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CN-116338760-B - Neutron dose measuring method and device

CN116338760BCN 116338760 BCN116338760 BCN 116338760BCN-116338760-B

Abstract

The application provides a neutron dose measurement method, which comprises the steps of determining a unit to be corrected corresponding to a dose monitoring system, determining a first correction factor based on the quantity of rays emitted by a nonmetallic unit to be activated after neutron activation and the unit to be corrected corresponding to the dose monitoring system, and correcting the dose monitoring system based on the first correction factor so as to determine the neutron real-time dose of a patient. According to the application, the sensitivity of the dose monitoring system is corrected by determining the first correction factor, so that the neutron real-time dose of the patient is determined, the measurement error caused by the sensitivity reduction or the position change of the dose monitoring system is avoided, and the accuracy and the reliability of the measurement result are improved. In another aspect, the application provides a neutron dose measurement device corresponding to the method.

Inventors

  • WANG CHAO
  • LIU YUANHAO

Assignees

  • 中硼(厦门)医疗器械有限公司

Dates

Publication Date
20260512
Application Date
20211222

Claims (9)

  1. 1. A neutron dose measurement method, comprising: determining a unit to be corrected corresponding to the dose monitoring system; determining a first correction factor based on the quantity of rays emitted by a nonmetallic unit to be activated after neutron activation and a unit to be corrected corresponding to the dose monitoring system, wherein the nonmetallic unit to be activated comprises a nonmetallic member and a first detection part for detecting the quantity of rays emitted by the nonmetallic member after neutron activation; Correcting the dose monitoring system based on the first correction factor to determine a neutron real-time dose for the patient; Determining a second correction factor based on the quantity of rays emitted by the non-metal unit to be activated after neutron activation and the quantity of rays emitted by the unit to be corrected corresponding to the dose monitoring system or the quantity of rays emitted by the metal unit to be activated after neutron activation; and correcting the first correction factor based on the second correction factor, thereby correcting the corrected dose monitoring system.
  2. 2. The neutron dose measurement method of claim 1, wherein the unit to be corrected is set to a count rate to be corrected, and wherein the determining the first correction factor based on the number of rays emitted by the nonmetallic unit to be activated after neutron activation and the unit to be corrected corresponding to the dose monitoring system comprises: Determining a first neutron reaction rate based on the quantity of rays emitted by the nonmetallic unit to be activated after neutron activation; And determining a first correction factor based on the count rate to be corrected and the first neutron reaction rate.
  3. 3. The neutron dose measurement method of claim 2, wherein the determining a first correction factor based on the count rate to be corrected and the first neutron reaction rate comprises: determining a nonmetallic average counting rate of an activation time period corresponding to the nonmetallic unit to be activated based on the counting rate to be corrected; the first correction factor is determined based on the first neutron reaction rate and the nonmetallic average count rate.
  4. 4. The neutron dose measurement method of claim 2, wherein the determining the second correction factor based on the number of rays emitted from the nonmetallic cell to be activated by neutrons and the number of rays emitted from the cell to be corrected corresponding to the dose monitoring system or the metallic cell to be activated by neutrons comprises: Determining a second neutron reaction rate based on the quantity of rays emitted by the metal unit to be activated after neutron activation; Determining the average metal counting rate of the activation time period corresponding to the metal unit to be activated based on the counting rate to be corrected; the second correction factor is determined based on the first neutron reaction rate and the metal average count rate or the second neutron reaction rate.
  5. 5. The neutron dose measurement method of claim 1, wherein the correcting the first correction factor based on the second correction factor, thereby correcting the corrected dose monitoring system comprises: determining difference information between the first correction factor and the second correction factor; If the first correction factor accords with a preset difference threshold condition based on the difference information, determining a correction value corresponding to the dose monitoring system based on the first correction factor; A neutron real-time dose of the patient is determined based on the correction value corresponding to the dose monitoring system, the dose conversion factor, and the irradiated time corresponding to the patient.
  6. 6. The neutron dose measurement method of claim 5, wherein the dose conversion factor comprises a boron dose conversion factor, the determining the neutron real-time dose for the patient based on the correction value for the dose monitoring system, the dose conversion factor, and the corresponding irradiated time for the patient comprising: Determining a real-time cancer cell dose rate correction value corresponding to the dose monitoring system based on the correction value and the boron dose conversion factor; Determining a neutron real-time dose of cancer cells of the patient based on the cancer cell real-time dose rate correction value and the irradiated time.
  7. 7. The neutron dose measurement method of claim 5, wherein the dose conversion factors include non-cancerous cell dose conversion factors, the determining the neutron real-time dose for the patient based on the correction values for the dose monitoring system, the dose conversion factors, and the corresponding irradiated times for the patient comprising: determining a real-time non-cancer cell dose rate correction value 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; determining a neutron real-time dose of non-cancerous cells of the patient based on the non-cancerous cell real-time dose rate correction value and the irradiated time.
  8. 8. The neutron dose measurement method of claim 1, wherein the material of the nonmetallic cell to be activated includes at least one of phosphorus, sulfur, silicon, and bromine.
  9. 9. A neutron dose measurement device, comprising: the first determining module is used for determining a unit to be corrected corresponding to the dose monitoring system; the second determining module is used for determining a first correction factor based on the quantity of rays emitted by the nonmetallic unit to be activated after neutron activation and the unit to be corrected corresponding to the dose monitoring system, wherein the nonmetallic unit to be activated comprises a nonmetallic member and a first detecting part used for detecting the quantity of rays emitted by the nonmetallic member after neutron activation; a third determination module for correcting the dose monitoring system based on the first correction factor, thereby determining a neutron real-time dose of the patient; The fourth determining module is used for determining a second correction factor based on the quantity of rays emitted by the nonmetallic unit to be activated after neutron activation and the quantity of rays emitted by the unit to be corrected corresponding to the dose monitoring system or the quantity of rays emitted by the metallic unit to be activated after neutron activation, wherein the metallic unit to be activated comprises a metallic member and a second detecting part used for detecting the quantity of rays emitted by the metallic member after neutron activation; And a fifth determining module, configured to correct the first correction factor based on the second correction factor, so as to correct the corrected dose monitoring system.

