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37results about How to "Reduce the risk of exposure to radiation" patented technology

Radiopharmaceutical pigs and portable powered injectors

InactiveCN101184518ALower Query GraphLower the spreadsheetInfusion syringesRadiation measurementEngineeringRadiation shield
Certain embodiments of the invention relate to a radiopharmaceutical system having a shielded cordless injector and various radiopharmaceutical pig and syringe structures that permit the syringe to remain in the pig during transportation and use of the syringe. In some embodiments, the shielded cordless injector may include an injector, a radiation shield disposed at least partially about the injector, a drive coupled to the injector, and an energy storage device coupled to the drive. The pig may have a computer with a display screen that displays a radioactivity level of a radiopharmaceutical and / or a desired (e.g., correct) unit dose volume of a radiopharmaceutical to be administered to a patient.
Owner:MALLINCKRODT INC

Mobile on-line radioactive decontamination system for nuclear power plant

The invention discloses a mobile online radioactive decontamination system for a nuclear power plant, which includes a mixing tank, an injection pump, a buffer tank, a decontamination pump and an electric heater. The decontamination system includes at least two movable modules, and each movable module All are equipped with input and output interfaces for connecting with other movable modules or equipment to be decontaminated; mixing tanks, injection pumps, buffer tanks, decontamination pumps and electric heaters are respectively set in the movable modules; when in use, the The movable module is moved to a suitable position, and the movable module and the online equipment to be decontaminated are connected to each other in a predetermined order through the connection interface, so that the liquid in the mixing tank can pass through the pipeline in turn through the injection pump, buffer tank, decontamination pump and electric decontamination pump. After the heater enters the equipment to be decontaminated, the equipment to be decontaminated is decontaminated online. The advantages of the present invention are as follows: the present invention can carry out online decontamination of the equipment to be decontaminated in the nuclear power plant, thereby simplifying the operation, reducing the radiation dose of personnel and reducing the risk of radiation exposure.
Owner:中广核工程有限公司 +1

Microwave heating treatment system for high-radioactivity nuclear industry waste

The invention discloses a microwave heating treatment system for high-radioactivity nuclear industry waste, and relates to the technical field of treatment of the high-radioactivity nuclear industry waste. The microwave heating treatment system comprises a sealing box and a control system. A microwave heating hole is formed in the top of the sealing box. A lifting device is arranged below the microwave heating hole. A sealing door is arranged on the sealing box. A first conveyor for feeding or taking a barrel containing high-radioactivity waste liquid to or away from the lifting device is arranged in the sealing box. A second conveyor is arranged on the outer portion of the sealing box. The control system comprises a touch screen and a PLC (programmable logic controller) electrically connected with the touch screen. The PLC is connected with the first conveyor, the second conveyor, the microwave heating hole and the lifting device electrically. The microwave heating treatment system has the advantages that automatic delivering, sealing, and microwave heating and evaporating of the barreled high-radioactivity waste liquid are realized, the whole process does not need manual on-siteoperations, and no high-radioactivity waste liquid exists on an equipment maintenance site, so that working efficiency is improved, and the risk that operators are radiated is reduced.
Owner:四川固力铁环保工程有限责任公司

Temperature loading device for neutron scattering experiment

The invention provides a temperature loading device for a neutron scattering experiment. The device comprises a heating furnace assembly, a translation sample stage assembly and a pneumatic lifting bracket assembly, wherein the heating furnace assembly comprises a furnace body cavity, an incident window plate, an emergent window plate and a water cooling pipe; the translation sample stage assembly comprises a servo electric cylinder, a sample stage surface and a sample stage base; the pneumatic lifting bracket assembly comprises a lifting air cylinder, a high position limit switch, a low position limit switch, a movable bracket and a lifting base. A sample loading hole is formed in the heating furnace in the temperature loading device for the neutron scattering experiment, is matched with the pneumatic lifting bracket assembly to complete automatic loading and unloading of the heating furnace of samples, and is coordinated with a blocking state of the translation sample stage assembly, so that in-situ temperature environment loading of multiple samples and automatic switching of the samples in the neutron scattering (diffraction) experiment can be achieved, the labor intensity of an experimenter and the ray irradiation risk are reduced, and the sample switching time is shortened.
Owner:INST OF NUCLEAR PHYSICS & CHEM CHINA ACADEMY OF

Automatic welding seam scanning device for water chamber locating plate of heat exchanger of nuclear power station

The invention belongs to the technical field of nondestructive inspection of a nuclear power station, and particularly discloses an automatic welding seam scanning device for a water chamber locatingplate of a heat exchanger of a nuclear power station. The automatic welding seam scanning device comprises an installation rail and a scanning assembly arranged on the installation rail in a sliding manner, wherein the scanning assembly comprises a framework arranged on the installation rail in a sliding manner, one or more scanning rail segments rotatably connected with the framework and a scanning rail car provided with a welding seam inspection device; and the scanning rail segments are unfolded to form a scanning rail for the movement of the scanning rail car. The scanning rail of the device adopts a folded structure, and the scanning rail can be folded in the installation and disassembling process, thereby reducing the overall size; after entering the water chamber, the scanning railcan be unfolded to form a long rail, thereby widening the scanning range of the device; and the installation and disassembling of the device are performed outside the water chamber, so that personneldo not need to enter the water chamber, thereby reducing the irradiation risk of the personnel.
Owner:CGNPC INSPECTION TECH +3

