41 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 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 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 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 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.

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.

The invention discloses a mixed radiation measurement device and a neutron dose measurement method, and the device comprises a housing and an inner core. The surface of the shell comprises a window; a cadmium filter disc is arranged on the window; the inner core comprises a solid track detection element and a thermoluminescence element group; when the inner core is arranged in the shell, the thermoluminescence element group is positioned below the window, and the solid track detection element is staggered from an area provided with the window; the thermoluminescence element group comprises at least one incidence group thermoluminescence element and at least one reflection group thermoluminescence element. The mixed radiation measurement device provided by the invention gives consideration to measurement of photons and neutrons.

The invention relates to the technical field of ionizing radiation measurement, in particular to a neutron field generating device which comprises a support. The neutron generation structure is arranged on the bracket and is used for emitting a neutron field; the moderation part is arranged in the support in the neutron field emission direction of the neutron generation structure, and the moderation part comprises a liquid moderation dielectric layer; the loading part is used for loading a neutron dose monitor; the loading part is connected to the first adjusting part, and the first adjusting part is used for adjusting the thickness of the liquid moderation dielectric layer between the loading part and the neutron generation structure according to the neutron field intensity requirement, so that the neutron field intensity of the plane where the loading part is located is adjusted, and the requirement for the neutron field intensity during calibration of various neutron dose monitors is met; and in addition, in the transportation process, the liquid moderation medium of the moderation part can be emptied, and the overall weight is reduced. The liquid moderation dielectric layer can absorb neutrons and ensure that the radiation level is in a safe level range.

The invention relates to the technical field of radiation experiments, and discloses an animal experiment anti-radiation protection device which comprises a base and a neutron moderation plate fixed on the base, and further comprises a neutron reflection plate arranged on the base in a sliding manner, and a neutron absorption plate is embedded in one surface of the neutron moderation plate and is octagonal; the self-hooping part is arranged in the mouse sleeve; the protecting part is arranged on the mouse sleeve and is connected with the self-hooping part; the cleaning and spraying part is arranged in the mouse sleeve and is connected with the protecting part; the dose of thermal neutrons is optimized through the neutron moderation plate, the upper sleeve and the lower sleeve are matched to ensure that only tumors are exposed to a thermal neutron area, irradiation damage to other parts of a mouse is reduced, push-pull of the upper sleeve drives the L plate to move along the guide groove, the T sleeve rotates in a matched mode, the strap is controlled to be tightened or loosened, and during tightening, the strap and the lower sleeve form a constraint space to fix the mouse; when the mouse is relaxed, the rubber band elastic auxiliary hoop rebounds, the mouse is released, manual binding is not needed, and the operation process is simplified.

This invention relates to the field of radiation experiment technology and discloses an animal experiment radiation protection device, including a base and a neutron moderator plate fixed on the base. It further includes: a neutron reflector plate slidably disposed on the base, with an octagonal neutron absorber plate embedded on one side of the moderator plate; a self-closing part disposed inside a mouse sleeve; a removal part disposed on the mouse sleeve and connected to the self-closing part; and a cleaning spray part disposed inside the mouse sleeve and connected to the removal part. This invention optimizes the thermal neutron dose through the neutron moderator plate, and, in conjunction with the upper and lower sleeves, ensures that only the tumor is exposed to the thermal neutron region, reducing radiation damage to other parts of the mouse. The push-pull mechanism of the upper sleeve drives the L-plate to move along the guide groove, and the T-tube rotates accordingly, controlling the tightening or loosening of the closing strap. When tightened, the closing strap and the lower sleeve form a restraint space to fix the mouse; when loosened, the elastic band assists the closing strap to rebound and release the mouse, eliminating the need for manual binding and simplifying the operation process.

The utility model discloses a neutron dose rate meter with wide energy response, which belongs to the technical field of neutron dose rate meters and comprises a shell, a threaded column is fixedly connected to the top end of the shell, a fixing assembly is arranged at the top end of the shell, and a sealing assembly is arranged between the fixing assembly and the shell. According to the utility model, the gear ring is arranged inside, during installation, the gear ring is driven by the grip to rotate, and the threaded sleeve is driven by the gear to rotate, so that the threaded sleeve is driven by the gear ring to synchronously rotate so as to enable the top cover to stably descend, and through the design, the top cover can stably descend during installation and fixation. The gear and the threaded sleeve can be driven to synchronously rotate only by rotating the gear ring, so that the operation becomes simple, a worker can conveniently operate, meanwhile, due to the synchronous rotation of the threaded sleeve, the top cover can stably descend to avoid inclination, the sealing sleeve can be uniformly stressed, and the sealing effect is ensured.

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.