177 results about "Neutron radiation" patented technology

The invention relates to a device and a method for measuring concrete volume change caused by long-term neutron irradiation, the device comprises a neutron emitter and a neutron receiver which are arranged in a laboratory in a matching manner, a test concrete test piece is fixed between the neutron emitter and the neutron receiver, and the test concrete test piece measures the temperature through a temperature detector; a contrast concrete test piece is arranged in the test chamber, a collection mold wraps the outer side of the contrast concrete test piece, and a condensation pipe, a water vapor collector and a high-precision electronic scale are arranged. The method comprises the following steps: 1, measuring the overall expansion rate of a concrete test piece through a strain measurer; 2, testing the volume change of the concrete test piece in the environment; 3, calculating the volume change rate of the concrete caused by neutron radiation by combining the thermal expansion coefficient of the concrete and the drying shrinkage of the concrete; and 4, the relationship between the volume expansion rate of the concrete and the neutron irradiation dose is tested, and the relationship between the volume change rate of the shielding concrete of the engineering structure and the time is speculated, so that the safety of the nuclear engineering structure is ensured.

The utility model relates to the technical field of radiation detection and measurement, and discloses a neutron bubble detector counting device, which comprises a neutron bubble detector used for forming bubbles matched with neutron radiation dose; the supporting module is used for bearing the neutron bubble detector and controlling the neutron bubble detector to rotate circumferentially; the backlight module is used for providing a backlight source for the neutron bubble detector; and the imaging module is arranged opposite to the backlight module, enables the neutron bubble detector to be located between the backlight module and the imaging module, and is used for imaging of the neutron bubble detector, so that bubble counting is facilitated. Through optical-mechanical linkage design, under the condition that complex algorithm preprocessing does not need to be introduced, native enhanced collection of bubble physical characteristics is achieved, a reliable data basis is established for follow-up automatic counting, and meanwhile a data basis is provided for follow-up data tracing and auditing.

The invention relates to the technical field of soil humidity monitoring, and particularly discloses an effective method for monitoring soil humidity by measuring neutron radiation, which comprises the steps of S1, region division, S2, equipment installation, S3, data processing, S4, humidity calculation and S5, data analysis and feedback. According to the method, based on the fact that fast neutrons collide with hydrogen nucleuses of water in soil to cause speed reduction or energy attenuation, as the cloud density of the slow neutrons around a probe changes along with the concentration of the hydrogen nucleuses of the water in the soil, the counting rate of the slow neutrons represents the water content of the soil, and the required volumetric water content of the soil can be converted through a correction curve; accumulated soil humidity data provides a scientific basis for agricultural management, helps farmers to make more reasonable planting and irrigation plans and establish a soil humidity database, is helpful for long-term research of interrelation between soil and crops, and guides future agricultural practice.

The invention relates to the technical field of underground geotechnical engineering and tunnel construction monitoring, in particular to a shield tunneling rock stratum real-time judgment method. The method comprises the steps that according to signals of neutron radiation characteristics released when different lithologic samples are fractured under a shield tunneling stress path simulated in a laboratory, a knowledge base of the neutron radiation characteristics of a rock stratum is constructed; deploying an on-site multi-source data acquisition system, and acquiring data of neutron radiation characteristics and shield tunneling parameters; jointly forming a fusion feature vector according to the data of the neutron radiation features and the shield tunneling parameters; the method has the advantages that signals of neutron radiation characteristics released in the rock fracture process are directly monitored, the signals are fused with shield tunneling parameters in a multi-source mode, a machine learning model is combined, and the lithology classification probability and the rock mass integrity index are obtained. Real-time and accurate discrimination of lithology and integrity of a front rock stratum is realized, physical characteristics of a rock mass are reflected, and a discrimination effect is continuously optimized.

