21 results about "Neutron dose" patented technology

The invention provides a neutron dose evaluation method and system based on mobile phone neutron activation product analysis, and the method comprises the steps: constructing an equivalent medium model for replacing a real mobile phone, and carrying out the neutron energy spectrum solving through the mobile phone activation product. The neutron energy spectrum can be reconstructed on site in daily scenes without professional equipment, such as villages, streets and shopping malls, so that the uncertainty of individual dose is reduced to a level equivalent to that of a laboratory spectrometer, the dependence on a multi-ball spectrometer, a TOF spectrometer and professionals is thoroughly eliminated, rapid and accurate measurement of the neutron energy spectrum and large-scale population dose evaluation are realized, and the accuracy of the neutron energy spectrum is improved. And a basis is provided for delimiting the influence range of the nuclear event, judging the event level of the nuclear event and formulating a hierarchical medical rescue scheme.

The invention provides a neutron energy spectrum reconstruction method and a neutron dose evaluation method based on a lithium ion battery. The neutron energy spectrum reconstruction method comprises the following steps: acquiring the lithium ion battery after neutron irradiation and the initial total activity of each activation product of the lithium ion battery; obtaining an initialized neutron energy spectrum; based on the initialized neutron energy spectrum, obtaining a theoretical activation reaction rate of each activation product of the lithium ion battery to be detected; setting a discretization equation, and iteratively updating the energy spectrum by taking a condition that the standard deviation between the activation reaction rate of the dominant reaction of each metal element of the lithium ion battery and the pre-acquired corresponding theoretical activation reaction rate is smaller than a preset threshold value as a convergence condition; and obtaining the neutron energy spectrum of the lithium ion battery after neutron irradiation. According to the invention, the lithium ion battery is used as a portable activation detector, the neutron energy spectrum of an illuminated position can be reconstructed in a daily scene, and rapid and accurate measurement of the neutron energy spectrum is realized.

The invention relates to the technical field of neutron measurement, and particularly discloses a multi-activation foil and method for measuring a neutron energy spectrum. The multi-activation foil comprises a shell and an activation sheet placed in the shell, and the activation sheet sequentially comprises Ni, Sc, Au, W, Cu, Pt, In, Zn and Fe from top to bottom. The activated foil can realize high-resolution measurement of a neutron spectrum in a very small space, has the characteristics of size miniaturization, wide energy response range, wide neutron fluence rate application range, controllable manufacturing tolerance, optimized material ratio and the like, and is suitable for neutron spectrum and neutron dose measurement of a small-scale region of a nuclear facility and neutron dose measurement of a small-scale region of a nuclear facility. The method can also be popularized and applied to fine dose field distribution measurement of a large-scale area of a nuclear facility, and provides accurate data support for safe operation, shielding verification and radiation protection of the nuclear facility.

This invention relates to the field of neutron dose monitoring, specifically to a method and apparatus for monitoring the dose equivalent around neutrons over a wide energy range. The apparatus includes an outer moderator, a thermal neutron absorbing layer, a high-energy neutron compensation layer, and an inner moderator. The high-energy neutron compensation layer is composed of a heavy metal material capable of undergoing a significant neutron multiplication reaction with ultra-high-energy neutrons. The thermal neutron detector is a radiation-resistant solid-state semiconductor detector, comprising a silicon carbide semiconductor substrate and an enrichment layer closely adhering to its surface. 6 The device is equipped with a lithium fluoride thermal neutron converter; an initial thermal neutron detector group is deployed within the device to collect thermal neutron fluence information under different slowing degrees; based on the initial thermal neutron detector group, position optimization and weight coefficient output are performed, and multiple groups of thermal neutron detectors in the first depth order are selected to make the total dose response flat in a wide energy range for dose equivalent monitoring.

