Method and apparatus for neutron dosimetry

Abstract

The present application provides a neutron dose measurement method in one aspect, comprising: determining a to-be-corrected unit corresponding to a dose monitoring system; determining a first correction factor based on the number of rays emitted after neutron activation of a to-be-activated non-metal unit and the to-be-corrected unit corresponding to the dose monitoring system; and correcting the dose monitoring system based on the first correction factor, thereby determining the real-time neutron dose of a patient. The present application corrects the sensitivity of the dose monitoring system by determining the first correction factor, thereby determining the real-time neutron dose of the patient, avoiding measurement errors caused by the reduced sensitivity or position change of the dose monitoring system, and improving the accuracy and reliability of the measurement results. The present application provides a neutron dose measurement device corresponding to the method.

Description

Technical Field

[0001] This application relates to the field of neutron dose measurement technology, specifically to a neutron dose measurement method and apparatus. Background Technology

[0002] The dose monitoring system acts as the "eyes" of boron neutron capture therapy (BNCT), playing a crucial role throughout the entire tumor treatment process. It can assess the neutron dose irradiated to the patient and stop irradiation when the neutron dose reaches the preset value.

[0003] However, while existing dose monitoring systems can measure the real-time neutron dose to patients, their sensitivity decreases after a certain period of measurement, leading to errors in the measurement results. Consequently, they cannot accurately control the irradiation time based on the preset neutron dose value. Summary of the Invention

[0004] To address the aforementioned technical problems, this application is proposed. Embodiments of this application provide a neutron dose measurement method and apparatus.

[0005] In a first aspect, one embodiment of this application provides a neutron dose measurement method, which includes: determining a unit to be calibrated corresponding to a dose monitoring system; determining a first calibration factor based on the number of rays emitted by a non-metallic unit after neutron activation and the unit to be calibrated corresponding to the dose monitoring system, wherein the non-metallic unit to be activated includes a non-metallic component and a first detection unit for detecting the number of rays emitted by the non-metallic component after neutron activation; and calibrating the dose monitoring system based on the first calibration factor to determine the real-time neutron dose to the patient.

[0006] In conjunction with the first aspect, in some implementations of the first aspect, the unit to be corrected is set as the count rate to be corrected; the first neutron reaction rate is determined based on the number of rays emitted by the non-metallic unit to be activated after neutron activation; and the first correction factor is determined based on the count rate to be corrected and the first neutron reaction rate.

[0007] In conjunction with the first aspect, in some implementations of the first aspect, the average count rate of nonmetals corresponding to the activation time period of the nonmetal unit to be activated is determined based on the count rate to be corrected; and the first correction factor is determined based on the first neutron reaction rate and the average count rate of nonmetals.

[0008] In conjunction with the first aspect, in some implementations of the first aspect, a second correction factor is determined based on the number of rays emitted by the non-metallic unit to be activated after neutron activation and the number of rays emitted by the corresponding unit to be calibrated in the dose monitoring system or the number of rays emitted by the metallic unit to be activated after neutron activation; the metallic unit to be activated includes a metallic component and a second detection unit for detecting the number of rays emitted by the metallic component after neutron activation; the first correction factor is corrected based on the second correction factor, thereby correcting the calibrated dose monitoring system.

[0009] In conjunction with the first aspect, in some implementations of the first aspect, a second neutron reaction rate is determined based on the number of rays emitted by the metal unit to be activated after neutron activation; an average metal count rate for the activation time period corresponding to the metal unit to be activated is determined based on the count rate to be corrected; and a second correction factor is determined based on the first neutron reaction rate and the average metal count rate or the second neutron reaction rate.

[0010] In conjunction with the first aspect, in some implementations of the first aspect, the first correction factor is corrected based on the second correction factor, thereby correcting the corrected dose monitoring system, including: determining the difference information between the first correction factor and the second correction factor; if the first correction factor is determined to meet the preset difference threshold condition based on the difference information, then the correction value corresponding to the dose monitoring system is determined based on the first correction factor; and the real-time neutron dose to the patient is determined based on the correction value corresponding to the dose monitoring system, the dose conversion factor, and the irradiation time corresponding to the patient.

[0011] In conjunction with the first aspect, in some implementations of the first aspect, the dose conversion factor includes a boron dose conversion factor. The real-time neutron dose to the patient is determined based on the correction value corresponding to the dose monitoring system, the dose conversion factor, and the patient's irradiation time. This includes: determining the real-time dose rate correction value for cancer cells corresponding to the dose monitoring system based on the correction value and the boron dose conversion factor; and determining the real-time neutron dose to the patient's cancer cells based on the real-time dose rate correction value for cancer cells and the irradiation time.

[0012] In conjunction with the first aspect, in some implementations of the first aspect, the dose conversion factor includes a non-cancer cell dose conversion factor. Determining the patient's real-time neutron dose based on the correction value corresponding to the dose monitoring system, the dose conversion factor, and the patient's irradiation time includes: determining a real-time dose rate correction value for non-cancer cells corresponding to the dose monitoring system based on the correction value corresponding to the dose monitoring system and the non-cancer cell dose conversion factor; and determining the patient's real-time neutron dose for non-cancer cells based on the real-time dose rate correction value for non-cancer cells and the irradiation time.

[0013] In conjunction with the first aspect, in some implementations of the first aspect, the material of the nonmetallic unit to be activated includes at least one of phosphorus, sulfur, silicon, and bromine.

[0014] Secondly, one embodiment of this application provides a neutron dose measurement device, which includes: a first determining module for determining a unit to be calibrated corresponding to a dose monitoring system; a second determining module for determining a first calibration factor based on the number of rays emitted by a non-metallic unit to be activated after neutron activation and the unit to be calibrated corresponding to the dose monitoring system, wherein the non-metallic unit to be activated includes a non-metallic component and a first detection unit for detecting the number of rays emitted by the non-metallic component after neutron activation; and a third determining module for calibrating the dose monitoring system based on the first calibration factor, thereby determining the real-time neutron dose to the patient.

