522 results about "Radioactive source" patented technology

The invention discloses an adaptive energy calibration method for a Timepix3 detector, and belongs to the field of plasma diagnosis, and the method comprises the steps: collecting a photon event through a detector, the photon event comprising arrival time, coordinates and energy information; sorting the photon events according to the arrival time of the photon events to obtain a sequence; mapping the sequence to an empty matrix in a time window sliding mode, searching and recording the area of a pixel cluster and the sum of count values, and compensating the count values according to a set threshold value; classifying according to the area of the pixel cluster, summing the counting values of the pixels in the pixel cluster to obtain the volume of the pixel cluster, and drawing a statistical histogram of the volume of the pixel cluster to form an energy spectrum; identifying an energy peak of each energy spectrum and performing Gaussian fitting, calculating a peak abscissa, and establishing a relationship between the volume of a pixel cluster and actual energy; and completing energy calibration by utilizing linear fitting of volume energy data of multiple groups of pixel clusters. According to the invention, the requirements for setting parameters such as radioactive source intensity, detector threshold, exposure time and the like are reduced.

The invention discloses a dynamic calculation method and system for a radiation field in the cutting process of an activity non-uniform radioactive source, and belongs to the field of radiation field calculation. The method comprises the following steps: acquiring three-dimensional activity distribution data of a radioactive source; constructing a voxelization model and coupling the voxelization model with an activity grid to distribute activity; establishing an LBVH hierarchical structure of the shielding body; a point kernel is generated in a self-adaptive mode through ray tracing and average free path comparison; carrying out radiation field calculation by adopting point nuclear integration, and realizing multilayer ray tracing in the radioactive source, between the sources and a shield in the process; on-line cutting and moving operation of the voxel model is supported, and the radiation field is dynamically updated. According to the method, the cutting operation of the activity non-uniform radioactive source can be simulated, the problem that the radioactive activity of each cutting product cannot be represented after cutting by a traditional method is solved, the radiation field dynamic calculation in the activity non-uniform radioactive source cutting process can be simulated, initial modeling of the radiation environment only needs to be carried out once, and the efficiency is improved. And repeated modeling is not needed.

The invention discloses a visual classification and intelligent analysis integrated radioactive source automatic verification system and method. The system is characterized by comprising a master control system, a grabbing device for automatically clamping and carrying a source box, automatic verification equipment for automatically verifying the source box, a carrying device for automatically conveying and storing the verified source box, and a lifting platform for driving the source box to lift. The mechanical arm drives the carrying device to replace manual work to clamp the source box on a truck to the automatic verification equipment, the automatic verification equipment automatically verifies the source box, after verification is completed, the mechanical arm drives the carrying device to clamp the source box to the material frame, and the carrying device carries and stores the source box on the material frame to the corresponding stock bin. And automatic verification and storage are realized, so that the identification accuracy and the storage operation efficiency of the radioactive source are improved, and the radiation risk and the labor intensity of personnel are reduced.

The invention discloses a rapid large-scale calculation simulation method and system for gamma radiation dose in a dynamic environment and a storage medium, and belongs to the technical field of ionizing radiation protection. The method comprises the following steps: firstly, constructing a triangular mesh scene model containing a radioactive source and a shielding body, and discretizing the radioactive source into a local point kernel; global coordinates of the point kernel and the vertex of the triangle are calculated in parallel by using a GPU, and a maximum parallelization hierarchical surrounding structure MPBVH of the scene is constructed; ray tracing is executed in parallel on the GPU, and all intersection points of MPBVH calculation rays and the shielding body are traversed to determine the thickness and the material of each shielding layer; and finally, dose values of all counting grids are calculated in parallel by adopting a point kernel method. When a radioactive source or a shielding body in a scene is subjected to dynamic changes such as movement and rotation, geometric data can be quickly updated, and calculation can be executed again. According to the method, the speed of large-scale point kernel calculation is increased, the influence of the environmental complexity on large-scale calculation time consumption is small, and the method can be suitable for rapid large-scale calculation and dynamic updating of the radiation field in the complex dynamic environment.