The present application relates to neutron dosimetry method, specifically provide a kind of for boron neutron capture therapy fast neutron dosimetry method, by using the paired ionization chamber test system with different liquid environment, one kind of liquid environment has obvious absorption to thermal neutron, then the radiation source under the same power is measured, to obtain more accurate fast neutron dose and the rest two kinds of mixed radiation dose, to solve the problem of inaccurate neutron dose test of different kinds in the prior art in the application process of mixed radiation field, more accurate mixed radiation quantity value can be obtained, so that the different types of neutron dose in mixed radiation field are grasped, so as to improve the radiation effect in the application scene of mixed radiation field.

The invention discloses a neutron-gamma dosimeter based on double detectors and a gamma and neutron dose rate detection method, the neutron-gamma dosimeter comprises a gamma detector, a neutron-gamma detector and a processing module, the gamma detector can only respond to gamma rays and output signals, and the neutron-gamma dosimeter can only respond to the gamma rays and output signals. The neutron-gamma detector can respond to neutrons and gamma rays and output signals, and the processing module can receive the signals of the gamma detector and the neutron-gamma detector, determine the gamma dose rate based on the output signals of the gamma detector, and determine the dose rate of the neutron-gamma detector based on the difference value of the output signals of the gamma detector and the neutron-gamma detector. And determining the neutron dose rate. According to the invention, through combination of the gamma detector and the neutron gamma detector, simultaneous monitoring and dose separation of neutrons and gamma rays are realized, doses of two radiation types can be accurately measured and distinguished, and use requirements in various complex environments are met.

Disclosed is a neutron capture therapy apparatus. The neutron capture therapy apparatus is used for irradiating a neutron beam with a preset neutron dose to an object to be irradiated. The neutron beam enters the object and undergoes a nuclear reaction with boron in the object. The neutron capture therapy apparatus includes a correction system for correcting the preset neutron dose.

The invention discloses a neutron beam dynamic regulation and control method and system in a BNCT process, and the method comprises the following steps: constructing a neutron beam-out regulation and control model, and obtaining a mapping relation between the intensity of a neutron beam and a neutron dose rate; dynamically monitoring the boron concentration of the tumor tissue and the boron concentration of the normal tissue to obtain a real-time T / N value; converting the T / N value into neutron beam intensity in real time, and substituting the neutron beam intensity into the neutron beam output regulation and control model to obtain a real-time neutron dose rate; comparing the obtained real-time neutron dose rate with a preset neutron dose rate, and if there is a difference between the real-time neutron dose rate and the preset neutron dose rate, adjusting neutron source parameters until the real-time neutron dose rate is consistent with the preset neutron dose rate; and the step S2 to the step S4 are repeated, and neutron beam dynamic regulation and control in the BNCT process are achieved. According to the invention, the technical problem that the neutron outgoing beam regulation and control precision and efficiency are low due to the fact that the real-time change of the boron concentration is not considered in the prior art can be solved.

The utility model discloses a neutron dose rate monitoring auxiliary device which comprises a box body, one side of the top of the box body is rotatably connected with a top cover through a hinge, a partition plate is fixed in the box body and divides the interior of the box body into two containing cavities, a pressing assembly is installed on the lower surface of the top cover, and the pressing assembly is connected with the top cover through a hinge. Two side plates are fixed to one side of the outer side wall of the box body, and a mounting assembly is rotationally connected between the two side plates. According to the neutron dose equivalent rate instrument, the box body, the top cover, the pressing assembly and the mounting assembly are arranged, when not used, the neutron dose equivalent rate instrument can be stored in the box body and extruded and fixed through the pressing assembly, shaking of the neutron dose equivalent rate instrument in the box body is avoided, and when needing to be used, a host of the neutron dose equivalent rate instrument can be placed on the surface of the top cover; the positioning sleeve is used for positioning and fixing the neutron dose equivalent rate, and the handheld operating handle is fixed through the mounting assembly, so that the neutron dose equivalent rate is more convenient to use.

