensing: Neutrons or gamma rays interact with a scintillator in the detector, producing fluorescence.

[0086] Photoelectric conversion: PMT or SiPM converts fluorescence into corresponding analog electrical signals (voltage pulses).

[0087] Signal digitization: The high-speed analog-to-digital converter (ADC) instantly captures the voltage pulse and converts it into a high-precision digital sequence. Anomaly alarm can be triggered via the DA module, activating a buzzer and LED indicator.

[0088] On-chip real-time processing: The FPGA receives digital pulse signals. Using the built-in PSD algorithm, it instantaneously determines whether the pulse originates from a neutron or a gamma event. It then accumulates the signal on the corresponding counter and executes dose calculation and anomaly detection logic.

[0089] Result wireless transmission: The FPGA packages the processed and simplified result data (e.g., "Probe A, neutron count rate: 1050cps, gamma dose rate: 0.15 Gy / h, status: normal") and sends it to the central monitoring platform via the wireless module.

[0090] Based on the above technical solutions, silicon photomultiplier tubes (SiPMs) can be used to replace traditional photodetectors. SiPMs are smaller, consume less power, and are insensitive to magnetic fields, making them more suitable for achieving extreme miniaturization and portability of detectors.

[0091] For neutron detection, besides boron-containing polystyrene scintillators or those sensitive to thermal neutrons... 6 In addition to Li glass scintillators or fast neutron-sensitive plastic scintillators, miniaturized ³He proportional counters (if volume and pressure are controllable) or boron-coated semiconductor detectors can also be used as alternatives.

[0092] In scenarios with relatively simple computational tasks, high-performance microcontrollers (MCUs) or application-specific integrated circuits (ASICs) can be used to replace FPGAs. MCUs are cheaper, ASICs have better power consumption and size, but FPGAs have advantages in flexibility and parallel processing capabilities.

[0093] In addition to Wi-Fi / Bluetooth, for applications requiring extremely low power consumption and self-organizing networks, wireless communication protocols such as Zigbee or LoRa can be considered.

[0094] In addition to lithium batteries, wireless charging technology or energy harvesting solutions (such as light energy harvesting) using low-power probes deployed in the treatment room can be used to achieve permanent or semi-permanent wireless power supply.

[0095] In a simplified approach, the ADC and FPGA can be retained at the probe end for signal processing and anomaly detection, but the final dose calculation and data display tasks can be completed on a central platform to reduce the complexity at the probe end.

[0096] The above description is merely an embodiment of the present invention and is not intended to limit the scope of protection of the present invention. For those skilled in the art, the present invention can have various modifications and variations. Any modifications, equivalent substitutions, improvements, etc., made within the spirit and principles of the present invention should be included within the scope of protection of the present invention.

Claims

1. An online dose monitoring and alarm system for boron neutron capture therapy, characterized in that, Includes at least one set of integrated wireless monitoring probes and a central monitoring platform; The integrated wireless monitoring probe includes a radiation detection module, a photoelectric conversion module, a high-speed analog-to-digital conversion module, a high-speed digital-to-analog conversion module, a field-programmable gate array (FPGA) module, a wireless communication module, and a power supply module. The radiation detection module includes a structure consisting of three probes: a background light signal probe, a gamma-ray light signal probe, and a neutron light signal probe. The photoelectric conversion module is used to convert optical signals into electrical signals; The high-speed analog-to-digital converter module is used to convert electrical signals into digital signals; The FPGA module is connected to the high-speed analog-to-digital conversion module and the wireless communication module, and is configured to perform pulse shape discrimination on the digital signal to distinguish between neutron events and gamma events, and to perform count rate calculation and dose rate calculation. The wireless communication module is used to send the result data processed by the FPGA module to the central monitoring platform.

2. The system according to claim 1, characterized in that, The neutron optical signal probe in the radiation detection module uses a boron-containing polystyrene scintillator. 6 The gamma-ray optical signal probe uses at least one of Li glass scintillator or plastic scintillator, and employs LaBr3 (Ce) scintillator or GAGG scintillator.

3. The system according to claim 1, characterized in that, The photoelectric conversion module includes a photomultiplier tube (PMT) or a silicon photomultiplier tube (SiPM).

4. The system according to claim 1, characterized in that, The FPGA module is configured to perform a pulse shape discrimination algorithm based on the difference between the rise time and / or decay time of the pulse waveform.

5. The system according to claim 1, characterized in that, The FPGA module has a preset safety threshold and is configured to activate an audible and visual alarm by driving an LED indicator and / or a buzzer through the high-speed digital-to-analog converter when the neutron count rate or gamma dose rate exceeds the safety threshold, and to send an alarm signal to the central monitoring platform through the wireless communication module.

6. The system according to claim 1, characterized in that, The wireless communication module only transmits the simplified result data processed by the FPGA module, which includes neutron count rate, gamma dose rate, and alarm status.

7. The system according to claim 1, characterized in that, The power module is a built-in rechargeable lithium battery; the integrated wireless monitoring probe is encapsulated as a cylindrical structure with a diameter of 4-5 cm and a length of 5-8 cm. The three probes are located at the front end of the cylinder, and the signal antenna and data interface are located at the rear end; the system includes multiple integrated wireless monitoring probes forming a distributed monitoring network.

8. An online dose monitoring and alarm method, characterized in that, Monitoring using the system described in claim 1 includes the following steps: The three probes based on the radiation detection module detect the background light signal, the light signal generated by gamma rays, and the light signal generated by neutrons, respectively. Optical signals are converted into electrical signals based on a photoelectric conversion module; Electrical signals are converted into digital signals based on a high-speed analog-to-digital converter module; The FPGA module at the probe end performs pulse shape discrimination on the digital signal to distinguish between neutron events and gamma events, and calculates the neutron count rate and gamma dose rate. When an abnormal dose is detected, the high-speed digital-to-analog converter at the probe end drives the LED indicator and / or the buzzer to issue an alarm. The processed data is sent to the central monitoring platform via a wireless communication module.

9. The method according to claim 8, characterized in that, The steps described above involve the FPGA module at the probe end performing pulse shape identification on the digital signal to distinguish between neutron events and gamma events, and calculating the pulse shape identification in the neutron count rate and gamma dose rate. This pulse shape identification is performed by the FPGA module at the hardware logic level.

10. The method according to claim 8, characterized in that, The FPGA module has a preset safety threshold, and the anomaly detection includes comparing the calculated neutron count rate or gamma dose rate with the safety threshold.

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