The invention relates to the technical field of gamma radiation dose calculation, and particularly discloses a gamma radiation dose calculation method based on a Unity engine, a program, equipment and a storage medium. In order to solve the problems that ray tracing is complex and low in efficiency in complex irregular geometry by means of an existing point kernel integration method, the physical calculation capacity of a Unity engine is introduced, ray tracing is conducted through Physics. Raycast interface iteration, and gamma radiation dose calculation under the multi-layer shielding condition is optimized. The method comprises the following steps: acquiring radioactive source energy, intensity, shielding body density, mass attenuation coefficient and detection point coordinates; constructing a radioactive source model and generating a point kernel set through parallel array ray discretization; performing ray tracing on the point core set to obtain a list of all intersection points of rays and the shielding body; and calculating the shielding thickness of each layer according to the intersection point list, calculating the dose contribution of each point core in combination with the accumulation factor, and summing to obtain a total dose value.

A radiation safety apparatus for a semiconductor processing system has a safety fence with a support frame and radiation shields defining containment regions associated with load ports of the semiconductor processing system. The containment regions are associated with radioactive sources that emit radioactive radiation, where radiation shields attenuate the radiation to a region external to the containment regions. The radiation shields have access doors movably coupled to the support frame to provide access to the containment regions. Interlocks are provided with the access doors to selectively lock the access doors in a closed position to control the access to the containment regions from the external region through the access doors. A controller controls the interlocks based on a radiation decay associated with each of the radioactive sources and a predetermined safe radiation exposure level.

The invention relates to a radiation contamination simulation detection equipment control method based on an ultraviolet fluorescence signal, which is applied to radiation contamination simulation detection equipment, and the equipment comprises a detection probe. The method comprises the steps that a fluorescence intensity original signal and an ambient light interference signal of a target area are collected, the distance between a detection probe and a target surface is obtained, a fluorescence simulation agent is sprayed on the target area and irradiated by an ultraviolet LED lamp, and the simulation agent is used for emitting fluorescence with the wavelength larger than 450 nm under excitation of ultraviolet light; based on the distance and the ambient light interference signal, performing coupling compensation on the fluorescence intensity original signal; and calculating a radiation simulation value according to the calibration fluorescence intensity signal, and outputting information such as the radiation simulation value, the safety level and the component type. According to the method, through non-radiation simulation agent replacement, signal calibration and multi-dimensional analysis technical means, the safety of radiation detection training is improved, the health threat of a real radioactive source to trainees is eliminated, and the accuracy and the information amount of a detection result are remarkably improved.

The invention relates to a double-cavity radiotherapy and chemotherapy integrated treatment capsule for brain glioma, which aims to solve the problems that the existing radioactive seed source or chemotherapy carrier cannot give consideration to radiotherapy and chemotherapy, the dosage is difficult to regulate and control, the medicine distribution is non-uniform and the like. The brain glioma double-cavity radiotherapy and chemotherapy integrated treatment bag is composed of a radiotherapy pipeline and a chemotherapy pipeline, the whole integrated treatment bag is a spiral pipe body, the radiotherapy pipeline is located in an inner ring, the chemotherapy pipeline is located in an outer ring, the radiotherapy pipeline is a closed cavity, a liquid radioactive source is contained in the closed cavity, and the liquid radioactive source is located in an outer ring. The chemotherapy medicine is released from the head end of the chemotherapy pipeline, the chemotherapy medicine is injected from the tail end of the chemotherapy pipeline, and the surface of the integrated treatment bag is coated with a composite antibacterial layer. According to the integrated treatment capsule, radiopharmaceuticals and chemical drugs are placed in the inner cavity and the outer cavity respectively, synergistic treatment of radiotherapy and chemotherapy is achieved through the synchronous effect of the two channels, and long-term low-dose release of the radiopharmaceuticals and the chemotherapy drugs is achieved and toxic and side effects are reduced by adjusting the screw pitch and the thickness of the tube wall.

The invention provides a radioactive source personal dose real-time monitoring device and a radioactive source personal dose real-time monitoring method based on a double-range self-adaptive mechanism. The radioactive source personal dose real-time monitoring device and method are suitable for intraoperative individual dose collection and dynamic evaluation in the tumor radiotherapy process. The device comprises a flexible attaching substrate, a first measuring range detection sub-module, a second measuring range detection sub-module, a self-adaptive scheduling unit, a temperature compensation module, a breathing synchronous correction module and a wireless communication module. The device can respond to different dose intensities in real time and adaptively switch or fuse channels; the collected dose projection is restored to a planned coordinate system through a breathing phase recognition and target region drift model, and dynamic target region dose tracking is achieved; temperature correction and wireless transmission functions are combined, and intraoperative data visualization and postoperative evaluation are supported. According to the invention, the precision and safety of radiotherapy dose monitoring are improved, and the method is especially suitable for radiotherapy management of areas with significant respiration-induced drift or adjacent key organs.

