65results about "Scintillation cells" patented technology

An ordering structure scintillator of scintillator and fabrication method is disclosed. The ordering structure scintillator of scintillator comprises: a tubular template, which consists of a plurality of thin film oxidized metal tubes; a plurality of scintillators, filled in the thin film oxidized metal tubes; and a package layer, formed on the surface of the tubular template for protecting the tubular template. In addition, through the fabrication method, the ordering structure scintillator of scintillator can be made by anodic treatment and die casting technology with low cost and rapid production; moreover, the film oxidized metal tubes of the tubular template can be further manufactured to nano tubes by adjusting electrolyte composition, electrolysis voltage, and processing time of anodic treatment, and the aperture size, the thickness and the vessel density of the nano tube can be controlled and ranged from 10 nm to 500 nm, 0.1 μm to 1000 μm, and 10⁸ to 10¹² tube/cm², respectively.

The invention discloses a water body gamma radiation stereoscopic monitoring system and method based on an autonomous underwater vehicle. Modular design is adopted, and the water body gamma radiationstereoscopic monitoring system comprises a gamma radiation detection module, a control module, an energy module and a power module; the gamma radiation detection module extracts gamma radiation in real time, quickly judges whether artificial radioactive nuclides exist or not through a deep learning network system, and collects detection data; the control module adopts an intelligent path planningsystem with Gaussian process regression to control the autonomous underwater vehicle to conduct intelligent cruising according to the gamma radiation measurement result. By means of the water body gamma radiation stereoscopic monitoring system, it can be achieved that stereoscopic distribution of the activity concentration of gamma radiation nuclides in the water body can be efficiently and precisely measured.

The apparatus for the determination of radionuclides in a continuous flow of a fluid comprises an alpha-beta chamber that converts alpha, beta and gamma radiation into photons; a gamma chamber that converts gamma radiation into photons; an external covering shield that isolates the alpha-beta chamber and the gamma chamber from environmental UV-visible light; and means for separatedly sending photons generated in the chambers to an analyzing unit. It permits determinations on-line, remotely, and continuously.

Radionuclide detection devices comprise a fluid cell comprising a flow channel for a fluid stream. A radionuclide collector is positioned within the flow channel and configured to concentrate one or more radionuclides from the fluid stream onto at least a portion of the radionuclide collector. A scintillator for generating scintillation pulses responsive to an occurrence of a decay event is positioned proximate at least a portion of the radionuclide collector and adjacent to a system for detecting the pulses. Methods of selectively detecting a radionuclide are also provided.

The invention relates to a rapid analysis method for multinuclides in a radioactive contaminated soil. The method comprises the steps that 1) drying, reducing, grinding and sieving are carried out onthe radioactive contaminated soil to acquire a radioactive contaminated soil sample; 2) 1 .0g radioactive contaminated soil is weighed for digestion; 3) after digestion is completed, liquid in a teflon tank is slowly evaporated at low temperature to nearly dry; 4) the sample is dissolved with a 10mL nitric acid solution and transferred to a centrifuge tube; 5) 0.5mL sample acquired in the step 4)is moved to a small stainless steel plate to prepare an alpha measurement source plate; 6) the total alpha and total beta of the sample are measured on the liquid scintillation counter, and the ratioof 241Am+328Pu and 239+240Pu in the total alpha is acquired; 7) the Cherenkov count of the sample is measured prior to the liquid scintillation counter, and after the end of the measurement, 137Cs and60Co in the sample are measured again on the gamma spectrum; and 8) the acidity is adjusted to 5.0 mol/L, and the U content in the sample is measured through a 30% TBP extraction spectrophotometric method. According to the invention, more than 3,000 radioactive contaminated soils in the decommissioning process of nuclear facilities are analyzed and determined.

A novel beta-ray detection device disclosed by the present invention solves the problem in the prior art that a conventional beta-ray detection device is narrow in application range and low in detection precision and accuracy due to the large size and the harsh usage conditions. The novel beta-ray detection device of the present invention comprises a beta-ray detection probe, an anti-radiation remote transmission optical fiber, a photomultiplier, a prepositive amplifying and shaping circuit and a PC, is simple in structure, scientific and reasonable in design, high in reliability and accuratein detection data, is convenient to use, and can be used in a closed environment or a high-radiation dose environment. The beta-ray detection probe mainly adopts an inorganic scintillator film material and is plated, thereby shrinking the size of the probe, simplifying the preparation technology of the probe, effectively improving the light extraction efficiency of the scintillator film, being able to convert the radiation information into the optical information effectively while guaranteeing that situation that a scintillator effectively acquires the beta-ray signals.

The invention discloses a scintillation ceramic array and a preparation method thereof. The method includes the steps of obtaining single cuboid ceramic crystal grains through a mechanical processingmethod, and then plating a metal reflection layer on the side surfaces of the cut crystal grains, plating the top surfaces with an epoxy resin reflecting layer, arranging the crystal grains into an array structure through a positioning coupling mold, then pouring a bonding agent into a gap between the crystal grains, and binding the crystal grains into a required scintillation ceramic array. In this way, x-ray interference between different crystal grains is reduced, and the light output performance of the scintillator array is improved.