A neutron source irradiation device capable of switching gas paths disclosed by the present invention comprises a gas path switching rotor assembly, a transmission pipeline and a plurality of storage pipelines, the transmission pipeline is provided with an electromagnetic chuck, and a neutron source is stored in each storage pipeline. And the transmission pipeline can be communicated with the different storage pipelines through rotation of the gas path switching rotor assembly, so that neutron sources in the different storage pipelines can reach the electromagnetic chuck through the transmission pipeline. Neutron sources at different positions can be transmitted to the same position for irradiation, an independent transmission irradiation structure is provided, the irradiation position structure is simple, the scattering influence can be reduced, meanwhile, different neutron sources have good repeatability and consistency at the irradiation positions, position adjustment of a measured instrument is not needed, the verification efficiency is improved, and the detection cost is reduced. And the stability and consistency error of the generated neutron radiation field are ensured.

The invention relates to an isotropic thermal neutron radiation field angle distribution uniformity control device and method, and the device is characterized in that a particle accelerator is used for emitting a high-energy charged particle beam with a beam position; the beryllium target is placed along the emission line of the high-energy charged particle beam, and the high-energy charged particle beam bombards the beryllium target to generate charges; the insulation isolation gasket is wound on the outer side of the beryllium target and prevents the charges from being led out from the outside through the beryllium target; and the adjusting assembly is connected with the beryllium target and used for acquiring the electric charge quantity on the beryllium target, and is connected with the particle accelerator and used for adjusting the angle of the high-energy charged particle beam irradiating to the beryllium target. According to the invention, the purposes of preventing the charges from being exported outwards based on the insulation isolation gasket and obtaining the charge quantity by the adjusting assembly to adjust the particle accelerator are achieved, so that after the insulation isolation gasket with low cost is used for isolation, the charge quantity is detected to adjust the particle accelerator, and the technical effect of effectively saving the cost is achieved.

The invention discloses a multi-ball neutron spectrometer applied to pulsed neutron radiation field monitoring. The multi-ball neutron spectrometer comprises a 3He gas detector, a 4H-SiC semiconductor detector, a neutron moderation ball, a preamplifier, a spectrometer main amplifier, a high-voltage power supply and a multichannel analyzer. A 3He gas detector and a 4H-SiC semiconductor detector are designed in a neutron moderator of a set of multi-sphere neutron spectrometer, the double-detector multi-sphere neutron spectrometer is applied in pulsed neutron radiation fields, and neutron energy spectrum and dose measurement is carried out in the pulsed neutron radiation fields with the neutron flux of 101-104 n.cm <-2 > s <-1 > and the neutron flux of 103-106 n.cm <-2 > s <-1 > respectively. According to the invention, a dual-detector multi-ball neutron spectrometer data acquisition system based on a 3He gas detector and a 4H-SiC semiconductor detector is utilized to realize measurement of neutron energy spectrum distribution information and neutron dose in a wide energy region.

The invention discloses a nuclear power station risk assessment method and device, electronic equipment and a storage medium. The method comprises the following steps: detecting a radiation source at a preset part position of the nuclear power plant to obtain first detection data, and determining a radiation risk factor of the nuclear power plant according to the first detection data; wherein the radiation source comprises neutron radiation, an alpha ray, a beta ray, a gamma ray and an x ray; detecting a pollution source and plants at a preset environment position of the nuclear power station to obtain second detection data, and determining an environment risk factor of the nuclear power station according to the second detection data; wherein the preset environment position comprises a preset soil position and a preset water body position, and the pollution source comprises strontium and cesium; and evaluating the operation risk of the nuclear power station according to the radiation risk factor and the environmental risk factor. According to the technical scheme of the embodiment of the invention, the representativeness of the radiation risk factor and the environmental risk factor can be improved, and the comprehensiveness and the accuracy of the operation risk assessment result of the nuclear power station are further improved.

The invention provides magnesium phosphate cement applicable to a high-temperature condition and a preparation method thereof, and relates to the technical field of cement. The magnesium phosphate cement is composed of main components and modified components, wherein the main components are composed of the following raw materials in percentage by mass: 50-80% of a magnesium material, 20-50% of a phosphorus material and the balance of water for mixing; the modified component comprises at least one of a retarding material, an auxiliary cementing material, a fiber material and a weighting material. The invention fills the blank of special cement suitable for high-temperature conditions, and provides an emergency scheme for shielding special environments such as ultrahigh temperature or thermal neutron radiation.

