106 results about "Neutron radiation" patented technology

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.

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 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 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 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.

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.

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 embodiment of the invention provides a neutron source emissivity valuing device and a neutron source emissivity measuring method. The neutron source emissivity valuing device comprises a solution pool, a measuring chamber, a circulating pipeline, a shielding body and a detector. The solution tank is provided with a first accommodating cavity for accommodating an activating solution and a second accommodating cavity for accommodating a neutron radioactive source; the measuring chamber is provided with a third accommodating cavity and a measuring cavity; the shielding body is provided with a fourth accommodating cavity for accommodating the measuring chamber and a communication channel communicated with the outside, and the communication channel is communicated with the measuring cavity; the detector is arranged in the communication channel, and one end of the detector extends into the measuring cavity. According to the neutron source emissivity valuing device, the detector in the measurement chamber can be taken out through the communication channel, so that on one hand, the detector is simpler and more convenient to disassemble and assemble; on the other hand, the detector can be independently packaged and stored, and collision damage of the detector is effectively prevented.

Provided herein are therapeutic methods, kits, and pharmaceutical compositions for protecting a subject from radiation using a therapeutic agent selected from the group consisting of RRx-001 and pharmaceutically acceptable salts thereof. An exemplary method of treatment includes administering RRx-001 to the subject prior to exposure of the subject to the radiation to protect the subject from radiation, such as ionizing radiation containing alpha-rays, beta-rays, gamma-rays, neutron radiation, or a combination thereof.

The invention discloses a pulse neutron generation device for cutting steady-state neutron radiation and a pulse time measurement method. Comprising a steady-state neutron radiation source device, a shielding structure, a supporting frame, a collimator provided with a conical beam limiting diaphragm, a cutting sliding block made of neutron absorbing materials and internally provided with a penetrating beam limiting hole, a sliding block falling stabilizing device, a sliding block height adjusting device, a sliding block releasing device and a detector located on the emergent side. The cutting sliding block freely falls down along a vertical track limited by the falling stabilizing device after being released at a preset height, time cutting is carried out on a steady-state neutron beam passing through the collimator, a reference point is arranged on the supporting frame according to the pulse time measuring method, and a photoelectric probe A, a photoelectric probe B and a timer are arranged near a falling path; in the falling process of the cutting sliding block, the two photoelectric probes are sequentially shielded to trigger the timer to start / stop timing, and the time interval recorded by the timer is determined as the actual pulse width of pulsed neutron radiation.

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 laboratory non-contact type loaded coal rock neutron monitoring test device comprises a box body with an opening in the front end and a partition plate which is arranged at the rear end of the inner wall of the box body in a matched mode and divides the box body into a device cavity and an operation cavity, and an experiment table base is arranged at the bottom of the inner wall of the operation cavity. Press machines are arranged on the left side and the right side of the upper end of the experiment table base in a matched mode, a neutron detector is arranged at the position, behind the press machines, of the upper end of the experiment table base, a pre-amplifier is installed on one side in the device cavity, and a high-voltage power module, a time synchronizer and a neutron monitoring controller are arranged on the other side in the device cavity. A data analysis panel is arranged at the open end of the device cavity in a matched mode and controls time synchronization through a time synchronizer, and a plurality of heat dissipation holes distributed in an array mode are backwards formed in the rear end of the inner wall of the device cavity. The neutron radiation test can be carried out, and meanwhile, the neutron discrete coefficient of the coal-rock mass is provided as a neutron radiation anomaly index, so that the coal mine dynamic disaster is predicted.

This invention discloses a cerium-doped InP-based single-photon avalanche detector for space communication and its fabrication method. The detector's epitaxial structure, from bottom to top, includes a substrate, an N-type buffer layer, an absorption layer, a band transition layer, an N-type charge layer, an intrinsic multiplication layer, an intrinsic InP layer, and a cerium-doped P-type contact layer. The core innovation lies in the dual radiation-resistant design of the Ce-doped P-type contact layer and the Ce-doped modified stacked passivation film. The fabrication method involves MOCVD epitaxial growth, spin-coating source diffusion to prepare the P-type contact layer, ICP etching and wet repair, magnetron sputtering doping, and electrode fabrication. This invention utilizes Ce's unique electronic structure to suppress radiation-induced defects and combines this with an SACM structure to optimize the electric field distribution, achieving low dark count rate, high detection sensitivity, and excellent neutron radiation resistance. The process is compatible with existing semiconductor production lines and is suitable for wafer-level mass production, meeting the high-reliability single-photon detection requirements of aerospace missions such as space laser communication and quantum key distribution.

The invention belongs to the technical field of neutron radiation protection, and discloses a flexible neutron radiation protection material and a preparation method thereof. Comprising a high-density polyethylene / modified boron nitride composite fabric, and the surface of the composite fabric is coated with a polymer / boron powder composite coating. The preparation method comprises the following steps: (1) preparing modified boron nitride; (2) preparing a polyethylene / boron nitride blend; (3) spinning polyethylene / boron nitride fibers; (4) weaving the fabric; (5) preparing a coating dispersion liquid; and (6) fabric coating treatment. The shielding efficiency of the product prepared by the invention at a 5.3-wavelength neutron absorption position can reach 50.9-78%, and the protection requirement of neutron radiation is met; the surface coating of the composite fabric obtained after batch production is good in quality, and the composite fabric has good popularization significance.

The application discloses a bat moth lepidoptera cordyceps strain and application thereof in preparation of anti-neutron radiation medicines. Samsoniella hepiali The strain is the bat moth lepidoptera cordyceps strain P969 (Pleurotus spodoleucus), which is preserved in the China Center for Type Culture Collection and has a preservation number of CCTCC NO: M 20251172 and a preservation date of May 26, 2025. Mycelium extracts of the strain can protect biological tissues against neutron radiation and repair organ damage caused by neutron radiation, so that the strain has a wide development space and a good development and application prospect.