A neutron capture therapy system includes a neutron ray generating unit, an irradiated body placing unit on which a patient (irradiated body) is placed, and a gamma ray detecting unit that detects gamma rays emitted from the patient (irradiated body). The gamma ray detecting unit includes an emission part that emits light or electrons as the gamma rays are incident thereon, an amplification part that amplifies and outputs the light or the electrons emitted from the emission part, a first neutron ray shielding part formed of a substance containing 6-lithium, and a second neutron ray shielding part formed of a light element. The first neutron ray shielding part is provided so as to cover at least a surface opposite to an adjacent surface adjacent to the amplification part, among surfaces of the emission part.

The invention provides a method and a device for measuring arrival time of high-energy photons. The method includes acquiring relevant arrival time of visible photons detected by every sensor unit in a photoelectric sensor array and generated from reaction between the high-energy photons and scintillation crystals, wherein the scintillation crystals refer to continuous crystals, and the photoelectric sensor array comprises a plurality of sensor units coupled with the scintillation crystals; acquiring to-be-averaged time corresponding to each of at least part of sensor units selected in the photoelectric sensor array at least based on the relevant arrival time of the visible photons detected by every sensor unit in the photoelectric sensor array; averaging the to-be-averaged time corresponding to each of at least part of the sensor units so as to obtain the arrival time of the high-energy photons. The method and the device for measuring the arrival time of the high-energy photons have the advantage that through averaging the to-be-averaged time acquired by the sensor units, high time resolution can be obtained.

The invention relates to a scintillator device regulated and controlled by plasmon crystal. The scintillator device comprises a substrate layer, a first scintillator layer arranged on the substrate layer, a metal period array layer arranged on the first scintillator layer and a second scintillator layer arranged on the metal period array layer. The metal period array layer is formed by cylindrical metal units of square or triangular structures which are distributed in periods. Compared with the prior art, the regulation and control of a light emitting direction and the shortening of attenuation time are concentrated in one scintillator device, and the detection efficiency and the time resolution capability are simultaneously improved in the system application.

The invention discloses a scintillation crystal unit sheet, an array module, and a detector. The scintillation crystal unit sheet comprises a scintillation crystal and a wrapping body. The wrapping body is provided with at least one concave part, and the scintillation crystal is disposed in the concave part. A scintillation crystal array is formed arranging a plurality of crystal units according to a preset design to form crystal unit sheets, and the crystal unit sheets are arranged to form the crystal array module. Each of the crystal unit sheets is formed by disposing each crystal unit on a reflection film in a wrapped manner, and then epoxy glue is used for solidification. The crystal unit sheets are arranged according to the preset design to form the array module, and are solidified by using the epoxy glue. A production method of a scintillation crystal detector array module has advantages of high flexibility, tidy arrangement, compact structure, and easy production.

The invention relates to a rare earth halide scintillating material of which the chemical general formula is RE<1-m>CemX<3+n>, wherein RE is one of rare earth elements such as La, Gd, Lu and Y, and the X is one or two of Cl, Br and I, 0.001 <= m <=1 and 0.0001 <= n <= 0.1. The rare earth halide scintillating material has excellent scintillating performance of high optic output, high energy resolution ratio and rapid attenuation.

The invention discloses a radiation source positioning system and method. The system comprises a detector, a rotating holder and a collecting and processing center. The detector comprises a thin scintillation crystal, a thin blocking sheet and a photoelectric detector. The thin blocking sheet clings to either of the two largest sides of the thin scintillation crystal, and the photoelectric detector is coupled to any side other than the two largest sides of the thin scintillation crystal. The rotating holder is used for making the detector rotate at a preset speed. The collecting and processingcenter is used for obtaining the angle-counting rate response curve of the detector when the detector rotates 360 degrees through the rotating holder, obtaining the normal of the two largest sides under the maximum counting rate, and obtaining the direction of a radiation source according to the normal direction in which the thin blocking sheet points to the thin scintillation crystal. With the system, the direction of a radiation source can be obtained and the radiation source can be found according to the normal direction in which the thin blocking sheet points to the thin scintillation crystal. The detection sensitivity is improved. The positioning vision is expanded. Blind search is avoided. The efficiency of radiation source search is improved.

The present invention discloses a rotary radioactive iodine monitoring system and method. The monitoring system comprises a shielding body, an iodine box, and a NaI detector; the NaI detector is connected with an analysis device; a rotating mechanism is arranged in the shielding body; the iodine box is fixed on the rotating mechanism; the NaI detector is arranged in the shielding body; the iodinebox is in communication with an air inlet pipe and an air outlet pipe; and a sampling pump is arranged on the air outlet pipe. According to the system and method provided by the present invention, theproblem of poor measurement accuracy caused by the existing radioactive iodine monitoring technology is solved.