The invention relates to a photoelectric signal extraction device and method, in particular to a low-time-dispersion strong-background photoelectric signal extraction device and method. The device comprises a photoelectric cathode, an accelerating electrode and an MCP detector, as well as an electron beam input guide tube, an electron beam guide tube, an electron beam buffer guide tube, a time dispersion compensation type electron beam guide tube and an electron beam output guide tube which are connected in sequence, the photoelectric cathode and the accelerating electrode are sequentially arranged at an inlet of the electron beam input guide tube; the electron beam guide tube and the time dispersion compensation type electron beam guide tube are respectively of a solenoid structure with a bent 1 / 4 spherical surface, and the other guide tubes are respectively of a straight cylindrical hollow solenoid structure; and the MCP detector is arranged at the outlet of the electron beam output guide tube. Spatial separation of detection signals and gamma and strong neutron radiation backgrounds can be realized, the signal-to-noise ratio of the system is improved, the time resolution is improved, the input end face of the MCP detector is prevented from being radiated by strong neutrons, and the service life of the detection system is prolonged.

The invention discloses and provides a test method for atmospheric neutron radiation and time-dependent breakdown of a nano FinFET device. A comprehensive effect test device is adopted, a sample is placed in the comprehensive effect test device, atmospheric neutron radiation beams are applied to the sample, and voltage and temperature are applied to the sample through the comprehensive effect test device; according to the method, in the atmosphere neutron radiation environment, the time-dependent breakdown test is carried out on the nanometer FinFET device so as to evaluate the comprehensive stress influence of the nanometer FinFET device on the ground and the flight height, two tests do not need to be carried out independently for evaluation, and the method is more convenient and faster.

The invention relates to a method for separating heavy metal cations and radionuclides from aqueous solutions. The method according to the invention can be used to separate dissolved and / or suspended naturally occurring ions or radioactive ions produced by radioactive decay, nuclear transformation reactions such as nuclear fission, or, for example, by activation with neutron radiation, from aqueous solutions.

A radiation dose quantification method and system, the method comprising: detecting, with one or more detectors with respective sensitive volumes, gamma-rays emitted as a result of capture of neutrons by a composition in a subject subjected to an irradiation program, the composition comprising one or more thermal neutron capture agents, the neutrons having been generated by non-elastic collisions between a primary beam of particles and nuclei in the subject, wherein the particles consist of any one or more of protons, deuterons, tritons and heavy ions, the irradiation program comprises at least one period of irradiation with a beam duration that includes beam-on periods and beam-off periods; applying at least one predefined energy window or filter configured to accept only detection events in the one or more detectors resulting from gamma-rays with an energy indicative of selected gamma-rays arising from the capture of thermal neutrons by the one or more thermal neutron capture agents, wherein the thermal neutrons are neutrons with energies below approximately 0.4 eV; applying a timing window configured to reject or ignore detection events in the one or more detectors resulting from at least prompt gamma-rays produced in non-neutron capture events; and determining the radiation dose of neutron radiation received by the subject during the irradiation program from at least the accepted detection events or determining a dose map of the radiation received by the subject from at least the accepted detection events.

The subject of the invention is a containment shell (1) comprising a wall (10) defining a space (12) made of a material of the concrete type and at least one observation module (30) comprising at least one window (33) arranged in an opening (32) of the wall (10), said window comprising a frame (36) in which is housed at least one optical block (34) providing protection against high-energy and / or neutron radiation, said frame fitting in the opening (32), the observation module further comprising a protection element (37) comprising a sash (38) carrying a glass (39) and arranged to close the opening at a surface inside the shell, said observation module thus comprising at least one interface (I) between two surfaces (S), characterized in that it further comprises at least one sealing system (40) arranged at the at least one interface (I).

The present invention relates to a remotely operated system (200) to deploy and recover materials (25) into and from a nuclear fusion device (100), for the purpose of exposing said materials (25) to neutron radiation, which will cause the generation of radioactive isotopes, comprising at least one loop made of pipes (14) with constant inner diameter, a plurality of capsules (23) with an outer diameter slightly smaller than the inner diameter of the at least one loop (14), wherein the capsules (23) are adapted to contain the material (25) to be irradiated by the neutron radiation, a propulsion system for circulating the capsules (23) through the at least one loop (14), a remotely operated capsule filling system (18) for filling said capsules (23) into the at least one loop (14), and a remotely operated capsule recovery system (19) for recovering said capsules (23) from the at least one loop (14).