[0015] Thirdly, one embodiment of this application provides a computer-readable storage medium including a computer program for performing any of the above-described neutron dose measurement methods.

[0016] Fourthly, one embodiment of this application provides an electronic device, including a processor for performing any of the above-described neutron dose measurement methods and a memory for storing executable instructions of the processor.

[0017] The neutron dose measurement method, neutron dose measurement device, computer-readable storage medium, and electronic device provided in this application determine the unit to be calibrated corresponding to the dose monitoring system, and then determine a first calibration factor based on the number of rays emitted by the non-metallic unit to be activated after neutron activation and the unit to be calibrated corresponding to the dose monitoring system. The first calibration factor is used to correct the sensitivity of the dose monitoring system, thereby determining the real-time neutron dose to the patient, avoiding measurement errors caused by reduced sensitivity or position changes of the dose monitoring system, and improving the accuracy and reliability of the measurement results. Attached Figure Description

[0018] The above and other objects, features, and advantages of this application will become more apparent from the more detailed description of the embodiments of this application in conjunction with the accompanying drawings. The drawings are provided to further illustrate the embodiments of this application and form part of the specification. They are used together with the embodiments of this application to explain this application and do not constitute a limitation thereof. In the drawings, the same reference numerals generally represent the same components or steps.

[0019] Figure 1 The diagram shown is a flowchart of a neutron dose measurement method provided in an exemplary embodiment of this application.

[0020] Figure 2 The diagram shown is a flowchart of a neutron dose measurement method provided in another exemplary embodiment of this application.

[0021] Figure 3The diagram shown is a flowchart of a neutron dose measurement method provided in another exemplary embodiment of this application.

[0022] Figure 4 The diagram shown is a flowchart of a neutron dose measurement method provided in another exemplary embodiment of this application.

[0023] Figure 5 The diagram shown is a schematic flowchart of an exemplary embodiment of this application, which describes the process of determining the real-time neutron dose of a patient based on the correction value corresponding to the dose monitoring system, the dose conversion factor, and the patient's irradiation time.

[0024] Figure 6 The diagram shown is a flowchart illustrating the process of determining the real-time neutron dose of a patient based on the correction value corresponding to the dose monitoring system, the dose conversion factor, and the patient's irradiation time, according to another exemplary embodiment of this application.

[0025] Figure 7 The diagram shown is a flowchart of a neutron dose measurement method provided in another exemplary embodiment of this application.

[0026] Figure 8 The diagram shown is a schematic representation of a neutron dose measurement device provided in an exemplary embodiment of this application.

[0027] Figure 9 The diagram shown is a structural schematic of an electronic device provided in an exemplary embodiment of this application. Detailed Implementation

[0028] The technical solutions of the embodiments of this application will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of this application, and not all embodiments. Based on the embodiments of this application, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of this application.

[0029] Boron neutron capture therapy destroys cancer cells through nuclear reactions within tumor cells. The principle behind this treatment is as follows: First, the patient is injected with a special boron-containing compound. This compound has a strong affinity for cancer cells, rapidly accumulating within them while remaining scarce in other tissues. This boron-containing compound is non-toxic and harmless to the human body, and has no therapeutic effect on cancer. Then, the patient is irradiated with neutron rays. These rays cause minimal damage to the body, but the neutrons react strongly with the boron within the cancer cells, releasing a highly lethal ray. This ray has a very short range, only the length of a cancer cell. Therefore, it kills only the cancer cells without damaging surrounding tissues. This technique of selectively killing complex-shaped cancer cells without damaging normal tissue is called boron neutron capture therapy.

[0030] The dose monitoring system, acting as the "eyes" of boron neutron capture therapy, plays a crucial role throughout the entire tumor treatment process. It assesses the neutron dose received by the patient and stops irradiation when the dose reaches a preset value. Currently, the most accurate method for neutron dose measurement is the neutron activation method. However, this method, which involves irradiating the patient with neutrons and then measuring the dose, is very time-consuming and cannot provide immediate results, thus failing to determine the patient's real-time neutron dose. While the transient activation analysis method can determine the patient's real-time neutron dose, the complex background radiation field introduces errors in the measurement results and can also cause beam disturbances. Furthermore, it requires additional hardware infrastructure, which is costly, and maintenance costs are also quite high.

[0031] While active detectors such as BF3 detectors can measure neutron dose in real time, the concentration of BF3 used in the detector gradually decreases after a period of neutron irradiation, leading to a reduction in the detector's sensitivity. Therefore, a BF3 detector that has been used for a certain period will inevitably respond differently to the same neutron intensity compared to an unused BF3 detector, resulting in measurement errors. Thus, the sensitivity of the BF3 detector needs to be calibrated periodically to ensure the accurate operation of the dose monitoring system.

[0032] Figure 1 The diagram shown is a schematic flowchart of a neutron dose measurement method provided in an exemplary embodiment of this application. Figure 1 As shown in the embodiments of this application, the neutron dose measurement method includes the following steps.

[0033] Step S10: Determine the unit to be calibrated corresponding to the dose monitoring system.

[0034] In one embodiment of this application, the unit to be corrected includes, but is not limited to, count rate (in n / s) and neutron flux (in N / cm²). 2 ), neutron dose (unit: Gy). The count rate can be determined based on real-time counting by a counter.

