317 results about "Radioactive source" patented technology

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 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.

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.

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.

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 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 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.

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.

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.

The invention discloses a Beta radioactive isotope coating and magnetic confinement enhanced air-breathing electric propulsion ionization method. The method is characterized by comprising the following steps: selecting a plasma generation assembly without electrode discharge; the ionization is enhanced by adopting Beta radioactive isotope; arranging a magnetic field in the beta ray radiation direction to carry out magnetic field constraint; by dynamically adjusting the magnetic induction intensity and regulating and controlling the plasma state and the ionization rate, the Beta radioactive isotope (such as nickel-63) is creatively adopted, and the device has the advantages that the service life is long, the protection requirement is low, and mechanical compression and heating cannot induce nuclear reaction. And the requirement on the activity of the radioactive source is fundamentally reduced, so that the material cost and the safety risk are greatly reduced, and the practicability and the safety of the electric propulsion system are improved.

The invention discloses a switch source device, a radiotherapy head and radiotherapy equipment, relates to the technical field of medical equipment, and is used for solving the technical problem that the switch source device of the radiotherapy equipment in the related technology cannot realize source switching in different application scenes. The switch source device is applied to the radiation treatment head, and the radiation treatment head comprises a shielding body, a collimation assembly arranged on the inner side of the shielding body, and a source carrying body arranged between the shielding body and the collimation assembly. The source carrier is used for arranging a radioactive source; the switch source device comprises a first switch source assembly, the first switch source assembly comprises a shielding block and an electromagnetic driving assembly, and the shielding block is used for shielding rays emitted by a radioactive source or enabling the rays emitted by the radioactive source to pass through a collimation assembly; and the electromagnetic driving assembly is connected with the shielding block and is used for driving the shielding block to move along the longitude direction of the shielding body or the collimation assembly and switching between a source closing position and a source opening position so as to realize source switching.

The application discloses a kind of scintillator decay time test methods based on waveform sampling, the steps of test method include: scintillator is coupled to the optical window of photomultiplier tube placed in shielding box, using radioactive source excitation sample, open oscilloscope automatic acquisition not less than 100 pulse signals and transmission to control computer;Pulse waveform data acquired by oscilloscope is handled calculation, obtains the decay time constant corresponding to single pulse data;The above steps are repeated for processing all collected pulse data, obtain decay time constant set;With decay time constant set histogram, data should present normal distribution;Using Gaussian function to the normal distribution is fitted, the decay time value corresponding to the peak obtained is the decay time of the sample.The application can accurately test the decay time of different scintillating materials, especially suitable for high-throughput decay time measurement.

The utility model relates to the technical field of radioactive source detection, in particular to a portable radioactive source positioning device which comprises a detector and a support, and an adjusting assembly used for adjusting the position of the detector is arranged on the support. The adjusting assembly comprises a lead screw, a nut seat and a movable ring, and the nut seat is in threaded fit with the lead screw; the nut seat is fixedly connected with a connecting rod in the circumferential direction of the nut seat; the end, away from the nut base, of the connecting rod is fixedly connected with the inner wall of the movable ring. The detector is slidably matched with the outer wall of the movable ring. The support is provided with a driving assembly used for driving the lead screw to rotate. A limiting assembly used for limiting the movement stroke of the nut base is arranged on the lead screw. The lead screw is further provided with a surrounding assembly used for enabling the detector to rotate around the moving ring. Through the design of the driving assembly and the surrounding assembly, the detector not only can adjust the height acquisition range, but also can acquire multi-directional radioactive source information, so that the positioning precision and efficiency are further improved.

The utility model discloses a support assembly for supporting a delivery catheter and a radioactive source implantation system, the support assembly comprises a support main frame and at least one support sub-frame arranged on the support main frame, the support main frame and / or the support sub-frame can realize pose or shape adjustment, the support sub-frame is used for supporting the delivery catheter, and the support sub-frame is used for supporting the delivery catheter. The conveying catheter is prevented from drooping, so that the conveying catheter is prevented from pulling a puncture needle connected with the front end to damage a target object; the radioactive source implanting system comprises a sleeve type radioactive source implanting device and a supporting assembly, the sleeve type radioactive source implanting device comprises a radioactive source implanting host and a conveying catheter, the supporting assembly is used for supporting the conveying catheter, and the rear end of the conveying catheter is connected with an output port of the radioactive source implanting host. The radioactive source implanting host drives the radioactive source to enter the target object along the conveying catheter. The supporting device is used for supporting different flexible conveying catheters in the operation process so as to adapt to puncture needles with different distances and angles.