The invention relates to the field of neutron dose monitoring, in particular to a wide-energy-region neutron surrounding dose equivalent monitoring method and device. The device comprises an outer-layer moderator, a thermal neutron absorption layer, a high-energy neutron compensation layer and an inner-layer moderator, wherein the high-energy neutron compensation layer is made of a heavy metal material which can generate a remarkable neutron multiplication reaction with ultrahigh-energy neutrons; the thermal neutron detector is a radiation-resistant solid-state semiconductor detector and comprises a silicon carbide semiconductor substrate and a < 6 > Li-enriched lithium fluoride thermal neutron converter tightly attached to the surface of the silicon carbide semiconductor substrate; an initial thermal neutron detector group used for collecting thermal neutron fluence information under different moderation degrees is arranged in the device. And based on the initial thermal neutron detector group, performing position optimization and weight coefficient output, and selecting a plurality of groups of thermal neutron detectors in a first depth order, so that the total dose response is flat in a wide energy region and dose equivalent monitoring is performed.

1. Name of the product in this design: Portable Neutron Dosimeter Alarm (NC-HAW-ZN13). 2. Purpose of this design: An instrument for radiation detection and alarm. 3. The key design feature of this product is its shape. 4. The image or photograph that best illustrates the design's key points: 3D view 1.

The invention provides a neutron dose response determination method and device, a storage medium and a product. The method comprises the following steps: obtaining a first neutron energy spectrum for a first emergence angle and a second neutron energy spectrum for a second emergence angle, wherein the second emergence angle is different from the first emergence angle; determining an energy spectrum correction factor based on the first neutron energy spectrum and the second neutron energy spectrum; obtaining a first indicating value of the neutron dose measurement equipment to be calibrated for the first emergence angle and a second indicating value of the neutron dose measurement equipment to be calibrated for the second emergence angle; determining a dose measurement value of the neutron dose measurement equipment to be calibrated based on the energy spectrum correction factor, the first indication value and the second indication value; and determining the neutron dose response of the neutron dose measurement equipment to be calibrated based on the dose measurement value and the agreed quantity value.

The invention relates to the technical field of data real-time monitoring, in particular to a real-time dose monitoring system and method for a boron neutron capture therapy device. The method comprises the steps that a main detector and an auxiliary detector are divided, the positions of the detectors are arranged, the neutron dose of each position is monitored in real time, and a multi-layer shielding structure is configured for the detectors; collecting six paths of redundant signals, and transmitting the redundant signals; according to the equipment connection and communication state, the dosage and the time monitoring data, the beam stopping condition is judged, and beam stopping reason data is obtained; calibrating a scale factor of the detector, and performing grading processing according to deviation data; storing real-time monitoring data, executing a calling request, and tracing a treatment process; the system comprises a detection deployment and shielding optimization module, a redundant signal acquisition module, a beam stop logic judgment module, a calibration and deviation processing module and a data tracing module. By means of the mode, the reliability and accuracy of real-time dose monitoring in boron neutron capture therapy are improved.

This invention relates to the field of radiation monitoring technology and discloses a method and system for real-time monitoring of radiation dose throughout the At-211 production process. The method includes: simultaneously acquiring gamma ray dose rate and neutron dose rate in real time at at least three fixed spatial points at 0 degrees, 90 degrees, and 180 degrees from the proton beam axis outside the bombardment cavity of the proton beam bombardment target; simultaneously acquiring the proton beam intensity in real time during the proton beam transmission process; generating dose monitoring instructions that can determine whether the radiation dose is abnormal or normal through multi-step collaborative analysis, accurately reflecting the internal and external radiation situation and potential abnormal risks, effectively avoiding the influence of signal lag or distortion from external radiation detectors, and thus accurately capturing changes in radiation dose within the bombardment cavity caused by instantaneous fluctuations in proton beam intensity, ensuring the health and safety of radiation during the bombardment process and the entire At-211 production process.

