712 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 Ga2O3 heterojunction beta irradiation battery with a multi-groove radioactive source, relates to the technical field of microelectronics, and solves the problems of low energy utilization rate and low energy conversion efficiency of a Ga2O3 nuclear battery radioactive source in the prior art. The battery comprises a filling type multi-groove radioactive source; the Ga2O3 heterojunction diode unit sequentially comprises a P-type ohmic contact electrode, a P-type NiO ion implantation region, an N-type Ga2O3 low-doped epitaxial layer, an N-type Ga2O3 high-doped substrate and an N-type ohmic contact electrode from top to bottom; a multi-T-type radioactive isotope source layer in the filling type multi-groove radioactive source is arranged above the P-type NiO ion implantation region and forms radiation energy coupling with the Ga2O3 heterojunction diode unit; the groove type structure is filled with the radioactive source, the energy deposition of the radioactive source entering the semiconductor conversion device is greatly increased, and the energy conversion efficiency of the Ga2O3 beta irradiation battery is improved.

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 relates to an automatic calibration device and method for continuously monitoring smoke dust concentration, and belongs to the technical field of environment monitoring. The device comprises a drying device, a dynamic heating system, a receiver and a radioactive source, a drying position, a sampling position and a detection position are sequentially arranged from left to right or from right to left; wherein the position where the drying device is located is a drying position, the lower portion of an exhaust pipe wrapped by the dynamic heating system is a sampling position, and the middle position where the receiver and the radioactive source are located is a beta-ray intensity detection position; and calculating the concentration of the smoke dust to be measured by adopting a smoke dust concentration automatic calibration algorithm according to the measured beta-ray intensity and sampling flow. According to the invention, long-time, high-precision, continuous and reliable operation of the light scattering smoke dust concentration continuous monitoring instrument can be ensured.

The invention relates to hot rolled plate thickness measuring equipment, and belongs to the technical field of detection equipment. The hot-rolled plate thickness measuring equipment comprises a control module and a plurality of detection mechanisms. Each detection mechanism comprises a radioactive source and a detection assembly. The detection assembly and the radioactive source are oppositely arranged in the thickness direction of the hot-rolled plate, and a gap for the hot-rolled plate to penetrate through is reserved between the detection assembly and the radioactive source. The detection mechanism is used for measuring the actual thickness size of the hot-rolled plate at the position; at least part of the multiple detection mechanisms can move in a reciprocating mode in the width direction of the hot rolled plate. And the control module controls the detection mechanism to stop or move in the width direction of the hot-rolled plate based on the variance of n actual thickness sizes of the hot-rolled plate continuously measured by the detection mechanism at the same position. The hot-rolled plate thickness measuring equipment provided by the invention can accurately measure the thickness dimension data of each part of the hot-rolled plate.

The invention relates to the technical field of medical imaging, and discloses an image reconstruction method and device for a Compton camera, computer equipment and a storage medium. Comprising the following steps: acquiring current weight distribution and reference weight distribution corresponding to an imaging plane; real radioactive source simulation is carried out based on the current weight distribution, and simulation weight distribution corresponding to the imaging plane is obtained; updating elements in the current source set according to the simulation weight distribution and the reference weight distribution to obtain an updated source set so as to perform image reconstruction on the Compton camera; wherein elements in the current source set are used for representing radioactive source coordinates corresponding to Compton events occurring in the Compton camera. Therefore, the image reconstruction method capable of improving the imaging quality of the Compton camera is realized, and the reconstructed image can reflect the actual distribution condition of the radioactive source more accurately, so that a reliable basis is provided for real-time monitoring of the boron concentration in the BNCT treatment process.

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 a radioactive source library management system, which comprises an intrusion detection unit comprising an infrared detector, an infrared camera and an emergency alarm device; a video monitoring unit; the radiation value detection unit comprises a fixed point radiation detector and a tracing robot moving radiation detector; an access control unit; the management and control platform unit is respectively connected with the intrusion detection unit, the video monitoring unit, the radiation value detection unit and the access control unit and is used for carrying out data acquisition on each unit, and the management and control platform unit is connected with the dynamic display unit and is used for providing display and alarm information for the dynamic display unit. Moving a radiation detector through a tracing robot to regularly collect the radiation dose in the radioactive source library, and judging whether the real-time number of the radioactive sources in the source library and the radiation dose are safe or not; manual collection is not needed, a radiation monitor does not need to be arranged for each radioactive source, the number of devices is reduced, meanwhile, the radiation detector does not need to be fixed to a radioactive source tank, touch is avoided, and damage is not prone to occurring.