[0035] Step S20: Based on the number of rays emitted by the non-metallic unit to be activated after neutron activation and the corresponding calibration unit of the dose monitoring system, a first calibration factor is determined. The non-metallic unit to be activated includes a non-metallic component and a first detection unit for detecting the number of rays emitted by the non-metallic component after neutron activation.

[0036] In one embodiment of this application, the non-metallic unit to be activated may be a phosphorus plate ( 31P). The first detection unit can be a counter used to detect the number of rays emitted by the non-metallic component after neutron activation. For example, the non-metallic unit to be activated can be placed in the air at the neutron beam exit, or it can be placed inside a phantom for neutron irradiation for a certain period of time. 31 P will be activated by neutrons to become 31 After neutron irradiation stops, a counter is used to count the 1266keV rays emitted by the non-metallic unit to be activated by neutrons. Based on the number of rays and the unit to be calibrated, a first correction factor is determined. The first correction factor is used to correct the aforementioned unit to be calibrated in order to correct the sensitivity of the dose monitoring system.

[0037] Step S30: Based on the first correction factor, the dose monitoring system is calibrated to determine the patient's real-time neutron dose.

[0038] In practical applications, the unit to be calibrated corresponding to the dose monitoring system is first determined. Then, based on the number of rays emitted by the non-metallic unit to be activated after neutron activation and the unit to be calibrated, the first calibration factor is determined. Finally, based on the first calibration factor, the dose monitoring system is calibrated to determine the real-time neutron dose to the patient.

[0039] The neutron dose measurement method provided in this application determines the unit to be calibrated corresponding to the dose monitoring system, and then determines a first calibration factor based on the number of rays emitted by the non-metallic unit to be activated after neutron activation and the unit to be calibrated corresponding to the dose monitoring system. The first calibration factor is used to correct the sensitivity of the dose monitoring system, thereby determining the real-time neutron dose to the patient, avoiding measurement errors caused by reduced sensitivity or position changes of the dose monitoring system, and improving the accuracy and reliability of the measurement results.

[0040] Figure 2 The diagram shown is a flowchart illustrating a neutron dose measurement method provided in another exemplary embodiment of this application. Figure 1 This application extends from the embodiments shown. Figure 2 The illustrated embodiment will be described in detail below. Figure 2 The illustrated embodiments and Figure 1 The differences between the embodiments shown are not repeated here, and the similarities are not repeated here.

[0041] like Figure 2 As shown, in the neutron dose measurement method provided in this application embodiment, the unit to be calibrated is set as the count rate to be calibrated, including the following steps.

[0042] Step S31: Determine the first neutron reaction rate based on the number of correction rays emitted by the non-metallic unit to be activated after neutron activation.

[0043] In one embodiment of this application, the first neutron reaction rate RR1 is determined according to the following formula (1).

[0044]

[0045] In the above formula (1), λ is the decay constant, C is the number of rays measured within the counting time (net count), N1 is the number of target nuclei of the non-metallic unit to be activated under irradiation, ε is the detection efficiency of the activation detector for the correction ray, Y is the correction ray branching ratio, f1 is the self-absorption correction factor of the correction ray, G is the flux fluctuation correction factor, and t irr t is the neutron irradiation time. c The cooling time (i.e., the time from the end of neutron irradiation to the start of radiation quantity measurement) is t. m The time for measuring the number of rays.

[0046] Step S32: Determine the first correction factor based on the count rate to be corrected and the first neutron reaction rate.

[0047] For example, after determining the count rate to be corrected and the first neutron reaction rate, the count rate to be corrected and the first neutron reaction rate can be calculated to obtain the first correction factor.

[0048] In one embodiment of this application, the average count rate of nonmetals corresponding to the activation time period of the nonmetal unit to be activated is first determined based on the count rate to be corrected, and then the first correction factor is determined based on the first neutron reaction rate and the average count rate of nonmetals.

[0049] Specifically, the average count rate of non-metallic substances Determined according to the following formula (2).

[0050]

[0051] In the above formula (2), B t T1 is the count rate to be corrected, and T1 is the activation time period corresponding to the non-metallic unit to be activated. The first correction factor k1 is determined according to the above formula (1) and the following formula (3).

[0052]

[0053] The neutron dose measurement method provided in this application improves the accuracy of the correction results by determining a first correction factor through a first neutron reaction rate and a non-metallic average count rate.

[0054] In one embodiment of this application, a second correction factor is determined based on the number of rays emitted by the non-metallic unit to be activated after neutron activation and the number of rays emitted by the corresponding unit to be calibrated in the dose monitoring system or the metal unit to be activated after neutron activation; the metal unit to be activated includes a metal component and a second detection unit for detecting the number of rays emitted by the metal component after neutron activation; the first correction factor is corrected based on the second correction factor, thereby correcting the calibrated dose monitoring system.

[0055] Specifically, the second correction factor can be determined based on the number of rays emitted by the non-metallic unit to be activated after neutron activation and the corresponding unit to be corrected in the dose monitoring system, or it can be determined based on the number of rays emitted by the non-metallic unit to be activated after neutron activation and the number of rays emitted by the metallic unit to be activated after neutron activation. This application does not impose specific limitations on this.

[0056] In one embodiment of this application, the metal unit to be activated can be a gold sheet. Exemplarily, the metal unit to be activated is placed in the air at the neutron beam exit, or it can be placed in a phantom, and subjected to neutron irradiation for a certain period of time. The metal unit to be activated will undergo an activation reaction with the neutrons. After the neutron irradiation stops, a counter is used to count the correction rays emitted by the metal unit to be activated after neutron activation. Based on the number of rays emitted by the non-metal unit to be activated after neutron activation and the number of rays emitted by the metal unit to be activated after neutron activation, a second correction factor is determined. The second correction factor is used to determine whether the correction method of the metal activation method or the non-metal activation method is accurate.