The invention proposes a sodium iodide or cesium iodide scintillator packing structure and the packing method thereof, wherein the packing method comprises the following steps: adhering the inner surface of a metal housing to the reflection layer; adhering the reflection layer to the sodium iodide or cesium iodide scintillator; placing seal glue at the threaded edges of the metal housing so that the seal glue is adhered to the outer surface of the metal housing; under a vacuum environment, pressing the optical coupling agent to the upper surface of the sodium iodide or cesium iodide scintillator layer to enhance the transmission rate of visible light; adhering the optical coupling agent to the lower surface of the reinforced glass layer wherein the circumference of the reinforced glass layer is all adhered to the seal glue and the seal glue is adhered to the metal housing. With the above method, the cost can be reduced; the seal performance, the light transmission rate and the light reflection rate can be increased; and the manufacturing cycle can be shortened.

The invention discloses a radiation monitoring device, and the device comprises a plurality of detectors arranged in the moving direction of a radiation source, wherein the visual field range of the detectors is divided into two-dimensional plane grids at the position of the radiation source, and rays emitted by the radiation source are detected by at least one of the plurality of detectors in a unit time interval; a data acquisition module which is used for acquiring a signal detected by at least one of the plurality of detectors; and a data processing module which is used for converting thesignals acquired by the data acquisition module into digital signals with position information so as to determine the position of the radiation source. The device can locate the orientation of the radiation source through the change of the dynamic data of the detector, gives a two-dimensional image in combination with the optical camera, identifies and determines a carrier, and realizes early warning.

Belonging to the field of optical materials, the invention discloses a high density tellurate scintillation glass and a preparation method thereof. The tellurate glass comprises the following components: 25-100mol% of TeO2; 0-20mol% of Gd2O3; 0-17.5mol% of Lu2O3; 0-60mol% of WO3; and a rare earth ion activator. Specifically, the sum of the four components TeO2, Gd2O3, Lu2O3 and WO3 is 100mol%; wherein, the external or internal admixing concentration of the rare earth ion activator is 0.1-16mol% of the sum of the four components TeO2, Gd2O3, Lu2O3 and WO3. The invention also discloses a preparation method of the high density tellurate scintillation glass. The preparation temperature of the high density tellurate scintillation glass is not higher than 1000DEG C, and the density is 5.50-6.57g/cm<3>. The high density tellurate scintillation glass has wide application in X-ray medical imaging, industrial online detection, national security supervision, high energy physics or nuclear physicsexperiments.

The invention discloses an experimental device for shortening flicker decay time of a LYSO crystal, and the experimental device comprises a vertically arranged thermal insulation sleeve, wherein the thermal insulation sleeve comprises a vertically arranged sample placing cylinder, the inner area of the sample placing cylinder is a heating cavity, the sample placing cylinder is made of a thermallyconductive insulating material, a crystal fixing mechanism is provided in the middle of the inner surface of the sample placing cylinder, and heating wires are evenly arranged on the outer surface ofthe sample placing cylinder to form a heating layer. The invention also discloses an experimental method of the above experimental device. The invention detects the flicker decay time of the heated sample crystal by setting a photodetector directly above the sample placing cylinder, and finds that the flicker decay time has changed from the original 36-42ns to 8-12ns, thereby overcoming the technical bias that the persons skilled in the art believe that LYSO crystal flicker cannot be used for high-repetition experiments.

The invention provides a manganese (II) complex based on a tricyclohexylphosphine structure as well as a synthesis method and application thereof. Firstly, organic cations are obtained through ionization, and then the organic cations are combined with manganese bromide to form the ionic manganese (II) complex. The types of organic cations or the central configuration of metal manganese of the manganese (II) complex can be changed during synthesis, so that the photophysical properties of the manganese (II) complex can be regulated and controlled. As a cheap metal luminescent material with a wide prospect, the metal organic manganese halide material has a series of advantages of low cost, low toxicity, abundant reserves, excellent luminescent property and the like, and is applied to a plurality of fields such as information storage and encryption, organic electroluminescence, sensors, scintillators and the like.

A scintillator material is made of a zinc-oxide single crystal grown on a +C surface or a −C surface of a plate-shaped seed crystal of zinc oxide including a C surface as a main surface. The zinc-oxide single crystal contains In and Li. In response to an incident radiation, the scintillator material emits fluorescence of less than 20-ps fluorescence lifetime.

The invention discloses a method for identifying the type of incident ray particles or the position of incident action based on the pulse waveform screening of the full waveform statistical characteristics, which includes using a detector to collect a number of pulse waveforms of each type, recording the normalization of the collection The final pulse waveform; for each type of pulse waveform collected, the statistical characteristics of each sampling point are obtained; according to the statistical characteristics of each sampling point, the likelihood of characterizing the shape information of each type of pulse waveform is constructed The function model performs pulse waveform discrimination to determine the type of particle or the position of action. The present invention directly starts from the statistical characteristics of the full waveform, constructs a joint probability density distribution model representing the shape characteristics of the pulse waveform, and then uses the maximum likelihood estimation method to determine the pulse waveform type of the unknown type of waveform pulse to complete the pulse waveform screening. Compared with the existing technology, due to the use of the statistical characteristics of the full waveform, it has stronger anti-noise ability and stronger waveform discrimination ability, especially suitable for applications where there are many types of pulse waveforms and their respective shape characteristics are not significantly different Scenarios, the ability to discriminate pulse waveforms has been improved.