50 results about "Neutron dose" patented technology

Disclosed are a neutron dose measurement apparatus and a neutron capturing treatment device. The neutron dose measurement apparatus includes a measurement unit for receiving neutrons and outputting signals, a signal processing unit for processing the signals output from the measurement unit, a counter for counting the signals output from the signal processing unit to obtain a count rate, and a count rate correction unit for correcting the count rate.

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 application provides a parameterized real-time measurement method for field neutron energy spectrum and dose, which comprises the following steps: using a three-section function model to represent the field neutron energy spectrum; constructing simulated field neutron energy spectrums of multiple moderation levels, and using a detector to measure and calculate a thermal-fast ratio; simulating and calculating the simulated field neutron energy spectrum of a test point by using a Monte Carlo model to obtain model parameters; establishing a corresponding relationship between the model parameters and the thermal-fast ratio; measuring the fast neutron pulse count rate and the thermal neutron pulse count rate by using the detector in the field, determining the value of the model parameters by looking up a table or interpolation, and the like according to the corresponding relationship between the model parameters and the thermal-fast ratio; calculating the field neutron energy spectrum according to the model parameters, and calculating the field neutron dose by using the field neutron energy spectrum and a neutron fluence-dose conversion coefficient.

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 present invention discloses a dose calibration system and method for a wide-energy-spectrum neutron radiation detector. The system comprises a neutron target device, a deflection system, a beam waste bin, a neutron collimator, and a test bench, which are sequentially arranged. The neutron target device is used to generate high-yield neutrons; the deflection system is used to deflect the proton beam remaining after passing through the neutron target device; the beam waste bin is used to collect and shield the deflected proton beam and radiation field; the neutron collimator is used to shield the background neutron radiation field that needs to be eliminated; and the test bench is used to calibrate the high-energy, narrow-spectrum neutron dose after the background neutron radiation field is eliminated. This solution can improve the accuracy of high-energy neutron dose calibration for a wide-energy-spectrum neutron radiation detector.

The invention relates to a neutron dose calculation method, device and equipment and a readable storage medium, and belongs to the technical field of boron neutron capture therapy dose calculation.The method comprises the steps that an initial voxel grid model generated based on medical image information is obtained, the initial voxel grid model comprises multiple voxels, and the multiple voxels comprise air voxels; cutting all air voxels in the initial voxel grid model to generate a target voxel grid model; a plurality of source particles used for Monte Carlo simulation are obtained, the plurality of source particles are simulated in the target voxel grid model based on an event-based Monte Carlo algorithm, a neutron dose distribution result of the target voxel grid model is obtained, and the neutron dose distribution result comprises the neutron dose of each voxel in the target voxel grid model. According to the method, the air voxels are accurately cut, so that the efficiency and the accuracy of Monte Carlo simulation are improved, and the neutron dose can be calculated more quickly and accurately.

The present invention discloses a neutron radiation-proof glass and a preparation method thereof. The neutron radiation-proof glass comprises, by weight, the following components: SiO2: 0.5-3.5%; B2O3: 20.0-35.0%; Li2O: 0.5-9.0%; Na2O: 0.1-5.0%; Gd2O3: 31.0-40.0%; Y2O3: 11.0-19.0%; GeO2: 0.1-9.0%; Nb2O5: 0.1-5.0%; ZnO: 0.5-5.0%; CeO2: 1.0-9.0%; WO3: 0.5-5.0%; and In2O3: 1.0-2.0%. By rationally configuring the components and their contents, the present invention achieves a 550nm transmittance greater than 80% and a Knoop hardness greater than 600×10 7 MPa, the glass thickness required to reduce the neutron dose rate to 50% is less than 30 mm, and the neutron radiation-proof glass of the present invention can effectively protect against neutron radiation. The obtained neutron radiation-proof glass has good radiation protection, glass forming properties, and chemical stability, and the optical uniformity of the neutron radiation-proof glass can reach 5×10 ‑6 , it is easy to prepare large-sized and highly uniform neutron radiation-proof glass.