[0057] Figure 3 The diagram shown is a schematic flowchart of a neutron dose measurement method provided in another exemplary embodiment of this application. Figure 1 This application extends from the embodiments shown. Figure 3 The illustrated embodiment will be described in detail below. Figure 3 The illustrated embodiments and Figure 1 The differences between the embodiments shown are not repeated here, and the similarities are not repeated here.

[0058] like Figure 3 As shown, the neutron dose measurement method provided in this application includes the following steps.

[0059] Step S21: Determine the second neutron reaction rate based on the number of rays emitted by the metal unit to be activated after neutron activation.

[0060] In one embodiment of this application, the second neutron reaction rate RR2 is determined according to the following formula (4).

[0061]

[0062] In the above formula (4), λ is the decay constant, C is the number of rays measured within the counting time (net count), N2 is the number of target nuclei of the irradiated metal unit to be activated, ε is the detection efficiency of the activation detector for the correction ray, Y is the correction ray branching ratio, f1 is the self-absorption correction factor of the correction ray, G is the flux fluctuation correction factor, and t irr t is the neutron irradiation time. c The cooling time (i.e., the time from the end of neutron irradiation to the start of radiation quantity measurement) is t. m The time for measuring the number of rays.

[0063] Step S22: Based on the count rate to be corrected, determine the average metal count rate of the metal unit to be activated during the activation time period.

[0064] In one embodiment of this application, the average metal count rate Determined according to the following formula (5).

[0065]

[0066] In the above formula (5), B t T1 represents the count rate to be calibrated, and T2 represents the activation time period corresponding to the metal unit to be activated.

[0067] Step S23: Determine the second correction factor based on the first neutron reaction rate and the average metal count rate or the second neutron reaction rate.

[0068] In one embodiment of this application, the second correction factor k2 is determined according to the following formula (6).

[0069]

[0070] In other embodiments of this application, the second correction factor may also be determined based on the ratio of the first neutron reaction rate to the second neutron reaction rate.

[0071] It should be noted that the method of determining the second correction factor by using the first neutron reaction rate and the average metal count rate or the second neutron reaction rate in the embodiments of this application is beneficial to improving the accuracy of the correction results.

[0072] Figure 4 The diagram shown is a schematic flowchart of a neutron dose measurement method provided in another exemplary embodiment of this application. Figure 1 This application extends from the embodiments shown. Figure 4 The illustrated embodiment will be described in detail below. Figure 4 The illustrated embodiments and Figure 1 The differences between the embodiments shown are not repeated here, and the similarities are not repeated here.

[0073] like Figure 4 As shown, in the neutron dose measurement method provided in this application embodiment, the step of correcting the first correction factor based on the second correction factor to correct the corrected dose monitoring system includes the following steps.

[0074] Step S41: Determine the difference information between the first correction factor and the second correction factor.

[0075] In one embodiment of this application, the difference information may be the difference between the first correction factor and the second correction factor.

[0076] Step S43: If the first correction factor is determined to meet the preset difference threshold condition based on the difference information, then the correction value corresponding to the dose monitoring system is determined based on the first correction factor.

[0077] In one embodiment of this application, the preset difference threshold condition can be 5% or 10% of the first correction factor. The specific value of the preset difference threshold condition can be set according to the actual situation, and this embodiment does not further limit it. If the difference between the first correction factor and the second correction factor is less than or equal to the preset difference threshold condition, it is determined that the first correction factor meets the preset difference threshold condition. Then, based on the product of the first correction factor and the count rate to be corrected, the correction value corresponding to the dose monitoring system is determined, i.e., the following formula (7).

[0078] B r =B t ×k1 (7)

[0079] In the above formula (7), B r This is the calibration value corresponding to the dose monitoring system.

[0080] Step S44: Determine the real-time neutron dose to the patient based on the correction value of the dose monitoring system, the dose conversion factor, and the irradiation time corresponding to the patient.

[0081] In one embodiment of this application, the real-time neutron dose to the patient is determined based on the product of the correction value corresponding to the dose monitoring system, the dose conversion factor, and the irradiation time corresponding to the patient.

[0082] The neutron dose measurement method provided in this application verifies whether the difference information between the first correction factor and the second correction factor meets the preset difference threshold condition. If it does, the correction value corresponding to the dose monitoring system is obtained based on the first correction factor, thereby improving the accuracy and reliability of the correction result of the first correction factor.

[0083] Figure 5The diagram illustrates a flowchart of an exemplary embodiment of this application, illustrating the process of determining a patient's real-time neutron dose based on a correction value corresponding to a dose monitoring system, a dose conversion factor, and the patient's irradiation time. In this application... Figure 4 This application extends from the embodiments shown. Figure 5 The illustrated embodiment will be described in detail below. Figure 5 The illustrated embodiments and Figure 4 The differences between the embodiments shown are not repeated here, and the similarities are not repeated here.

[0084] like Figure 5 As shown, in the neutron dose measurement method provided in this application embodiment, the step of determining the real-time neutron dose of the patient based on the correction value corresponding to the dose monitoring system, the dose conversion factor and the irradiation time corresponding to the patient includes the following steps.

[0085] Specifically, the dose conversion factor includes the boron dose conversion factor.

[0086] Step S441: Based on the correction value corresponding to the dose monitoring system and the boron dose conversion factor, determine the real-time dose rate correction value for cancer cells corresponding to the dose monitoring system.

[0087] In one embodiment of this application, the real-time dose rate correction value of the cancer cells corresponding to the dose monitoring system is determined based on the product of the correction value corresponding to the dose monitoring system and the boron dose conversion factor, i.e., the following formula (8).

