20 results about "Neutron emission" 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 invention provides a device and a method for on-line measurement of boron concentration in a boron trifluoride complex system, and relates to the technical field of boron-10 acid production. The device comprises a neutron emission part, a fluid circulation part, a neutron detection part and a data processing part. The neutron emission part is used for emitting thermal neutron beams, the fluid circulation part is communicated with a fluid pipeline at the bottom of an exchange rectifying tower of the boron trifluoride-anisole complex production process, and the fluid circulation part is of a neutron penetrable structure; the neutron detection part is arranged on the side, away from the neutron emission part, of the fluid circulation part and used for receiving thermal neutron beams penetrating through the boron trifluoride-anisole complex and converting neutron intensity signals into electric signals, and the data processing part is electrically connected with the neutron detection part and used for receiving the electric signals and sending the electric signals to the fluid circulation part. And inverting the concentration of boron-10 in the boron trifluoride-anisole complex according to the attenuation degree of the thermal neutron beam to obtain the total concentration of boron. The device can output the total boron concentration measurement result in real time, and sampling can be carried out without interrupting the production process.

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

The present application relates to a kind of long-term neutron irradiation caused concrete volume change determination device and method, the device includes: the neutron emitter and neutron receiver of matching setting in laboratory interior, test concrete test piece is fixed between neutron emitter and neutron receiver, test concrete test piece is measured temperature by temperature detector;Test chamber is equipped with control concrete test piece, control concrete test piece outside is wrapped up collection mould, setting condenser tube, water vapor collector and high-precision electronic scale.The method: one, the overall expansion rate of concrete test piece is determined by strain measuring device;Two, the self volume change of test concrete test piece in environment;Three, the volume change rate of concrete caused by neutron radiation is calculated in combination with the thermal expansion coefficient of concrete and the drying shrinkage of concrete;Four, the volume change rate of engineering structure shielding concrete with time is inferred by the relationship between the volume expansion rate of experimental concrete and neutron irradiation dose, to ensure the safety of nuclear engineering structure.

The invention discloses an active test method and an active test system for a neutron detector, and the active test method comprises the steps: S1, carrying out the body test of a temporary charging monitoring system, and placing the neutron detector of the temporary charging monitoring system on a reactor pool platform; s2, a ray generating device is installed on a reactor pool platform, a neutron emitting end of the ray generating device is close to a neutron detector, a moderator is arranged between the neutron emitting end and the neutron detector, and an active test is carried out on the neutron detector; s3, after the active test is completed, evacuating the ray generating device from the reactor pool platform; the active test system comprises a ray generating device and a moderator, the ray generating device comprises a memory, an ion source, an accelerating pole, a target material and a neutron emitting end which are connected in sequence, and the neutron emitting end, the moderator and a neutron detector are arranged in sequence. According to the invention, the overall exposure dose of active testers can be reduced, the test preparation and implementation efficiency is improved, and the cost is reduced.

A non-destructive inspection system includes a non-destructive inspection apparatus and a management apparatus. The non-destructive inspection apparatus includes: a neutron emission unit capable of emitting a neutron beam; a gamma-ray detector capable of detecting a gamma ray; an apparatus case covering the neutron emission unit and the gamma-ray detector and including an opening; an outer shutter configured to open and close the opening; dose monitors each provided on the apparatus case and configured to detect a radioactive dose; an apparatus communication unit capable of transmitting apparatus information including the detected radioactive dose to the management apparatus and capable of receiving inspection permission information from the management apparatus; and an apparatus control unit configured to open the outer shutter and allows emission of the neutron beam from the neutron emission unit upon acquisition of the inspection permission information.

A fuel target device for an inertial confinement fusion process. The device comprises a center region is comprising a first fuel layer of deuterium-tritium-lithium ((DT)(1-x)Lix, 0<x<0.5) fuel characterized by a higher or equal ignition temperature in comparison with a lowest ignition temperature of deuterium-tritium (DT). The device comprises a second fuel layer of deuterium-tritium (DT) fuel characterized by the lowest ignition temperature is surrounding the center region, and a third fuel layer comprising an outer region of a pure hydrogen (H2) or a proton rich boron (pyB(1-y)11, 1>y>0.5) material is surrounding the deuterium-tritium (DT) fuel such that the deuterium-tritium (DT) fuel is sandwiched between the deuterium-tritium-lithium ((DT)(1-x)Lix, 0<x<0.5) fuel and the pure hydrogen or proton rich boron (pyB(1-y)11, 1>y>0.5) material.