The embodiment of the utility model discloses a portable neutron dose rate instrument, which comprises a spherical polyethylene moderator, a cylindrical connecting part is connected to the upper part of the spherical polyethylene moderator, a cylindrical cavity is formed in the center of the spherical polyethylene moderator, and the cylindrical cavity is communicated with the cylindrical connecting part; supporting legs are arranged below the base; the cylindrical polyethylene moderator is adaptively arranged in the cylindrical cavity of the sphere; a spherical cavity is formed in the cylindrical polyethylene moderator, and a connecting hole communicated with the spherical cavity is formed in the upper surface of the cylindrical polyethylene moderator; the hollow cadmium sheet sphere is adaptively arranged in the spherical cavity in the cylindrical polyethylene moderator; the counter is arranged in the cadmium sheet sphere, and a polyethylene moderator material is arranged between the He3 counter and a shell of the cadmium sheet sphere; and the information processing assembly is arranged above the cylindrical polyethylene moderator, and the He3 counter is connected with the information processing assembly through a signal line arranged in the connecting hole.

A non-destructive inspection system includes: a neutron emission unit capable of emitting neutrons having a first neutron dose; a neutron detection unit capable of detecting a second neutron dose of neutrons scattered inside an inspection object A by the emission of the neutrons from the neutron emission unit; a gamma-ray detection unit capable of detecting a gamma dose of gamma rays released from the inspection object A by the emission of the neutrons from the neutron emission unit; and an analysis unit configured to calculate a content of a predetermined substance based on the gamma dose and correct the content of the predetermined substance based on the first neutron dose and the second neutron dose.

The invention provides a wide-energy-spectrum neutron dose rate meter, and the meter comprises a mechanical structure assembly which comprises a proportional counter tube, a neutron moderator layer, and a neutron multiplier layer; wherein the neutron moderator layer wraps the proportional counter tube, and the neutron multiplier layer is arranged between the neutron moderator layer and the proportional counter tube; and the circuit board is used for providing working voltage for the proportional counter tube and processing a detection signal output by the proportional counter tube.

The invention is suitable for the field of radiation detection, and provides a neutron detector. Comprising a proportional counter tube, a signal amplifying and shaping module connected with the signal output end of the proportional counter tube, a first pulse counting module connected with the signal amplifying and shaping module, a signal integral quantization module connected with the ground signal output end of the proportional counter tube, and a second pulse counting module connected with the signal integral quantization module, the processor is respectively connected with the first pulse counting module and the second pulse counting module, and the prompting module, the storage module and the communication module are respectively connected with the processor. According to the invention, the effect of zoning measurement of 2nSv / h-1000mSv / h is realized, the linearity of full-range measurement is ensured by the zoning measurement technology, and the neutron dose with a relatively wide range is measured by one proportional counter tube.

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.

The present invention discloses a method for improving the reverse breakdown voltage of a gallium oxide diode based on neutron radiation, which mainly solves the problem of the low breakdown voltage of the existing gallium oxide diode. The implementation scheme is as follows: Select a neutron source device, and set the neutron energy of the device to 0.1 MeV - 20 MeV and the dose to 1×10<supgt;13< / supgt> - 1×10<supgt;16< / supgt> n / cm<supgt;2< / supgt> according to the tolerance of gallium oxide material to neutron radiation; Horizontally and evenly attach multiple Ga<subgt;2< / subgt>O<subgt;3 diodes to the PCB board, and then vertically place the PCB board with the devices attached at the pore position of the neutron source radiation device; After checking that the setting parameters of the neutron source device are correct, turn on the power to irradiate the attached devices with neutrons until the neutron dose emitted by the neutron source reaches the preset value, then turn off the power and take out the Ga<subgt;2O<subgt;3 diodes. The present invention effectively improves the reverse breakdown voltage of the Ga<subgt;2O<subgt;3 diode and can be applied to high-voltage and high-power power electronic devices.

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.