[0088]

[0089] In the above formula (8), D t1 σ represents the real-time dose rate correction value for cancer cells (in Gy / s), and σ represents the thermal neutron reaction cross section (in cm). 2 f2 is the neutron attenuation correction factor caused by activation of the detection detector, and K is the boron dose conversion factor (in Gy × cm) for boron concentration when the flux reaches 1 ppm. 2 / ppm), N is the actual boron concentration (in ppm), and CBE is the composite biological effect factor.

[0090] Step S442: Determine the real-time neutron dose to the patient's cancer cells based on the real-time dose rate correction value of the cancer cells and the irradiation time.

[0091] In one embodiment of this application, the real-time neutron dose of the patient's cancer cells is determined based on the integral of the real-time dose rate correction value of the cancer cells over the irradiated time period, i.e., the following formula (9).

[0092]

[0093] In the above formula (9), D acm1T represents the cumulative neutron dose to the patient's cancer cells during the irradiation period (i.e., the real-time neutron dose), and T represents the irradiation time for the patient.

[0094] The neutron dose measurement method provided in this application embodiment obtains the real-time neutron dose of the patient's cancer cells, accurately assesses the neutron dose irradiated to the patient's cancer cells, and stops irradiation in a timely manner when the neutron dose reaches a preset value.

[0095] Figure 6 The diagram shown is a schematic representation of a process for determining a patient's real-time neutron dose based on a correction value corresponding to a dose monitoring system, a dose conversion factor, and the patient's irradiation time, according to another exemplary embodiment of this application. Figure 5 This application extends from the embodiments shown. Figure 6 The illustrated embodiment will be described in detail below. Figure 6 The illustrated embodiments and Figure 5 The differences between the embodiments shown are not repeated here, and the similarities are not repeated here.

[0096] like Figure 6 As shown, in the neutron dose measurement method provided in this application embodiment, the step of determining the real-time neutron dose of the patient based on the correction value corresponding to the dose monitoring system, the dose conversion factor and the irradiation time corresponding to the patient includes the following steps.

[0097] Specifically, dose switching factors include non-cancer cell dose switching factors.

[0098] Step S443: Based on the correction value corresponding to the dose monitoring system and the non-cancer cell dose conversion factor, determine the real-time dose rate correction value for the non-cancer cell corresponding to the dose monitoring system.

[0099] In one embodiment of this application, the real-time dose rate correction value for non-cancer cells corresponding to the dose monitoring system is determined based on the product of the correction value corresponding to the dose monitoring system and the dose conversion factor for non-cancer cells, as shown in the following formula (10).

[0100]

[0101] In the above formula (10), D t2 The real-time dose rate correction value for non-cancer cells is given in Gy / s, and σ is the thermal neutron reaction cross section in cm. 2 f2 is the neutron attenuation correction factor caused by the activation of the detection detector, and K t RBE is a dose switching factor for non-cancer cells and a relative biological effector.

[0102] Step S444: Determine the real-time neutron dose to the patient's non-cancerous cells based on the real-time dose rate correction value for non-cancerous cells and the irradiation time.

[0103] In one embodiment of this application, the real-time neutron dose to the non-cancer cells of the patient is determined based on the integral of the real-time dose rate correction value of the non-cancer cells over the irradiated time period, as shown in the following formula (11).

[0104]

[0105] In the above formula (11), D acm2 T represents the cumulative neutron dose (i.e., real-time neutron dose) to the patient's non-cancerous cells during the irradiation period, and T represents the irradiation time to the patient.

[0106] In practical applications, the real-time dose rate correction value for non-cancer cells is first determined based on the correction value and non-cancer cell dose conversion factor corresponding to the dose monitoring system. Then, based on the real-time dose rate correction value for non-cancer cells and the irradiation time, the real-time neutron dose to the patient's non-cancer cells is determined.

[0107] The neutron dose measurement method provided in this application provides the real-time neutron dose to the patient's non-cancer cells, accurately assesses the neutron dose irradiated to the patient's non-cancer cells, and provides more reference data for tumor treatment.

[0108] Figure 7 The diagram shown is a schematic flowchart of a neutron dose measurement method provided in another exemplary embodiment of this application. Figure 4 This application extends from the embodiments shown. Figure 7 The illustrated embodiment will be described in detail below. Figure 7 The illustrated embodiments and Figure 4 The differences between the embodiments shown are not repeated here, and the similarities are not repeated here.

[0109] like Figure 7 As shown, in the neutron dose measurement method provided in this application embodiment, before the step of determining the correction value corresponding to the dose monitoring system based on the first correction factor and the count rate to be corrected if the first correction factor meets the preset difference threshold condition based on the difference information, the following steps are also included.

[0110] Step S42: Determine whether the first correction factor meets the preset difference threshold condition based on the difference information between the first correction factor and the second correction factor.

[0111] In one embodiment of this application, if the difference between the second correction factor 8 and the first correction factor 11 is less than or equal to a preset difference threshold condition, it is determined that the second correction factor 8 meets the preset difference threshold condition, and steps S43 and S44 are executed. If the difference between the second correction factor 8 and the first correction factor 11 is greater than the preset difference threshold condition, it is determined that the second correction factor 8 does not meet the preset difference threshold condition, and the second correction factor 8 is obtained again by neutron activation of the metal unit 4 to be activated and the first correction factor 11 is obtained again by neutron activation of the non-metal unit 9 to be activated, until the second correction factor 8 meets the preset difference threshold condition.

[0112] For example, assuming the preset difference threshold is 10%, and the difference between the second correction factor 8 and the first correction factor 11 is 7%, then the difference between the second correction factor 8 and the first correction factor 11 is less than the preset difference threshold, and the second correction factor 8 is determined to meet the preset difference threshold. Conversely, assuming the difference between the second correction factor 8 and the first correction factor 11 is 13%, then the difference between the second correction factor 8 and the first correction factor 11 is greater than the preset difference threshold, and the second correction factor 8 is determined to not meet the preset difference threshold.