The utility model relates to a medical scanning system and a water mold tool for SPECT correction of the medical scanning system. Comprising a water mold, a skeleton and a radioactive source. The framework comprises a plurality of supporting pieces, the supporting pieces are connected with one another and define a polyhedral geometric structure with a containing cavity, and the water mold is arranged in the containing cavity; the radioactive source comprises a long line source, a point source and a short line source, one of the long line source, the point source and the short line source is selected to be arranged on the framework, and the long line source is longer than the short line source; wherein the support piece comprises a first support piece, the length of the first support piece is adjustable, a fixed point is formed at the joint of any two connected support pieces, and one of the long line source, the point source and the short line source is selectively fixed on the first support piece or the fixed point. According to the water mold tool, uniformity calibration of the probe or the collimator, registration correction of the SPECT equipment and the CT equipment and posture and sensitivity correction of the probe can be achieved at the same time, time and labor are saved during calibration, and radiation damage to operators can be reduced.

The invention discloses a real-time image analysis method and system applied to quality control of an afterloading therapy machine, and relates to the technical field of image analysis, and the method comprises the steps: controlling an afterloading radioactive source to be in a non-leading-out state, and capturing an initial image as a background image; after the radioactive source is led out, real-time images are continuously captured, difference images are analyzed through inter-frame pixel differences, and positioning of the resident position of the radioactive source of the afterloading therapy machine is completed; through multi-thread parallel processing, when the result of the frame difference method is abnormal, calling a neural network to supplement detection, and fusing the results of the frame difference method and the neural network model by adopting a dynamic weighted average algorithm; and recording the capture timestamp of each frame of image, establishing an association relationship between time and position by combining the fused positioning result, and analyzing the residence position and time of the radioactive source. According to the method, the frame difference method is combined with the neural network model, high-precision space positioning and time measurement are achieved, and the monitoring accuracy of the radioactive source residence position and time is remarkably improved.

The invention relates to a fermentation method applying'two-time irradiation sterilization ', belongs to the field of fermentation application, and relates to a fermentation method adopting two-time irradiation sterilization, namely'irradiation sterilization on fermentation raw materials before fermentation' and'irradiation sterilization on fermented matured products after fermentation maturing '. The production of infectious microbes needs to be controlled in the fermentation process in the background technology. According to irradiation sterilization, electron beams and gamma rays generated by an irradiation device applying an accelerator or an isotope radioactive source (such as a cobalt-60 gamma source) penetrate through goods to be irradiated, act on microorganisms and directly or indirectly damage ribonucleic acid, protein and enzyme of the microorganisms, so that the microorganisms are killed, and the disinfection and sterilization effects are achieved. According to the invention, an irradiation device of an accelerator (generally 1-10MeV) or an isotope radioactive source (such as a cobalt-60 gamma source) is applied to intervene in the fermentation process. 'irradiation sterilization on fermentation raw materials before fermentation 'is carried out to kill infectious microbes and bacteriophages to reach the required sterilization standard. And the fermentation is stopped by performing irradiation sterilization on the fermented matured product after the fermentation is matured, so that the quality guarantee period for maintaining the quality of the fermented matured product is prolonged. The method can be widely applied to the fermentation fields of tobacco, tea, grains, feed and the like.

The storage cabinet for the radiology department comprises a cabinet body, isolation fixing frames and an isolation cover plate, the two isolation fixing frames are fixedly installed in an inner cavity of the cabinet body, a plurality of circular grooves are evenly formed in the isolation fixing frames, and a plurality of second springs are evenly installed on the bottom faces of the circular grooves. The movable ends of the second springs are connected and provided with clamping supporting plates, a plurality of sets of guide sliding grooves are symmetrically formed in the inner wall of the cabinet body, guide sliding blocks are symmetrically and fixedly installed on the two sides of the three isolation cover plates, the guide sliding blocks are clamped and embedded in the guide sliding grooves, and a plurality of installation bases are evenly and fixedly installed on the bottom faces of the two isolation cover plates. And a plurality of first springs are uniformly mounted on the bottom surface of the mounting seat. The device has the advantages that a stored radioactive source lead tank can be conveniently clamped and fixed, the radioactive source lead tank is prevented from toppling over when being vibrated, when the radioactive source lead tank is taken out for use, the lead tank can be automatically ejected out of a part of an inner cavity of the circular groove, a user can conveniently take out the lead tank in a clamping mode, use is more convenient, and practicability is higher.

The application discloses a PET system correction method and device, a storage medium and computer equipment, relates to the medical image technical field, and mainly can reduce the efficiency correction cost of the PET system detector, and simultaneously reduces the efficiency correction difficulty of the PET system detector. The method comprises the following steps: acquiring single photon counting values collected by each detector in a PET system, wherein the single photon counting value is the number of single photons generated by a radioactive source phantom and collected by each detector in the process that the radioactive source phantom moves along the axial direction of the PET system, and the length of the radioactive source phantom is less than the axial field of view length of the PET system; calculating efficiency correction coefficients of each detector based on the single photon counting values collected by each detector; and determining efficiency correction coefficients of corresponding original coincidence event data of the PET system according to the efficiency correction coefficients of each detector, wherein the efficiency correction coefficients of the original coincidence event data are used for correcting the detection efficiency of the PET system.