The invention discloses an in-situ monitoring device and an in-situ monitoring method for a mineral precipitation behavior in a fluid mixing reaction process, and belongs to the technical field of mineralogy monitoring. The device comprises a fluid injection and control system, a fluid mixing reaction device, a movably mounted sample table and an in-situ detection system (a microscopic optical detection device, a Raman detection device or a neutron emission and detection device). Sapphire wafer windows are arranged in front of and behind the fluid mixing reaction device, so that optical signals and neutron signals can penetrate through the sapphire wafer windows; the upper end of the fluid mixing reaction device is connected with a fluid injection system, and continuous and stable injection of fluid is controlled through a high-precision high-pressure injection pump; and the lower end of the fluid mixing reaction device is connected with a vacuum pump and a liquid outlet, so that a vacuum environment condition in the reaction device can be realized before reaction. The optical imaging method and the neutron scattering method can be used for monitoring mineral crystal nucleation and growth changes in real time, and full-size change monitoring of mineral nucleation and growth in the fluid mixing reaction process can be achieved.

The application provides an accelerated calculation method, a terminal and a treatment planning system for BNCT treatment dose, which comprises: dividing each voxel block in a voxel model into a first voxel block and a second voxel block based on the three-dimensional coordinates of each voxel block; alternately iteratively performing parallel calculation processes of the first voxel block and the second voxel block based on a pre-constructed calculation dependency relationship until a neutron emission flow and a neutron flux of each voxel block are obtained when an iteration stop condition is met; wherein the dependency calculation relationship comprises that the parallel calculation of the first voxel block depends on the neutron emission flow of the second voxel block, and the parallel calculation of the second voxel block depends on the neutron emission flow of the first voxel block; and calculating the BNCT treatment dose based on the neutron flux of each voxel block. The application can form a large-scale parallel calculation task set under the premise of strictly guaranteeing calculation accuracy, maximally compress the iteration convergence period and the overall calculation time consumption, and meet the demand of clinical rapid calculation of the BNCT treatment dose.

The present invention provides a composite deuterium storage coating material for neutron emission tubes and a preparation method thereof. By using a chemical vapor deposition method, a metal transition layer is deposited on the surface of a substrate to further enhance the bonding strength between the coating and the substrate. A metal deuteride thin film is deposited and prepared on the surface of the metal transition layer. By controlling the percentage of deuterium gas introduced during sputtering, the deuterium storage amount in the deposited coating is regulated. On the premise of meeting higher deuterium storage density and good thermal stability, the hydrogen embrittlement resistance and deuterium storage performance of the coating are improved. Finally, a protective layer is deposited on the surface of the deuterium storage thin film to enhance the oxidation resistance and anti-carbonization performance of the deuterium storage composite thin film.

A first aspect of the invention relates to a system for the in-line preparation of a vitrifiable mixture having a target composition, the system comprising: - a unit for dispensing raw materials, which is able to provide a premix comprising cullet, preferably at least 20% by weight of cullet; - a conveyor which is able to move the premix; - a unit for the in-line measurement of the composition of the premix by neutron activation, the in-line measurement unit comprising: • at least one neutron emission source configured to irradiate all or part of said premix; • at least one gamma ray detector configured to detect the gamma rays emitted by the premix when it is irradiated by the neutron emission source; and • a digital processing device configured to calculate, from the signal of the gamma ray detector, the content of chemical elements present in the premix, and optionally configured to estimate the water content and / or the content of organic compounds in the premix; and - at least one means for adjusting the premix to obtain the vitrifiable mixture having the target composition. The invention also relates to a method for the in-line preparation of a vitrifiable mixture having a target composition.

According to a first aspect, the invention relates to an online preparation system for a vitrifiable mixture of target composition, the system comprising: - a raw material distribution unit capable of supplying a premix comprising cullet, preferably at least 20% by mass of cullet; - a conveyor capable of moving the premix; - an online measurement unit for the composition of the premix by neutron activation, the online measurement unit comprising: • at least one neutron emission source configured to irradiate all or part of said premix; • at least one gamma ray detector configured to detect the gamma rays emitted by the premix when it is irradiated by the neutron emission source;and • a digital processing device configured to calculate, from the gamma ray detector signal, the chemical element content present in the premix, and optionally configured to estimate the water content and / or the organic compound content in the premix; and at least one means for adjusting the premix to obtain the vitrifiable mixture of target composition. The invention also relates to a method for preparing a vitrifiable mixture of target composition online. Figure 1.

Method for characterizing isotopes by a plurality of neutron emissions of different spectra. The invention relates to a method (100) for characterizing at least one isotope of a target (4) by neutron irradiation. The method comprises irradiating (110) the target with neutrons generated by a first neutron generator (2); measuring (120) a first spectral response of the target during and after irradiation; identifying (130) a first line produced by a reaction of at least one isotope with neutrons; when the measurement of the first spectral response is complete, irradiating (140) the target with neutrons generated by a second neutron generator (3); measuring (150) a second spectral response of the target during and after irradiation; The identification (160) in the second spectral response of a second line produced by a reaction of the isotope with neutrons. Figure for the abstract: Fig. 2

A cable inspection device non-destructively inspects a cable used for supporting a bridge. The cable inspection device includes a neutron source and a neutron detection device. The neutron source emits neutrons to the cable. The neutron detection device includes a detection surface arranged outside the cable, and detects target neutrons and measures the number of the detected target neutrons when neutrons are emitted to the cable. The target neutrons are among the neutrons released from the cable and incident on the detection surface, and each have an energy equal to or lower than a predetermined value that is lower than an energy of a fast neutron.