[0113] like Figure 7 As shown, BF3 detector 1 is placed in a beam shaping assembly (BSA) to receive neutron irradiation. Boron in BF3 detector 1 undergoes a nuclear reaction with neutrons to generate... 10 B(N,A) 7 Li, A and 7 Charged Li particles are collected by high-voltage electrodes under voltage drive, generating induced electrical pulse signals. The pulse signals are transmitted to signal processing circuit 2 via coaxial cable. Signal processing circuit 2 performs pulse amplification, filtering and shaping operations on the pulse signals. The processed pulse signals are transmitted to counter 3 for pulse counting to obtain the count rate (i.e., the count rate to be corrected). The neutron beam intensity can be measured in real time by the count rate.

[0114] However, after the boron element in BF3 detector 1 undergoes a nuclear reaction with a certain flux of neutrons, its content will gradually decrease, leading to a decrease in the sensitivity of BF3 detector 1. Therefore, the sensitivity of BF3 detector needs to be calibrated at regular intervals to ensure that the dose monitoring system operates correctly.

[0115] The specific steps for the calibration operation are as follows.

[0116] The non-metallic unit 9 to be activated is placed in the air at the neutron beam exit, or it can be placed in a phantom, and irradiated with neutrons for a certain period of time. The non-metallic unit 9 will undergo an activation reaction with the neutrons. After the neutron irradiation stops, the activated non-metallic unit is placed in front of the activation detection detector 5 of the measuring device, and the signal processing circuit 6 performs a preprocessing operation on the correction rays emitted by the non-metallic unit 9 after neutron activation, shaping the correction rays and eliminating noise. Then, the counter 3 is used to count the correction rays to obtain the first neutron reaction rate 10, and the first correction factor 11 is determined based on the first neutron reaction rate 10.

[0117] Furthermore, the metal unit 4 to be activated is placed in the air at the neutron beam exit, or it can be placed in a phantom, and subjected to neutron irradiation for a certain period of time. The metal unit 4 will undergo an activation reaction with the neutrons. After the neutron irradiation stops, the activated metal unit is placed in front of the activation detection detector 5 of the measuring device, and the signal processing circuit 6 performs preprocessing operations on the correction rays emitted by the metal unit 4 after neutron activation, shaping the correction rays and eliminating noise. Then, the counter 3 is used to count the correction rays to obtain the second neutron reaction rate 7, and the second correction factor 8 is determined based on the second neutron reaction rate 7.

[0118] It should be noted that the material of the non-metallic unit to be activated includes at least one of phosphorus, sulfur, silicon and bromine, and the correction rays emitted after the metal unit and the non-metallic unit to be activated are gamma rays and / or electron rays. The activation detection detector includes at least one of high-purity germanium, semiconductor detector, scintillator and ionization chamber detector.

[0119] Figure 8 The diagram shown is a structural schematic of a neutron dose measurement device provided in an exemplary embodiment of this application. Figure 8 As shown, the neutron dose measurement device provided in this application embodiment includes:

[0120] The first determining module 100 is used to determine the unit to be calibrated corresponding to the dose monitoring system;

[0121] The second determining module 200 is used to determine a first correction factor based on the number of rays emitted by the non-metallic unit to be activated after neutron activation and the unit to be corrected corresponding to the dose monitoring system. The non-metallic unit to be activated includes a non-metallic component and a first detection unit for detecting the number of rays emitted by the non-metallic component after neutron activation.

[0122] The third determining module 300 is used to calibrate the dose monitoring system based on the first calibration factor, thereby determining the patient's real-time neutron dose.

[0123] In one embodiment of this application, the second determining module 200 is further configured to: set the unit to be corrected to a count rate to be corrected; determine a first neutron reaction rate based on the number of correction rays emitted by the non-metallic unit to be activated after neutron activation; and determine a first correction factor based on the count rate to be corrected and the first neutron reaction rate.

[0124] In one embodiment of this application, the second determining module 200 is further configured to: determine the average count rate of nonmetals corresponding to the activation time period of the nonmetal unit to be activated based on the count rate to be corrected; and determine the first correction factor based on the first neutron reaction rate and the average count rate of nonmetals.

[0125] In one embodiment of this application, the neutron dose measurement device further includes a fourth determining module for determining a second correction factor based on the number of rays emitted by the non-metallic unit to be activated after neutron activation and the number of rays emitted by the corresponding unit to be calibrated in the dose monitoring system or by the metallic unit to be activated after neutron activation; the metallic unit to be activated includes a metallic component and a second detection unit for detecting the number of rays emitted by the metallic component after neutron activation. A fifth determining module is used to correct the first correction factor based on the second correction factor, thereby correcting the calibrated dose monitoring system.

[0126] In one embodiment of this application, the second determining module 200 is further configured to: determine a second neutron reaction rate based on the number of rays emitted by the metal unit to be activated after neutron activation; determine the average metal count rate of the metal unit to be activated during the activation time period based on the count rate to be corrected; and determine a second correction factor based on the first neutron reaction rate and the average metal count rate or the second neutron reaction rate.

[0127] In one embodiment of this application, the fifth determining module is further configured to: determine the difference information between the first correction factor and the second correction factor; if the first correction factor is determined to meet the preset difference threshold condition based on the difference information, then determine the correction value corresponding to the dose monitoring system based on the first correction factor; and determine the real-time neutron dose of the patient based on the correction value corresponding to the dose monitoring system, the dose conversion factor, and the irradiation time corresponding to the patient.