A quality assurance method for a radiotherapy device is disclosed. The method comprises disposing a phantom on a patient couch of the radiotherapy device, moving the patient couch to simulate motion of a subject, determining a measured value associated with the phantom, and comparing the measured value to an expected value. A radiotherapy device is also disclosed, the radiotherapy device comprising a radiation source configured to apply a radiation beam, a patient couch, a phantom disposable on the patient couch, and a controller communicatively coupled to the patient couch. A computer-readable medium storing instructions is also disclosed. A phantom for a radiotherapy device is also disclosed.

The invention relates to the technical field of logging equipment, in particular to a density logging instrument structure and an assembling method.The density logging instrument structure comprises a logging instrument shell, a column body and a gravity center deviation part, the gravity center deviation part enables the gravity center of the shell to deviate to one side of a well wall, a containing cavity is formed in the gravity center deviation part, and a shielding body is arranged in the cavity; the shielding body is provided with a first mounting hole for mounting a radioactive source and a radiation hole, a radioactive source protection piece is arranged in the radiation hole, a gravity center deviation part is provided with a protection cover plate, and a ray window cover plate opposite to the radiation hole is arranged on the protection cover plate; the invention further comprises an assembling method of the structure, such as the steps of fixing the shielding body, plugging the protection piece, installing the radioactive source, installing the protection cover plate and the like. The technical effects that the gravity center of the logging instrument structure deviates to one side of the well wall, the logging instrument can make contact with the well wall surface for measurement conveniently, the assembling method is safe and convenient, and the radioactive source can be effectively protected are achieved.

The invention discloses a multi-channel radioactive source implantation system with a needle withdrawing driving function, which comprises a push rod output channel, a push rod, a push rod driving mechanism, a first connecting part, a first motion platform and a needle withdrawing driving mechanism, and is characterized in that the push rod pushes a radioactive source arranged in front of the push rod to be output along the push rod output channel; the first connecting part and one end of the push rod output channel are arranged on the two sides of the first moving platform respectively, the needle pulling driving mechanism and one end of the push rod output channel are arranged side by side, and the first moving platform drives one end of the push rod output channel and the needle pulling driving mechanism to move relative to the first connecting part. The push rod output channel is butted with different hole sites through the relative movement of the push rod output channel and the first connecting part, so that multi-channel implantation of radioactive particles is realized; the puncture needle is automatically pulled out through the needle pulling driving mechanism, the implantation precision and the implantation effect are improved, full-automatic operation is achieved, the radiation risk is avoided, the operation time is short, the structure is simple and reasonable, and driving is convenient and fast.

The present application relates to a kind of bubble method tritium sampler sampling efficiency determination method, gas generated by water vapor generator is passed into tritium sampler, sampling flow in gas path is controlled by flowmeter, after sampling, sampling efficiency is the ratio of the mass of tritium sampler and the mass of water vapor generator.The present application realizes using water vapor generator to generate water vapor as sampling gas source to replace non-radioactive method of tritium water vapor gas source, while using weighing method to measure and calculate bubble method tritium sampler, sampler sampling efficiency, effectively avoids the problem of tritium water vapor activity concentration traceability, avoids the risk of contamination of tritium sampler, sampler and tritiated water vapor leakage in the process of efficiency determination using tritiated water vapor gas source.The present application provides a convenient, fast, non-polluting, no need to operate radioactive source and safe determination method for bubble method tritium sampler, sampler sampling efficiency determination.

An automatic shutdown control device and a radiation source system are disclosed. The automatic shutdown control device includes a first actuator (15), a first one-way throttle valve (6), a first pilot-operated one-way throttle valve (11), a first directional valve (110), a fluid pressure source (1), a first return line, a fluid control valve (10), and a first accumulator (13). The first pilot-operated one-way throttle valve (11) includes a second one-way throttle valve (112) and a first one-way valve (111). When power is off, the first directional valve (110) switches to a second operating position (123), the outlet of the fluid pressure source (1) is connected to the through port of the second one-way throttle valve (112) through the first directional valve (110), and the through port of the first one-way throttle valve (6) is connected to the inlet of the first return line through the first directional valve (110). When the fluid pressure source (1) is outputting, the fluid control valve (10) switches to the closed position (101); when the fluid pressure source (1) is disconnected, the fluid control valve (10) switches to the open position (102), and the outlet of the first accumulator (13) is connected to the closed port (B2) of the first actuator (15) through the fluid control valve (10). This device can automatically complete the shutdown action in the state of power failure and / or flow interruption, without the need for manual shutdown, reducing the risks associated with manual operation.