The invention relates to an arrayed neutron spectrum measuring device, which is characterized in that a moderator is placed in a box body, the moderator is liquid, and the box body is of a cuboid structure with an opening at the top end and blocked side surfaces; the plurality of thermal neutron detectors are arranged in a row in parallel in an array mode, the plurality of thermal neutron detectors are all located on the axis of a neutron beam emitted by the neutron emitter, the plurality of thermal neutron detectors are placed in the box body from the top end opening of the box body, and the position depths of the plurality of thermal neutron detectors are all determined based on the response matrixes of the corresponding thermal neutron detectors; wherein the position depth is used for indicating the distance between the thermal neutron detector and the neutron emitter, and the response matrix of the thermal neutron detector is obtained in the simulated standard neutron field. According to the invention, a plurality of arrayed thermal neutron detectors are arranged, a moderation ball does not need to be replaced, the measurement process is simplified, a plurality of data are simultaneously measured at one time, the measurement deviation is reduced, and the energy spectrum measurement precision is improved.

The application provides a spin-optical excitation multi-field coupling in-situ neutron scattering sample environment device, which comprises a sample cabin, a sample adjusting platform, a temperature control device and an optical detection device; the temperature control device is connected with the sample adjusting platform and is used for controlling the environmental temperature of the sample table; the optical detection device comprises an optical cabin, a laser emitter, a collimating lens and a liquid crystal wave plate, generates a specified type of polarized light, and finally irradiates the sample on the sample table through a laser window; two opposite sides of the sample table are respectively provided with a neutron incident window and a neutron emission window; in the sample environment device, the temperature control device is integrated to provide a specific environmental temperature for the sample, the optical detection device provides a polarized light environment for the sample, and the neutron scattering technology is used to detect the data of the sample under different temperatures and different polarized light environments, so that the sample detection scene is enriched and the experimental environment of multiple spectrometer lines can be adapted.

A downhole tool is equipped with a neutron generator configured to emit neutrons into a geological formation. The downhole tool includes one or more neutron detectors configured to detect neutrons that return to the downhole tool upon interaction with the geological formation. The downhole tool further includes one or more gamma ray detectors configured to detect gamma rays from the geological formation, the gamma rays being formed when the neutrons are inelastically scattered by the geological formation. Formation density is determined using measurements from a detector combination of at least one of the one or more neutron detectors and at least one of the one or more gamma ray detectors. The first formation density determined using the first detector combination is used to compensate for the second formation density determined using the second detector combination.

A method for obtaining elemental concentration and determining the formation density uses a tool having multiple dual-function detectors that can detect both neutrons and gamma rays simultaneously. The method includes emitting neutrons into the formation, detecting neutron and gamma ray signals from the formation and discriminating the neutron signal and the gamma ray signal, obtaining the space, time and energy dependent fluence rates for fast neutrons and thermal neutrons, obtaining gamma ray energy spectra from initial inelastic gamma rays and backscattered inelastic gamma rays from one or more detectors. The formation density can be calculated based on one or more ratios between the gamma ray count rates at the one or more detectors to the gamma ray count rate at the near detector.

This invention relates to the field of oil and gas exploration and development, and discloses a compensated neutron emission sub and a compensated neutron logging tool. The compensated neutron emission sub includes a shield, a source chamber shell, a source chamber, a neutron emission source, a first conduit, a first conduit connector, a second conduit connector, and a plug-in component. The source chamber shell has a first end and a second end, with the first end facing the detector sub. The shield is disposed at the first end of the source chamber shell, and the plug-in component is disposed at the second end of the source chamber shell. The source chamber is disposed inside the source chamber shell, and the neutron emission source is disposed inside the source chamber. The first conduit is fixed to the outer wall of the source chamber shell through the first and second conduit connectors. By setting the conduit on the outer wall of the source chamber shell, the source chamber shell can be integrally machined, avoiding welding processes. This not only simplifies the manufacturing process but also improves the safety of the compensated neutron logging tool.

The present application relates to the technical field of nuclear radiation measurement, and discloses a kind of measurement method and device for the mass of plutonium in container, according to the gamma and neutron emission characteristics of plutonium, combined gamma spectrum and neutron measurement, realize the complementary advantages of two kinds of detection, avoid the defects of single gamma spectrum by spectrum peak overlap, sample self-absorption interference, single neutron method by particle induced neutron interference.No need to match the same physical standard source to calibrate detection efficiency, with the help of simulation fitting to complete quantitative calculation, reduce the risk of test and irradiation.Dual-path respectively accounts the mean value of isotope mass, effectively weakens systematic error, improves the measurement accuracy of whole component plutonium isotope, can complete the accurate detection of barrel-packed plutonium material under non-destructive condition without opening.