[0128] In one embodiment of this application, the fifth determining module is further configured to determine the real-time dose rate correction value of the cancer cells corresponding to the dose monitoring system based on the correction value corresponding to the dose monitoring system and the boron dose conversion factor; and to determine the real-time neutron dose of the patient's cancer cells based on the real-time dose rate correction value of the cancer cells and the irradiation time.

[0129] In one embodiment of this application, the fifth determining module is further configured to determine the real-time dose rate correction value for non-cancer cells corresponding to the dose monitoring system based on the correction value corresponding to the dose monitoring system and the dose conversion factor for non-cancer cells; and to determine the real-time neutron dose to the patient's non-cancer cells based on the real-time dose rate correction value for non-cancer cells and the irradiation time.

[0130] It should be understood that Figure 8 The operation and functions of the first determining module 100, the second determining module 200, and the third determining module 300 in the provided neutron dose measurement device can be referred to the above. Figures 1 to 7 The neutron dose measurement method provided will not be described again here to avoid repetition.

[0131] Below, for reference Figure 9 This describes an electronic device according to embodiments of the present application. Figure 9 The diagram shown is a structural schematic of an electronic device provided in an exemplary embodiment of this application.

[0132] like Figure 9 As shown, the electronic device 50 includes one or more processors 501 and memory 502.

[0133] The processor 501 may be a central processing unit (CPU) or other form of processing unit with data processing and / or instruction execution capabilities, and may control other components in the electronic device 50 to perform desired functions.

[0134] The memory 502 may include one or more computer program products, which may include various forms of computer-readable storage media, such as volatile memory and / or non-volatile memory. The volatile memory may include, for example, random access memory (RAM) and / or cache memory. The non-volatile memory may include, for example, read-only memory (ROM), hard disk, flash memory, etc. One or more computer program instructions may be stored on the computer-readable storage medium, and the processor 501 may execute the program instructions to implement the neutron dose measurement methods of the various embodiments of this application described above and / or other desired functions. Various contents, such as the count rate to be calibrated, a first correction factor, a second correction factor, and the real-time neutron dose, may also be stored in the computer-readable storage medium.

[0135] In one example, the electronic device 50 may also include an input device 503 and an output device 504, which are interconnected via a bus system and / or other forms of connection mechanism (not shown).

[0136] The input device 503 may include, for example, a keyboard, a mouse, etc.

[0137] The output device 504 can output various information to the outside, including the count rate to be calibrated, the first correction factor, the second correction factor, and the real-time neutron dose. The output device 504 may include, for example, a display, a speaker, a printer, and a communication network and its connected remote output devices, etc.

[0138] Of course, for the sake of simplicity, Figure 9 Only some of the components of the electronic device 50 relevant to this application are shown in this illustration; components such as buses, input / output interfaces, etc., are omitted. In addition, the electronic device 50 may include any other suitable components depending on the specific application.

[0139] In addition to the methods and apparatus described above, embodiments of this application may also be computer program products, which include computer program instructions that, when executed by a processor, cause the processor to perform the steps in the neutron dose measurement methods according to the various embodiments of this application described above.

[0140] The computer program product can be written in any combination of one or more programming languages ​​to perform the operations of the embodiments of this application. The programming languages ​​include object-oriented programming languages ​​such as Java and C++, as well as conventional procedural programming languages ​​such as C or similar languages. The program code can be executed entirely on the user's computing device, partially on the user's computing device, as a standalone software package, partially on the user's computing device and partially on a remote computing device, or entirely on a remote computing device or server.

[0141] Furthermore, embodiments of this application may also be computer-readable storage media storing computer program instructions thereon, which, when executed by a processor, cause the processor to perform the steps in the neutron dose measurement methods according to the various embodiments of this application described above.

[0142] The computer-readable storage medium may be any combination of one or more readable media. A readable medium may be a readable signal medium or a readable storage medium. A readable storage medium may, for example, include, but is not limited to, electrical, magnetic, optical, electromagnetic, infrared, or semiconductor systems, apparatuses, or devices, or any combination thereof. More specific examples of readable storage media (a non-exhaustive list) include: electrical connections having one or more wires, portable disks, hard disks, random access memory (RAM), read-only memory (ROM), erasable programmable read-only memory (EPROM or flash memory), optical fibers, portable compact disk read-only memory (CD-ROM), optical storage devices, magnetic storage devices, or any suitable combination thereof.

[0143] The basic principles of this application have been described above with reference to specific embodiments. However, it should be noted that the advantages, benefits, and effects mentioned in this application are merely examples and not limitations, and should not be considered as essential features of each embodiment of this application. Furthermore, the specific details disclosed above are for illustrative and facilitative purposes only, and are not limitations. These details do not limit the application to the necessity of employing the aforementioned specific details for implementation.

[0144] The block diagrams of devices, apparatuses, devices, and systems involved in this application are merely illustrative examples and are not intended to require or imply that they must be connected, arranged, or configured in the manner shown in the block diagrams. As those skilled in the art will recognize, these devices, apparatuses, devices, and systems can be connected, arranged, and configured in any manner. Words such as “comprising,” “including,” “having,” etc., are open-ended terms meaning “including but not limited to,” and are used interchangeably with them. The terms “or” and “and” as used herein refer to the terms “and / or,” and are used interchangeably with them unless the context clearly indicates otherwise. The term “such as” as used herein refers to the phrase “such as but not limited to,” and is used interchangeably with it.

[0145] It should also be noted that in the apparatus, equipment, and methods of this application, the components or steps can be disassembled and / or recombined. These disassemblies and / or recombinations should be considered as equivalent solutions of this application.

[0146] The above description of the disclosed aspects is provided to enable any person skilled in the art to make or use this application. Various modifications to these aspects will be readily apparent to those skilled in the art, and the general principles defined herein can be applied to other aspects without departing from the scope of this application. Therefore, this application is not intended to be limited to the aspects shown herein, but rather to be accorded the widest scope consistent with the principles and novel features disclosed herein.