1. The name of this design product: Lateral detection passive nuclear level meter. 2. Application of this product: It is used to detect the material in the container by using the side of the crystal in the sensor without the need for a radioactive source. 3. The key point of the design of this product lies in its shape. 4. The picture or photo that best illustrates the key points of the design: Design 3 3D diagram. 5. Designate Design 3 as the base design.

The embodiment of the invention provides a radioactive source reversing device and a radioactive source reversing method. The radioactive source reversing device comprises a first storage tank, a second storage tank, an operation rod and an adsorption assembly. The operating rod is provided with a holding end and an operating end, the adsorption assembly is arranged at the operating end, and the adsorption assembly adsorbs the radioactive source so that the radioactive source can be selectively stored in any one of the first storage cavity and the second storage cavity. According to the radioactive source reversing device, the radioactive source can be firmly adsorbed through the adsorption assembly, the stability is high, the falling risk of the radioactive source in the transferring process can be greatly reduced, and therefore the fixing effect on the radioactive source can be improved.

The invention discloses a high-efficiency multichannel positron annihilation lifetime measurement method and device. The method comprises the following steps: 1) detecting instant gamma photons generated by positron of a target radioactive source and positron annihilation gamma photons by using a plurality of detectors, converting the instant gamma photons and the positron annihilation gamma photons into analog signals, and sending the analog signals to a sampling circuit; 2) a sampling circuit is responsible for sampling and digitally processing analog signals generated by each detector and then uploading the analog signals to an upper computer; and 3) the upper computer analyzes and processes the uploaded data to obtain the positron annihilation lifetime of the target radioactive source. The sampling circuit comprises a trigger module, a sampling module, a digital module and a control module. The control module configures each module according to a program issued by upper computer program control software. When the detector input signal meets the setting of the trigger module, the sampling module starts or stops sampling the detector signal of each channel; the digital module carries out digital processing on the signals, converts the signals into data and uploads the data to an upper computer.

The present disclosure relates to a method, device, storage medium and electronic device for measuring radioactivity, the method comprising: obtaining an absorption factor of a shielding medium corresponding to each of a plurality of target radioactive objects in a target container and an absorption factor of the target container, the absorption factors representing absorption efficiencies of radioactive rays of the target radioactive objects; and determining radioactivity of the target radioactive objects according to the absorption factors of the shielding medium and the absorption factor of the target container. In this way, the radioactivity of the target radioactive objects is determined according to the absorption factors of the shielding medium and the absorption factor of the target container, thereby avoiding the problem of poor accuracy of the analysis result of the radioactivity due to non-uniform radioactivity of the plurality of target radioactive objects, and effectively improving the accuracy of the radioactivity measurement result when the plurality of target radioactive objects are non-uniform radioactive sources.

This invention discloses a method for estimating radioactive release during the preparation of radioactive metal waste, comprising the following steps: (1) conducting gamma dose rate surveys and delineating the distribution of radioactive pollution in the radioactive source area; (2) setting up monitoring points in the radioactive metal waste areas with different pollution levels, and calculating the radioactive residue in the metal waste based on the monitoring data; (3) calculating the total release of each nuclide in the metal waste based on the above-mentioned radioactive residue in the metal waste and the obtained concentration data of radionuclides in the metal waste. By conducting gamma dose rate surveys and delineating the distribution of radioactive pollution in the radioactive source area; setting up monitoring points in the delineated areas to obtain the radioactive residue in the metal waste; and calculating the total release of each nuclide using formulas, the process is simple, easy to operate, and can obtain effective data on the total release of nuclides, providing data support for the preparation of radioactive contaminated metal waste and supporting the assessment of the dose caused by contaminated metal waste to the public.

The application discloses a kind of nuclear material plate uranium uniformity detection devices, it includes the feeding roller way conveying device (1) sequentially arranged from left to right, support (2) and discharging roller way conveying device (3), support (2) is respectively provided with detector assembly (4) and calibration assembly (5) on front and rear ends, detector assembly (4) is set to the front side of feeding roller way conveying device (1), detector assembly (4) includes linear module (6), detector (7) and gamma ray radiation source (8), linear module (6) is set to the top surface of support (2), the slider (22) of linear module (6) is fixed with connecting frame (9), the rear end of connecting frame (9) is provided with L plate (10), and the horizontal plate of L plate (10) is provided with gamma ray radiation source (8).The beneficial effects of the present application are: compact structure, realize the automatic flow detection of the uranium surface density value of nuclear material plate, improve the detection efficiency, simple operation.