Nuclear fuel reprocessing plant plutonium product transfer device

The invention belongs to the technical field of nuclear fuel reprocessing plant radioactive material radiation shielding design, and particularly relates to a nuclear fuel reprocessing plant plutoniumproduct transfer device. The device is used for containing plutonium product cups containing plutonium products in a sealed mode. A shielding layer comprises a first stainless steel shielding layer,a neutron shielding layer and a second stainless steel shielding layer which are sequentially arranged from inside to outside. The first stainless steel shielding layer is used for shielding alpha particles and part of beta rays and gamma rays emitted by the plutonium product cups. The neutron shielding layer is used for shielding neutrons emitted by the plutonium products. The second stainless steel shielding layer is used for shielding the gamma rays and bremsstrahlung photons and secondary photons generated after passing of the neutron shielding layer. By means of the device, neutron rays and the gamma rays can be greatly reduced, the neutron and photon radiation risk generated in the transferring process of the plutonium product cups is greatly reduced, and meanwhile the alpha particles and the beta rays can be completely shielded and the stability of the device is considered.
Owner:CHINA NUCLEAR POWER ENG CO LTD

Gamma camera based on double encoding plates and method thereof for positioning radioactive materials

The invention discloses a gamma camera based on double encoding plates and a method for positioning radioactive materials, belongs to the field of radiation detection technology and radioactive monitoring, and can obtain high-resolution radiation images greater than the number of pixels of an array detector. The gamma camera provided by the invention comprises a first encoding plate, a second encoding plate, an encoding plate switching device, an array detector, a detector position conversion device, a depth camera, a data acquisition processing system and a shielding structure. By using two encoding plates and one array detector, a higher-resolution radiological image can be obtained by performing twice radiological imaging and superimposing the images. At the same time, the energy spectrum and dose data can be obtained by the detector, and the measurement of positions, types, activities and doses of radioactive materials can be realized by combining the distance detection function ofthe depth camera, thereby realizing a multifunctional and multipurpose radioactive location positioning method.
Owner:NANJING UNIV OF AERONAUTICS & ASTRONAUTICS

CFETR (Chinese fusion engineering testing reactor) vacuum chamber pre-grinding piece longitudinal weld joint automatic flaw detection positioning device

The invention discloses a CFETR (Chinese fusion engineering testing reactor) vacuum chamber pre-grinding piece longitudinal weld joint automatic flaw detection positioning device. The device comprisesa flaw detection vehicle capable of operating in an interlayer of an outer shell and an inner shell of a vacuum chamber pre-grinding piece; and a radiation source machine is arranged on the inner side of the inner shell. The problem that the interlayer of the inner shell and the outer shell of the CFETR vacuum chamber pre-grinding piece is difficult in sheet distribution is solved, the work riskof workers is lowered, and the flaw detection requirement of the installation site of the vacuum chamber pre-grinding piece is met.
Owner:合肥聚能电物理高技术开发有限公司 +1

Automatic laser decontamination equipment for radioactive contamination plate of nuclear power station

PendingCN113369244AImproving the Work Efficiency of Laser DecontaminationReduce the risk of exposure to radiationCleaning using gasesNuclear engineeringRadioactive contamination
The invention belongs to the technical field of nuclear power station radioactive decontamination, and provides automatic laser decontamination equipment for a radioactive contamination plate of a nuclear power station. The automatic laser decontamination equipment comprises a rack, a conveying mechanism, a laser head and an air suction assembly, wherein the conveying mechanism is arranged on the rack and is used for conveying the radioactive contamination plate; the laser head and the air suction assembly are sequentially arranged above the conveying mechanism in the conveying direction of the conveying mechanism, the laser head is arranged on the rack and used for emitting laser to the surface of the radioactive contamination plate, and the air suction assembly is arranged on the rack and used for absorbing stains falling off from the surface of the radioactive contamination plate. According to the automatic laser decontamination equipment, the radioactive contamination plate can be automatically conveyed forwards; rusty spots or coatings and the like on the surface of the radioactive contamination plate can be automatically removed through laser decontamination; and meanwhile, falling stains can be automatically absorbed, the work efficiency of laser decontamination of the radioactive contamination plate can be remarkably improved, and the risk that a worker suffers from radiation can be reduced.
Owner:GUANGDONG NUCLEAR POWER JOINT VENTURE +3