[0147] The above description has been given for purposes of illustration and description. Furthermore, this description is not intended to limit the embodiments of this application to the forms disclosed herein. Although numerous exemplary aspects and embodiments have been discussed above, those skilled in the art will recognize certain variations, modifications, alterations, additions, and sub-combinations thereof.

Claims

1. A method for measuring neutron dosage, characterized in that, include: Identify the unit to be calibrated corresponding to the dose monitoring system; Based on the number of rays emitted by the non-metallic unit to be activated after neutron activation and the unit to be calibrated corresponding to the dose monitoring system, a first calibration factor is determined, wherein the non-metallic unit to be activated includes a non-metallic component and a first detection unit for detecting the number of rays emitted by the non-metallic component after neutron activation. The dose monitoring system is calibrated based on the first correction factor to determine the patient's real-time neutron dose. A second correction factor is determined based on the number of rays emitted by the non-metallic unit to be activated after neutron activation and the number of rays emitted by the corresponding unit to be calibrated in the dose monitoring system or the metal unit to be activated after neutron activation; the metal unit to be activated includes a metal component and a second detection unit for detecting the number of rays emitted by the metal component after neutron activation. The first correction factor is corrected based on the second correction factor, thereby correcting the dose monitoring system after correction.

2. The neutron dose measurement method according to claim 1, characterized in that, The unit to be calibrated is set to the count rate to be calibrated; the determination of the first calibration factor based on the number of rays emitted by the non-metallic unit to be activated after neutron activation and the unit to be calibrated corresponding to the dose monitoring system includes: The first neutron reaction rate is determined based on the number of rays emitted by the non-metallic unit to be activated after neutron activation. A first correction factor is determined based on the count rate to be corrected and the first neutron reaction rate.

3. The neutron dose measurement method according to claim 2, characterized in that, The determination of the first correction factor based on the count rate to be corrected and the first neutron reaction rate includes: Based on the count rate to be corrected, determine the average count rate of non-metals for the activation time period corresponding to the non-metallic unit to be activated; The first correction factor is determined based on the first neutron reaction rate and the average count rate of the nonmetal.

4. The neutron dose measurement method according to claim 2, characterized in that, The determination of the second correction factor based on the number of rays emitted by the non-metallic unit to be activated after neutron activation and the number of rays emitted by the corresponding unit to be corrected or the metallic unit to be activated after neutron activation in the dose monitoring system includes: The second neutron reaction rate is determined based on the number of rays emitted by the metal unit to be activated after neutron activation. Based on the count rate to be corrected, determine the average metal count rate of the metal unit to be activated during the activation time period; The second correction factor is determined based on the first neutron reaction rate and the average metal count rate or the second neutron reaction rate.

5. The neutron dose measurement method according to claim 1, characterized in that, The step of correcting the first correction factor based on the second correction factor, thereby correcting the corrected dose monitoring system, includes: Determine the difference information between the first correction factor and the second correction factor; If it is determined based on the difference information that the first correction factor meets the preset difference threshold condition, then based on the first correction factor, the correction value corresponding to the dose monitoring system is determined; Based on the correction value of the dose monitoring system, the dose conversion factor, and the irradiation time of the patient, the real-time neutron dose of the patient is determined.

6. The neutron dose measurement method according to claim 5, characterized in that, The dose conversion factor includes a boron dose conversion factor. Determining the real-time neutron dose to the patient based on the correction value corresponding to the dose monitoring system, the dose conversion factor, and the patient's irradiation time includes: Based on the correction value and the boron dose conversion factor, the real-time dose rate correction value for cancer cells corresponding to the dose monitoring system is determined; The real-time neutron dose to the patient's cancer cells is determined based on the real-time dose rate correction value of the cancer cells and the irradiation time.

7. The neutron dose measurement method according to claim 5, characterized in that, The dose conversion factor includes a non-cancer cell dose conversion factor. Determining the real-time neutron dose to the patient based on the correction value corresponding to the dose monitoring system, the dose conversion factor, and the patient's irradiation time includes: Based on the correction value corresponding to the dose monitoring system and the non-cancer cell dose conversion factor, determine the real-time dose rate correction value for the non-cancer cell corresponding to the dose monitoring system; The real-time neutron dose to the non-cancerous cells of the patient is determined based on the real-time dose rate correction value for the non-cancerous cells and the irradiation time.

8. The neutron dose measurement method according to claim 1, characterized in that, The material of the non-metallic unit to be activated includes at least one of phosphorus, sulfur, silicon, and bromine.

9. A neutron dose measuring device, characterized in that, include: The first determining module is used to determine the unit to be calibrated corresponding to the dose monitoring system; The second determining module is used to determine a first correction factor based on the number of rays emitted by the non-metallic unit to be activated after neutron activation and the unit to be corrected corresponding to the dose monitoring system. The non-metallic unit to be activated includes a non-metallic component and a first detection unit for detecting the number of rays emitted by the non-metallic component after neutron activation. The third determining module is used to calibrate the dose monitoring system based on the first calibration factor, thereby determining the patient's real-time neutron dose. The fourth determining module is used to determine a second correction factor based on the number of rays emitted by the non-metallic unit to be activated after neutron activation and the number of rays emitted by the unit to be calibrated corresponding to the dose monitoring system or the metal unit to be activated after neutron activation; wherein, the metal unit to be activated includes a metal component and a second detection unit for detecting the number of rays emitted by the metal component after neutron activation; The fifth determining module is used to correct the first correction factor based on the second correction factor, thereby correcting the corrected dose monitoring system.

Images