Description

Neutron dose measuring method and device Technical Field The application relates to the technical field of neutron dose measurement, in particular to a neutron dose measurement method and device. Background The dose monitoring system is used as both eyes of boron neutron capture treatment (Boron Neutron Capture Therapy, BNCT), plays an important role in the whole tumor treatment process, and can evaluate the neutron dose irradiated by a patient, and stop irradiation when the neutron dose reaches a preset value. However, although the existing dose monitoring system can measure the neutron real-time dose of a patient, after a certain time is measured, the sensitivity of the dose monitoring system is reduced, and errors occur in the measurement result, so that the irradiation time cannot be accurately controlled according to the preset value of the neutron dose. Disclosure of Invention The present application has been made to solve the above-mentioned technical problems. The embodiment of the application provides a neutron dose measuring method and device. In a first aspect, an embodiment of the application provides a neutron dose measurement method, which comprises the steps of determining a unit to be corrected corresponding to a dose monitoring system, determining a first correction factor based on the quantity of rays emitted by a nonmetallic unit to be activated after neutron activation and the unit to be corrected corresponding to the dose monitoring system, wherein the nonmetallic unit to be activated comprises a nonmetallic member and a first detection part for detecting the quantity of rays emitted by the nonmetallic member after neutron activation, and correcting the dose monitoring system based on the first correction factor, so that the neutron real-time dose of a patient is determined. With reference to the first aspect, in some implementations of the first aspect, the unit to be corrected is set to a count rate to be corrected, a first neutron reaction rate is determined based on a number of rays emitted by the nonmetallic unit to be activated after neutron activation, and a first correction factor is determined based on the count rate to be corrected and the first neutron reaction rate. With reference to the first aspect, in some implementations of the first aspect, a nonmetallic average count rate of an activation time period corresponding to nonmetallic units to be activated is determined based on the count rate to be corrected, and a first correction factor is determined based on the first neutron reaction rate and the nonmetallic average count rate. With reference to the first aspect, in some implementations of the first aspect, a second correction factor is determined based on a number of rays emitted by the nonmetallic unit to be activated after neutron activation and a number of rays emitted by a unit to be corrected corresponding to the dose monitoring system or by neutron activation of the metallic unit to be activated, the metallic unit to be activated includes a metallic member and a second detection portion for detecting the number of rays emitted by the metallic member after neutron activation, and the first correction factor is corrected based on the second correction factor, so that the corrected dose monitoring system is corrected. With reference to the first aspect, in some implementations of the first aspect, the second neutron reaction rate is determined based on a number of rays emitted by the metal unit to be activated after neutron activation, the average metal count rate of the activation time period corresponding to the metal unit to be activated is determined based on the count rate to be corrected, and the second correction factor is determined based on the first neutron reaction rate and the average metal count rate or the average metal count rate and the second neutron reaction rate. With reference to the first aspect, in some implementations of the first aspect, the first correction factor is corrected based on the second correction factor, so as to correct the corrected dose monitoring system, including determining difference information between the first correction factor and the second correction factor, determining a correction value corresponding to the dose monitoring system based on the first correction factor if the first correction factor is determined to meet a preset difference threshold condition based on the difference information, and determining a neutron real-time dose of the patient based on the correction value corresponding to the dose monitoring system, the dose conversion factor, and an irradiated time corresponding to the patient. With reference to the first aspect, in certain implementations of the first aspect, the dose conversion factor includes a boron dose conversion factor, and determining the neutron real-time dose of the patient based on the correction value corresponding to the dose monitoring system, the dose conversion factor, and the