The invention relates to an under-voltage protection circuit suitable for a neutron radiation environment. The circuit comprises NMOS (N-channel Metal Oxide Semiconductor) tubes Q1 and Q2, a voltage-regulator tube D1, diodes D2 and D3 and resistors R1-R5, the anode of the voltage-regulator tube D1 is connected with the anode of the diode D2; the cathode of the diode D2 is connected with the first end of the resistor R1 and the first end of the resistor R2 at the same time. The second end of the resistor R2 is connected with the first end of the resistor R5 and the grid electrode of the NMOS tube Q1 at the same time. The drain electrode of the NMOS tube Q1 is connected with the first end of the resistor R3 and the grid electrode of the NMOS tube Q2; the second end of the resistor R5, the first end of the resistor R4, the cathode of the diode D3 and the drain electrode of the NMOS tube Q2 are connected; the cathode of the diode D1, the second end of the resistor R3 and the second end of the resistor R4 are connected to a power supply VCC; the second end of the resistor R1, the source electrode of the NMOS tube Q1 and the source electrode of the NMOS tube Q2 are connected to a reference ground end GND. The device is realized based on a localized VDMOS, and has the characteristics of neutron displacement radiation resistance, simple design, easy realization, low cost and the like.

A neutron flux detector comprising a source material and a solid state radiation detector is disclosed. The source material is configured to produce gamma photons greater than or equal to 6.8 MeV during neutron capture. The solid state radiation detector comprises a Schottky diode and an emitter layer comprising a Compton and photoelectron source material. The emitter layer is configured to receive the gamma photons produced by the source material. The emitter layer is spaced apart from the Schottky diode a distance such that a gap is defined between the emitter layer and the Schottky diode. The distance is selected such that only electrons produced by the emitter layer as a result of the emitter layer absorbing the gamma photons will contribute to a measured output signal of the Schottky diode.

The invention discloses a degradation method and a super-resolution reconstruction method suitable for a neutron ray image, and relates to the technical field of image super-resolution, and the method comprises the steps: building a degradation model of the neutron ray image, carrying out the degradation of a high-resolution neutron ray image based on the degradation model, and generating a corresponding low-resolution neutron ray image, the degradation processing comprises fuzzification, down-sampling and addition of at least gamma white spot noise; multiple groups of paired high-resolution and low-resolution neutron ray images are obtained based on the degradation model to be used for training an image super-resolution model, and super-resolution reconstruction of the neutron ray images is achieved based on the trained image super-resolution model. The low-resolution neutron ray image obtained on the basis of the degradation method is closer to a real neutron ray image, so that the super-resolution reconstruction of the neutron ray image can be realized on the premise of inhibiting various degradation effects on the basis of the trained image super-resolution model.

An arylboron compound, its preparation method, applications, and pharmaceutical compositions are disclosed for tumor imaging. The compound of formula (I) exhibits high fluorescence quantum efficiency through intramolecular charge transfer. The compound of formula (I) synthesized in this invention can be linked to different antibodies via Q3 at certain concentrations, allowing for precise targeting of corresponding tumors based on the antibody. This type of boron drug formulation can be used in boron neutron capture therapy to kill tumor cells. It exhibits better killing effects; the compound of formula (I) targets tumor cells through antigen-antibody interaction. After the boron-10-containing drug accumulates at the tumor site, neutron radiation triggers a nuclear reaction releasing alpha particles and... 7 Lithium particles kill cells; the range of these two particles is approximately 10 μm. High-energy-density heavy ions disrupt the DNA double helix structure in tumor cells, causing irreparable cell death. Simultaneously, the 10 μm distance avoids damage to normal cells and tissues.