The portable neutron personal dosimeter disclosed by the embodiment of the invention comprises a silicon semiconductor detector unit used for detecting neutron radiation and generating a corresponding electric signal; the pre-amplification circuit unit is connected with the silicon semiconductor detector unit and is used for processing the detected neutron radiation electric signals and converting the neutron radiation electric signals into pulse signals; the information processing unit is configured to be connected with the pre-amplification circuit unit and is used for processing the pulse signal and outputting neutron dose information; the power supply circuit unit is used for respectively providing proper voltage for the silicon semiconductor detector unit, the pre-amplification circuit unit and the information processing unit; the display screen unit is connected with the information processing unit and is used for displaying the neutron dose information; and the alarm unit is connected with the information processing unit and is used for outputting an alarm signal. The portable neutron personal dosimeter device is simple in structure and light and convenient to use, can accurately detect neutron radiation, can well protect individuals, and has a good application prospect in the field of neutron radiation detection.

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.

Compensating for high energy radiation damage to a semiconductor-based radiation detector. A radiation signal, temperature and leakage or dark current are detected. A compensated leakage current is determined based on the detected temperature, for example based on a polynomial relationship. A high energy radiation exposure is determined based on the compensated leakage current, for example by using a scaling factor. A compensated radiation signal based is determined based on the determined high energy radiation exposure. This may be used to determine neutron dose rates in nuclear power, reactors or decommissioning.

The invention relates to a pollution radiation test method for a high-energy photon reference radiation field, and the method comprises the steps: constructing a detector physical model of high-energy photons based on a Monte Carlo method; obtaining a measurement spectrum at a high-energy photon radiation substance calibration point through a detector physical model; calculating the measurement spectrum through a G function to obtain a high-energy photon dose rate value; simulating an HpGe detector detection efficiency curve within the energy range of 8MeV in the detector physical model to obtain a low-energy photon dose rate value; based on Co-60 isotope energy calibration, determining an electron dose rate value through an extrapolation ionization chamber; neutron isotopes are set, and a neutron dose rate value is obtained based on a long counter; and determining a dose ratio based on the dose rate value. The technical effect of obtaining the dose ratio of the high-energy photon dose rate value, the low-energy photon dose rate value, the electron dose rate value and the neutron dose rate value is achieved.

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.

The invention relates to the field of neutron energy spectrum measurement, and provides a neutron energy spectrum measurement method and device based on characteristic gamma energy response, and the method comprises the steps: obtaining a counting rate and a corresponding energy response; discretizing continuous energy into a plurality of energy groups, and establishing a linear equation set by using an energy response function; carrying out iterative solution on the linear equation set to obtain a neutron energy spectrum; a neutron dose equivalent conversion factor can be expressed as linear superposition of an energy response function, and a contribution weight coefficient is obtained by adopting a weighted least square method; and calculating a first neutron dose equivalent rate based on the contribution weight coefficient and the counting rate, calculating a second neutron dose equivalent rate based on the neutron energy spectrum and the neutron dose equivalent conversion factor, carrying out comparison verification on the first neutron dose equivalent rate and the second neutron dose equivalent rate, and outputting the neutron energy spectrum as a final measurement result when the comparison verification is passed. On the basis of the single detector, the purpose of online real-time measurement of the neutron energy spectrum is achieved, and the accuracy and the reliability of a measurement result are improved.

1. The name of the design product: portable pulse neutron dosimeter. 2. The use of the design product: for measuring pulse neutron dose. 3. The design points of the design product: in shape. 4. The picture or photo that best indicates the design points: perspective view.

The invention discloses a multi-point radiation dose real-time monitoring system and method for a proton radiotherapy environment, and relates to the technical field of radiation monitoring. Neutron dose signals and X-gamma ray dose signals of a fixed subarea, a non-coverage area and a worker position in the control area are collected respectively; calculating the radiation coefficient of each region by using the collected signals, and constructing and perfecting a radiation coefficient graph of the three-dimensional control region to realize dynamic labeling of risk and safety regions in the control region; meanwhile, in combination with real-time positioning and dosage signals of the personal radiation dosage monitoring module, the danger level of the position where the worker is located is determined, reminding is given out in time, and the safety of the worker is ensured; according to the method, radiation dose distribution in the proton radiotherapy environment can be monitored comprehensively in real time, and effective support is provided for radiation protection.