The invention relates to a shielding transportation device for an Sr-90 radioactive source, which comprises a shielding container, a protective cover and a transportation bracket, the protective cover is arranged at the upper part of the shielding container, and the transportation bracket is arranged at the lower part of the shielding container; the shielding container comprises a shielding container cylinder, the shielding container cylinder comprises an outer container and an inner container, the inner container is arranged in the outer container, a spring is arranged below the inner container, and the inner container is used for loading an Sr-90 radioactive source. Compared with the prior art, the device can meet the requirement that the radioactive source is loaded and unloaded in a horizontal state, can prevent the radioactive source from scattering under the condition of a transportation accident, still has enough shielding capability, has good transportation interface performance, and can ensure the safety in the transportation process. The chemical forms of the transported Sr-90 comprise 90SrO, 90Sr (NO3) 2 and 90SrTiO3, and the item forms of the transported Sr-90 cover powder, ceramics, solutions, pellets and the like.

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 discloses a real-time determination method, system and equipment for residence time of an afterloading radioactive source, and relates to the technical field of radioactive source detection, and the method comprises the steps: obtaining a radioactive source contour from a video image, screening a longest transverse line segment from the video image, and obtaining an end point coordinate of the longest transverse line segment; searching each scale point on the scale line from the end point coordinate along the direction perpendicular to the scale line by utilizing an iterative vertical line scale line method, selecting the scale point corresponding to the minimum distance from all the distances according to the distance between each scale point and the end point coordinate, and taking the scale point as a radioactive source coordinate; recording the radioactive source coordinate of each frame in the video image, eliminating and fusing the noise frame, obtaining the staying duration of the radioactive source in each radioactive source coordinate according to the video frame rate of the video image and the radioactive source coordinate of each frame, and filtering the preset short staying duration from all the staying durations. According to the invention, the residence position and time of the afterloading radioactive source can be accurately determined.

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 provides a radioactive biological experimental facility radiation environment monitoring and personal dose monitoring method, which comprises a fixed radiation dose monitor, a portable radiation dose monitor, a personal dose instrument, an experimental facility computer system docking port, an analysis center and an early warning judgment module, the experimental facility environment radiation dose can be monitored in real time, single-time operation personal cumulative doses under three different conditions can be obtained through an experimental facility computer system, radiation dose summary analysis can be carried out on radioactive sources operated in the experimental facility, radiation dose changes under different radioactive source operations are obtained, and the experimental facility environment radiation dose monitoring system can be used for monitoring the experimental facility environment radiation dose in real time. And finally, performing early warning according to the environmental radiation dose and the individual accumulated dose result. The environment radiation state can be monitored timely, accurately and effectively, and the external irradiation dose of personnel can be monitored and evaluated in real time.

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.

The invention discloses a collimation array detection system for measuring radioactive source distribution in a complex radiation field, and solves the problems that a traditional complex radiation field construction method is long in time consumption and low in efficiency, the resolution ratio of obtained radioactive source distribution information is low, and life health and safety of workers are difficult to guarantee. The device specifically comprises a detection unit, a collimation shielding unit and a data processing unit. The detection unit comprises a PCB (Printed Circuit Board) assembly, an N * N detector array and a buffer gasket, wherein N is greater than or equal to 2; the N * N detector array is installed on the PCB assembly. The buffer gasket is arranged on the detection end face of the N * N detector array; the collimation shielding unit comprises a detection shell and a collimation assembly which are connected with each other; the PCB assembly, the N * N detector array and the buffer gasket are all mounted in the detection shell; n * N collimation channels penetrating through the two ends of the collimation assembly are arranged in the collimation assembly; the data processing unit is connected with the N * N detector array through the PCB assembly.

The present application discloses a detection method, a surface density device, a detection apparatus, and a storage medium. The surface density device includes a radiation source and an ionization chamber disposed at an interval from the radiation source. The detection method includes: during the operation of the surface density device, obtaining a first current pose of the radiation source and a second current pose of the ionization chamber; confirming a first pose deviation of the radiation source according to the first current pose; confirming a second pose deviation of the ionization chamber according to the second current pose; and determining whether a pose change occurs between the radiation source and the ionization chamber according to the first pose deviation and the second pose deviation. In the detection method according to the embodiments of the present application, the current poses of the radiation source and the ionization chamber are first obtained respectively, and then it is confirmed whether a pose change occurs between the radiation source and the ionization chamber according to the current poses, so that corresponding measures can be taken when a pose change occurs between the radiation source and the ionization chamber, thereby improving the accuracy of the measurement result of the surface density device.