A plastic scintillating fiber includes an organic compound containing an element with a neutron cross section larger than that of hydrogen, and includes: an outermost peripheral layer containing a plastic material that emits scintillation light when it is irradiated with neutron radiation; a core having a high refractive index, disposed inside the outermost peripheral layer, and containing at least one type of fluorescent substance that absorbs the scintillation light and wavelength-converts the absorbed light into light having a wavelength longer than that of the absorbed light; and a cladding layer covering an outer peripheral surface of the core and having a refractive index lower than that of the core. A wavelength shifting fiber including the core and the cladding layer, and the outermost peripheral layer covering an outer peripheral surface of the wavelength shifting fiber are integrally formed.

The present application discloses a sample pool and probe integrated device for Raman spectrum detection, which is applied to a pressurized water reactor neutron-free radiation source boric acid concentration detector, which includes: a sample pool for holding a solution to be tested; an optical path system, including a closed outer shell and a Raman probe assembly arranged inside the outer shell, the Raman probe assembly is used to emit a laser beam; a flange window, the flange window is arranged between the outer shell and the sample pool, the outer shell is connected to the sample pool through the flange window, and the laser beam acts on the solution to be tested through the flange window; wherein a planar super lens is arranged between the Raman probe assembly and the sample pool, the planar super lens is fixedly mounted on the flange window, the planar super lens acts on the laser beam so that the laser beam is focused and then acts on the solution to be tested to form a Raman scattering signal, and the pressure resistance of the planar super lens is not less than 3 MPa. Through the above arrangement, the loss generated during the light transmission process is reduced to improve the intensity of the Raman signal.

The utility model relates to a nuclear power station spent fuel transportation container shielding protection device. The device comprises a container body; the neutron shielding layer is arranged on the outer side of the container body in a surrounding mode, a filling cavity is defined by the neutron shielding layer and the outer side wall of the container body, and the filling cavity is filled with neutron shielding materials. By arranging the neutron shielding layer surrounding the outer side of the container body and the neutron shielding material filled in the neutron shielding layer, the neutron radiation shielding problem in the spent fuel transportation and assembly loading process is solved, the neutron radiation dose on the outer surface of the transportation container can be effectively reduced, a stable shielding structure is formed, and safe transportation of spent fuel is guaranteed.

The present application relates to cement-based building material technical field, especially to a kind of carbonized steel slag phosphogypsum light aggregate anti-radiation super high performance concrete and preparation method thereof, the present application uses cement as main cementitious material, adds composite admixture, utilizes steel slag and phosphogypsum to prepare light aggregate with core-shell structure, and cooperates with copper-plated steel fiber, and the anti-radiation super high performance concrete with good fluidity, high mechanical property, low shrinkage, strong neutron radiation resistance is prepared.

The invention provides a self-repairing lithium target for generating a neutron radiation field and a preparation method and a self-repairing method thereof, the lithium target comprises a target material shell and lithium poured into the target material shell, the target material shell is not completely filled with the lithium poured into the target material shell, and a reserved gap is formed between the lithium poured into the target material shell and the target material shell. The target material bombarded by the proton beam is heated until lithium in the target material shell is in a molten state, bubbles generated by bombardment of the proton beam can be separated out of the lithium to the reserved gap, and lithium target self-repairing can be completed after the lithium in the target material shell is cooled and solidified. The self-repairing lithium target is simple in structure and easy to prepare, air holes left in the lithium target after proton beam bombardment can be easily removed only by heating the target material, self-repairing of the lithium target is achieved, frequent replacement of the target material is avoided, the service life of the lithium target is prolonged, and the working efficiency of an accelerator neutron source system is improved.

The invention discloses a neutron radiation shielding material and a preparation method thereof, the neutron radiation shielding material comprises a neutron radiation protection coating agent, and the neutron radiation protection coating agent comprises the following raw materials: polyvinyl alcohol, N, N-dihydroxyethyl-2-methacrylamide, di (carborane methoxy ester) phthalate, a dispersant, a cross-linking agent and an accelerant. According to the neutron radiation protection coating agent, N, N-dihydroxyethyl-2-methacrylamide is introduced and can be polymerized under the thermal action to form a Gel-PMA and PVA hydrogel system, a PVA-boric acid ester covalent network system is further constructed under the action of boric acid ester, and the neutron radiation protection coating agent is prepared. And a strong bisamide hydrogen bond interpenetrating network is generated under complete dispersion of phthalic acid di (carborane methoxyl ester) in a Gel-PMA polymer system, and the dual effects of mechanical property improvement and efficient neutron shielding effectiveness are synergistically realized.