Provided is a neutron beam irradiation device with which it is possible to cause a lesion located at a deeper position from the body surface to absorb a neutron beam dose sufficient for treatment, without increasing the neutron beam exposure dose of normal cells. In order to achieve the above, this neutron beam irradiation device 100 comprises: a plurality of heads 1, each of the heads having a built-in accelerator neutron source and being capable of independently emitting a neutron beam; and a control unit 3 for controlling the heads 1. The heads 1 are arranged so that the neutron beams B emitted from the respective heads 1 are directed toward a lesion C. The control unit 3 causes the neutron beams B to be emitted from the heads 1 simultaneously or at staggered timings within one neutron beam irradiation cycle.

The invention relates to the technical field of radiation monitoring, and discloses a whole-course radiation dose real-time monitoring method and system for an At-211 production process, and the method comprises the steps: carrying out the real-time monitoring of the whole-course radiation dose on the periphery of a bombardment cavity of a proton beam bombardment target material at least at three fixed space point positions which form 0 degree, 90 degrees and 180 degrees with the axis of a proton beam, the gamma ray dose rate and the neutron dose rate are synchronously obtained in real time, and the proton beam intensity is obtained in real time in the proton beam transmission process; through collaborative analysis of a plurality of steps, a dose monitoring instruction capable of judging that the radiation dose is abnormal or normal is generated, internal and external radiation situations and potential abnormal risks are accurately reflected, and the influence of signal lag or distortion of an external radiation detector is effectively avoided; furthermore, the radiation dose change in the bombardment cavity caused by the instantaneous fluctuation of the proton beam intensity is accurately captured, and the health and safety of the At-211 production bombardment link and the whole process radiation are ensured.

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.

A neutron capture therapy device and a corresponding correction method for a neutron capture therapy device. The neutron capture therapy device comprises a neutron dose measurement apparatus (21) and a correction system (3) for correcting the neutron dose measurement apparatus (21), wherein the neutron dose measurement apparatus (21) comprises a detector (211) used to receive neutrons and output electrical signals, a signal processing unit (212) used to process the electrical signals output from the detector (211) and convert the electrical signals into pulse signals, and a counter (213) used to count the pulse signals output from the signal processing unit (212) to obtain a count rate.

The application provides a lithium-ion battery-based neutron spectrum reconstruction method and a neutron dose evaluation method. The neutron spectrum reconstruction method comprises the following steps: obtaining a lithium-ion battery irradiated by neutrons and initial total activity of each activation product of the lithium-ion battery; obtaining an initial neutron spectrum; and based on the initial neutron spectrum, obtaining a theoretical activation reaction rate of each activation product of the lithium-ion battery to be detected; setting a discretization equation, taking the standard deviation between the activation reaction rate of the dominant reaction of each metal element of the lithium-ion battery and the corresponding theoretical activation reaction rate obtained in advance being less than a preset threshold as a convergence condition, and iteratively updating the spectrum; and obtaining the neutron spectrum of the lithium-ion battery irradiated by neutrons. The lithium-ion battery is used as a "portable activation detector", and the neutron spectrum of the irradiated position can be reconstructed on site in a daily scene, so that the neutron spectrum can be measured quickly and accurately.

The invention discloses a reinforcement learning-based multi-target reactor radiation shielding design method. The method comprises the following steps of defining a multi-target optimization problem and constraint conditions; coding the shielding layer structure to obtain a layer vector; sampling multiple times in the parameter optimization range of the layer vector to obtain a plurality of sample schemes, respectively simulating neutron doses corresponding to the sample schemes, and respectively calculating mass, volume and construction cost corresponding to the sample schemes to obtain a training data set; the training data set is utilized, an NSGA-III multi-target optimization algorithm based on reinforcement learning, dose simulation and dose prediction is adopted, and a multi-target reactor radiation shielding design model is obtained through training; and inputting condition parameters in the multi-target reactor radiation shielding design model, and outputting a Pareto frontier shielding design scheme set meeting dose constraints. According to the method, on the premise of ensuring radiation safety, material consumption and comprehensive cost can be effectively reduced, and calculation efficiency and solution diversity are both considered.