The invention discloses a radioactive source identification method based on attenuation model inversion, and belongs to the field of radioactive source spatial position and intensity information estimation. Detecting unknown source parameter posteriori estimation results at present; executing a decision-making method based on an attenuation model information distance by using the mobile robot, and inverting that the radioactive source position is located on an extension line of a measurement point when detecting that some of the measurement points pass by the mobile robot conform to the attenuation model; carrying out collinearity measurement point detection to realize collinearity constraint and positioning optimization, and confirming the collinearity through geometric inspection and statistical inspection; and completing the search of the radioactive source until the termination condition of the search task is met. The radioactive source positioning cost is low, the positioning efficiency is high, and the reliability is good.

The utility model provides an interactive experience teaching aid simulating a level gage for science popularization. The interactive experience teaching aid comprises an experiment container and a U-shaped pipe communicated with the bottom of the experiment container. The immersion liquid sensor is arranged on the side of the U-shaped pipe, and a sensing head of the immersion liquid sensor can be inserted into the U-shaped pipe; the simulated radioactive source and the simulated detector are detachably connected with the container support frame of the experimental container; the experiment container is communicated with a U-shaped pipe, so that the experiment container is flush with the liquid level of an inner cavity of the U-shaped pipe, when the amount of the injected liquid material reaches a threshold value set for science popularization demonstration teaching, an induction head of the immersion inductor makes contact with the liquid material in the inner cavity of the U-shaped pipe, and then the immersion inductor sends a signal to the simulated detector electrically connected with the immersion inductor. The buzzer and the light of the simulated detector flicker to remind an operator that injection of liquid materials is stopped when the threshold value set by teaching is reached, and the simulated radioactive source is only the same as a real radioactive source in appearance and does not have radioactivity, so that radiation damage to the operator is avoided.

The invention provides a radioactive source for a thickness measuring device, and the radioactive source comprises a box body part which is provided with a containing cavity and an exit window, and the containing cavity is used for containing beta radioactive gas; the collimation part is arranged on the box body part, a plurality of emergent channels which are arranged at intervals are formed, the emergent channels are conducted in the first direction, and the emergent window covers one end of each emergent channel; the electric field generating part is arranged in the box body part and is used for forming an electric field in the accommodating cavity; the direction of the electric field is parallel to the first direction, and the electric field points to the interior of the containing cavity from the emergent window. According to the radioactive source, beta rays emitted to the emergent window in the accommodating cavity or beta rays emitted through the emergent window can be screened by utilizing the collimating part, so that part of beta rays with high consistency with the first direction can be emitted out of the box body part through the emergent channel and the emergent window so as to participate in thickness measurement of an object to be measured; therefore, the collimation of the emitted beta ray is improved, and the measurement precision of the thickness measurement device is improved.

A radiation treatment system includes a rotatable gantry that is configured to rotate about a treatment isocenter of the radiation therapy system, a treatment-delivering radiation source that is coupled to the rotatable gantry and directs a treatment beam through the treatment isocenter of the radiation therapy system, a first X-ray imager that is coupled to the rotatable gantry, and a second X-ray imager that is mounted on a component of the radiation therapy system and is fixed in position relative to a couch of the radiation therapy system while the rotatable gantry rotates about the treatment isocenter.

The invention provides an online self-checking method and system for a parallel plate ionization chamber and a beam loss monitoring system, and relates to the technical field of particle accelerators, the parallel plate ionization chamber comprises a bias pole plate and a signal pole plate, and a composite voltage formed by superposing a DC bias voltage and a preset low-frequency AC oscillation voltage is applied to the bias pole plate; a test current with the same frequency as the low-frequency alternating-current oscillation voltage is induced on the signal pole plate by using the natural capacitance between the bias pole plate and the signal pole plate; the test current is collected and analyzed to obtain at least one preset characteristic parameter, and the characteristic parameter comprises a quantity related to the magnitude or period of the test current; and comparing the characteristic parameters with a preset reference value so as to judge the health states of the parallel plate ionization chamber and the signal measurement link thereof. According to the invention, a radioactive source and a complex mechanical structure do not need to be additionally arranged, and online self-inspection with high reliability and comprehensive diagnosis of the parallel plate ionization chamber can be remotely realized.