The application provides a rotating sample stage and a control method. A center rocker mechanism and a driving module are arranged in an atmospheric environment outside a vacuum scattering cavity, away from a high-flux neutron radiation area at the center of a sample, so that electronic components and precision mechanical parts are prevented from being damaged by neutron / gamma irradiation, and the long-term reliability and service life of the equipment are significantly improved.

The invention relates to an accelerator thermal neutron radiation field double-target beam automatic adjusting device and method, and the device is characterized in that a particle transmitting end is used for transmitting an ion beam; the particle receiving end is arranged on the emission axis of the ion beam; the particle receiving end comprises two semicircular beryllium targets and a tantalum target, the projections of the two semicircular beryllium targets form a complete circle on the ion beam emission axis, the tantalum target is arranged at the outermost side line of the two semicircular beryllium targets, and the area of the tantalum target is smaller than one third of the area of the two semicircular beryllium targets; and the xy guider is arranged between the particle transmitting end and the particle receiving end, a deflection electric field is arranged in the xy guider, and the xy guider is used for acquiring the quantity of ions received by the two semicircular beryllium targets and the quantity of ions received by the tantalum targets respectively, adjusting the electric field intensity of the deflection electric field based on the quantity of ions and changing the shooting direction of the ion beam. The technical effects that manual adjustment is not needed, the monitoring efficiency is improved, and meanwhile the experience degree needed by adjustment is reduced are achieved.

The invention discloses a neutron ray image super-resolution reconstruction method and device based on Real-ESRGAN and a medium, and relates to the technical field of image super-resolution. The method comprises the following steps: constructing a second-order degradation model, wherein the second-order degradation model is used for generating a low-resolution neutron ray image with gamma white spot noise; constructing an image pair training set based on the second-order degradation model and a sample data set; training a training set based on the image to obtain a Real-ESRGAN model suitable for the neutron ray image; and super-resolution reconstruction of the neutron ray image is realized based on the Real-ESRGAN model. According to the neutron ray image super-resolution reconstruction realized based on the method, the resolution of the neutron ray image can be effectively improved, and meanwhile, the degradation influence in the neutron ray imaging process is inhibited.

The invention discloses radiation shielding type high-strength ceramsite based on lead-zinc ore tailings and a preparation method of the radiation shielding type high-strength ceramsite, and relates to the technical field of radiation protection concrete. The lead-zinc ore tailings containing more Pb elements are used as main ceramic forming raw materials, a proper amount of lead-rich raw materials are used as auxiliary materials to adjust the content of the Pb elements, a proper amount of boron-rich raw materials are used as auxiliary materials to adjust the content of the B elements, and the composite powder with the proper content of the Pb elements and the proper content of the B elements is prepared. The efficient shielding effect of the Pb element and the B element on gamma rays and neutron radiation is fully exerted, and the sintering temperature of the ceramsite is remarkably reduced. In addition, a proper amount of fly ash floating beads with spheroidal cavity structures are introduced as a pore-forming template, so that the purpose of regulating and controlling the density grade of the ceramsite is achieved, and the problem that the concrete structure is not uniform due to the fact that the density of aggregate is not matched with that of a cementing material is solved. The prepared ceramsite has relatively high strength and a good radiation shielding coefficient, and has a density similar to that of a cementing material.

A neutron flux detector comprising a source material and a solid state radiation detector is disclosed. The source material is configured to produce gamma photons greater than or equal to 6.8 MeV during neutron capture. The solid state radiation detector comprises a Schottky diode and an emitter layer comprising a Compton and photoelectron source material. The emitter layer is configured to receive the gamma photons produced by the source material. The emitter layer is spaced apart from the Schottky diode a distance such that a gap is defined between the emitter layer and the Schottky diode. The distance is selected such that only electrons produced by the emitter layer as a result of the emitter layer absorbing the gamma photons will contribute to a measured output signal of the Schottky diode.