The invention discloses an energy spectrum analysis method based on sample migration, and relates to the technical field of nuclear radiation detection, and the method comprises the following steps: taking a large amount of simulated radionuclide gamma energy spectrum data obtained through a Monte Carlo numerical simulation method as a source domain; taking marked actually measured radionuclide gamma energy spectrum data obtained by measuring a radioactive source through a detector as a target domain; source domain and target domain samples with heterogeneous data distribution are mapped to a shared subspace with discriminative feature representation through feature alignment; aligning samples of a source domain and a target domain with tag space isomerism through tag alignment; and constructing a classification model of the low-count energy spectrum through tree decision. According to the method, effective expansion of the energy spectrum number is realized through data distribution and label space heterogeneous simulated energy spectrum data, and the strong dependence of a classification model on a large amount of actually measured annotated data can be reduced.

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 discloses a radon gas detector test method and related equipment, and the method comprises the steps: obtaining equipment parameters of a tested radon gas detector, and determining the first test concentration of the tested radon gas detector according to the equipment parameters; determining the test distance of the radon gas detector to be tested according to the first test concentration, wherein the first test concentration is in negative correlation with the test distance; controlling the distance between the americium 241 radioactive source and the detected radon gas detector to meet the test distance, and controlling the americium 241 radioactive source to be turned on; acquiring a plurality of first test data acquired by the signal transceiving module from the radon gas detector to be tested during the starting period of the americium 241 radioactive source, wherein the first test data are electric signal data corresponding to alpha particles generated by the americium 241 radioactive source; and determining a test result of the tested radon gas detector according to the plurality of first test data. By adopting the method provided by the invention, the problem of high detection cost caused by a radon source in a traditional detection method is solved.

The invention relates to a gynecological tumor multichannel after-loading radiotherapy source applicator capable of automatically post-expanding, which comprises a central radioactive source catheter, radioactive source catheter sub-blades, a linkage device, a post-expanding gear knob and a fixed handle, and is characterized in that the fixed handle is arranged at the bottom of the central radioactive source catheter; a rear dilation gear knob is arranged at the upper part of the fixed handle; the rear expansion gear knob is connected with a linkage device; the linkage device is provided with a radioactive source conduit branch blade; planting needle holes are formed in the radioactive source catheter branch blades; the source applicator has the advantages that when expansion is not started, the source applicator is small in size and can be conveniently placed into the vagina; after the afterloading radiotherapy source applicator is placed in the vagina, the expansion degree of the afterloading radiotherapy source applicator in the vagina can be regulated and controlled through an external control key, especially the expansion degree of the top end can be larger than that of the middle rear section, and the top end of the source applicator channel can reach the top end of the vagina and extend towards the outer side of the periphery. The conformity and individualization of the radioactive source channel can be realized by flexibly adjusting the position of the radioactive source catheter leaf division, and the radiotherapy effect of the vagina tip and the cervix uteri is obviously improved.

Described herein are methods for beam station delivery of radiation treatment, where the patient platform is moved to a series of discrete patient platform locations or beam stations that are determined during treatment planning, stopped at each of these locations while the radiation source rotates about the patient delivering radiation to the target regions that intersect the radiation beam path, and then moving to the next location after the prescribed dose of radiation (e.g., in accordance with a calculated fluence map) for that location has been delivered to the patient.

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 present invention relates to the technical field of the construction of a radiation field of a radiation source, and provides a safety protection device for a lifting rope of a radiation source, which comprises a two-section lifting rope of an underwater lifting rope and an above-water lifting rope, and the two sections of lifting ropes respectively adopt the redundancy mode of a main rope and a deputy rope. When the radiation source is in a non-operating state, the main body is submerged in a pool, and the lifting rope section connected to the radiation source is the underwater lifting rope, and the lifting rope section located above the pool and connected to the driving mechanism is the above-water lifting rope, and the two sections of lifting ropes are connected through a connecting limit ring. The safety protection device for the lifting rope of the radiation source of the present invention has a simple structure and is convenient to use. The underwater and above-water two independent lifting ropes can be independently protected and maintained. Each section of the lifting rope is provided with a main / deputy rope, and the double redundancy protection can avoid the overall fracture of the lifting rope; the rope can be safely replaced without contacting the radiation source.

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.