The utility model discloses a radioactive source recovery tank which comprises a recovery tank body and a first quick connector, the recovery tank body is provided with a storage cavity used for storing a radioactive source, one end of the recovery tank body is provided with a water inlet communicated with the storage cavity, and the other end of the recovery tank body is provided with an opening. The first quick connector is installed at the opening of the recycling tank body in a replaceable mode through a quick connecting structure, when the first quick connector is installed at the opening of the recycling tank body, the first quick connector is provided with a filtering part, one end of the filtering part is communicated with the storage cavity, and a water outlet is formed in the end face or the side face of the first quick connector and communicated with the other end of the filtering part. And the first quick connector is mounted at the opening of the recovery tank body, so that the functions of recovering, storing, cleaning and drying the radioactive source are realized.

The invention relates to the technical field of isotope batteries and discloses a preparation method of a transducer device and a preparation method of an isotope battery, the preparation method of the transducer device comprises the following steps: S1, preparing a to-be-fragile layer on the surface of a soluble substrate, the to-be-fragile layer comprising solvent atoms; s2, preparing a first solute layer on the surface of the layer to be fragile; s3, heating at least one of the soluble substrate, the to-be-fragile layer and the first solute layer; s4, a, etching is carried out on the surface of the fragile layer; and S5, a transducer device is prepared on the surface, with the preset shape, of the fragile layer. According to the preparation method of the transducer device, the technical problems of how to prepare the transducer device with effective thickness, realizing large-scale three-dimensional structure preparation on the surface of the transducer device and uniformly loading a radioactive source on the surface of the three-dimensional structure can be solved, the transducer device can be prepared on the fragile layer, and the radioactive source can be uniformly loaded on the surface of the three-dimensional structure by utilizing the pulverization property of the fragile layer. Therefore, a substrate-free energy conversion device can be obtained, and the effective radiation receiving area of the energy conversion device can be increased.

To provide a radioactivity measurement device capable of suppressing a decrease in working efficiency and an increase in working time during calibration using a standard radiation source.SOLUTION: A radioactivity measurement device 10 includes an identification medium 11, an information storage unit 12, an information reading unit 14, and a processing device 17. The identification medium 11 is provided on a standard radiation source S. The information storage unit 12 stores information on the standard radiation source S. An information reading unit 14 acquires information of the identification medium 11. The processing device 17 acquires at least a part of the information associated with the standard radiation source S among the information stored in the information storage unit 12 according to the information acquired from the identification medium 11 by the information reading unit 14.SELECTED DRAWING: Figure 1

The utility model relates to the technical field of pipeline detection, in particular to a support for a pit detection environment of digital radiographic detection equipment, which comprises a telescopic rod and a bracket arranged at the top of the telescopic rod and used for placing a radiation source. The telescopic rod comprises four supporting rods fixedly connected with the bottom of the bracket, adjusting sleeves arranged on the peripheral faces of the supporting rods in a sleeving mode, adjusting columns fixed to the peripheral faces of the supporting rods and close to the bottom ends of the supporting rods, and adjusting rings in threaded connection with the peripheral faces of the adjusting sleeves. Threads are arranged on the peripheral face of the adjusting sleeve, a notch is formed in the length direction of the adjusting sleeve, threads are arranged in the adjusting ring, the adjusting column extends out of the notch, the bottom of the adjusting column is clamped on the adjusting ring, and by screwing the adjusting ring, the adjusting ring drives the adjusting column to move upwards or downwards so that the overall length of the telescopic rod can be increased or decreased; the support has the advantages of being capable of meeting detection requirements of detection pits with different depths, easy to manufacture and low in cost.

The application relates to the technical field of particulate matter monitoring, and discloses a beta radioactive source radioactivity detection instrument, which comprises an L-shaped shell, an opening is formed in the top of the shell, a U-shaped protective cover is hinged to the opening, a touchable display panel for displaying radioactivity information is fixedly installed at the top of the shell, and two detection tables are arranged in the shell. The beta radioactive source radioactivity detection instrument is convenient for workers to replace the beta radioactive source on the other detection table when the equipment is used to detect the beta radioactive source installed on one of the detection tables, solves the problem that the equipment needs to wait for the workers to replace the beta radioactive source after one round of beta radioactive source detection is completed before the next round of detection work is carried out, causes time waste, reduces work efficiency, has the function of synchronous feeding and discharging, and further improves the functionality and practicability of the equipment.