Disassembly method of irradiation device

The invention discloses a disassembly method of an irradiation device. The disassembly method comprises the following steps of: S10, hoisting the irradiation device; S30, moving the irradiation deviceto a shielding device, putting an activated section of a cylindrical shell into the shielding device from an opening of the shielding device, and exposing at least part of a safety section of the cylindrical shell out of the shielding device; S50, cutting off the part, exposed out of the shielding device, of the safety section; and S90, completely putting the residual irradiation device into theshielding device. According to the technical scheme, the risk that workers are irradiated can be reduced, and the irradiation dose of the workers, the irradiation objects and the radiation safety of awork site can be effectively and safely supervised.
Owner:CHINA INSTITUTE OF ATOMIC ENERGY

Method and apparatus for determining ideal single-lifting counting rate

The invention, which belongs to the technical field of the computer, discloses a method and apparatus for determining an ideal single-lifting counting rate. The method comprises: distances between unit regions in a curved surface formed by rotation of a bar source of radioactive activity in a direction parallel to an axial direction of positron emission tomography (PET) equipment at a first distance being a distance to the axis of the PET equipment and all crystals of the PET equipment as well as angles of each unit region and each crystal are determined; and according to the distances between the unit regions and the crystals and the angles of each unit region and each crystal as well as a preset ideal single-lifting counting rate algorithm, a current ideal single-lifting counting rate of each crystal is determined. Therefore, being close to a radioactive solution by a technicist for long time can be avoided and thus the risk of radiation on the technicist can be reduced; and an accident can be prevented.
Owner:赛诺联合医疗科技(北京)有限公司

Medical puncture device

The invention provides a medical puncture device which comprises a puncture gun and a puncture needle. The puncture needle is provided with an operating mechanism and a clamping and locking mechanism in linkage with the operating mechanism, and the operating mechanism is exposed outside the puncture gun when the puncture needle is disposed in a containing cavity of the puncture gun; the operating mechanism is operated to drive the clamping and locking mechanism to move in the containing cavity, and the clamping and locking mechanism squeezes an elastic part in the containing cavity and is matched with a clamping and locking matching mechanism in the containing cavity to enable the clamping and locking mechanism to be in an elastic locking state. The medical puncture device is simple in structure, small in size and light in mass, convenience is brought to medical staff for actual use, and both structural stability and reliability are guaranteed.
Owner:孙龙

Hydrogen isotope on-line analysis micro-chromatography measurement and control system and control method thereof

The invention discloses a hydrogen isotope on-line analysis micro-chromatography measurement and control system and a control method thereof. The system comprises an upper computer, an embedded processor, an analog quantity input module and a thermal conductivity concentration detector which are electrically connected in sequence, wherein the embedded processor, the analog quantity input module and the thermal conductivity concentration detector are arranged at the field end of hydrogen isotope gas to be detected; and the upper computer is arranged at a remote end. The problems that remote operation is difficult to achieve, universality is low, the automation degree is low, operation is troublesome, and radiation risks exist in the prior art are solved.
Owner:MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS

Automatic detection and classification device for radioactive contamination parts of nuclear power station

The invention belongs to the technical field of nuclear power station radioactive decontamination, and provides an automatic detection and classification device for radioactive contamination parts of a nuclear power station. The automatic detection and classification device is characterized in that a conveying mechanism is arranged on a rack and is used for conveying the radioactive contamination parts, and a clamping mechanism is arranged on the rack and is used for clamping and moving the radioactive contamination parts; and a radiation detector is arranged on the rack and is used for carrying out radioactivity detection on the radioactive contamination parts clamped by the clamping mechanism, and a storage part is arranged on the rack and is used for storing the radioactive contamination parts which are clamped by the clamping mechanism and are qualified or unqualified after radioactivity detection. According to the automatic detection and classification device, radioactive detection can be automatically carried out on the radioactive contamination parts, the radioactive contamination parts which are detected to be unqualified are automatically classified and collected in the storage part, and the radioactive contamination parts which are detected to be qualified are conveyed to the next station by the conveying mechanism to be automatically classified and collected, so that the working efficiency is remarkably improved, and the radiation risk of workers can be reduced.
Owner:GUANGDONG NUCLEAR POWER JOINT VENTURE +3

Reaction device and method for degrading radioactive waste resin based on Fenton method

The invention belongs to the field of nuclear waste treatment and discloses a reaction device and a method for degrading a radioactive waste resin based on a Fenton method. The device comprises a mixing reaction module, a resin feeding module, an acidic catalyst adjustment module, a heating adjustment module, a hydrogen peroxide adjustment module, a reaction liquid treatment module and gas circulation module control equipment, wherein the control equipment is used for acquiring temperatures and pH values of reaction substances in an agitation tank main body in real time to regulate and controlconveying amounts of the acidic catalyst adjustment module, the heating adjustment module and the hydrogen peroxide adjustment module in real time. The method comprises the following steps: adding awaste resin, an acidic catalyst and hydrogen peroxide into the stirring reaction module according to a feeding order, regulating and controlling reaction temperatures and pH values of the components in real time, performing oxidation decomposition on waste resin particles, and performing aftertreatment on a product of the waste resin particles. By adopting the device and the method, the waste resin can be effectively degraded, pollutants can be reduced, and meanwhile, due to adoption of the highly automatic device, the risk of radioactive leakage can be reduced.
Owner:HUAZHONG UNIV OF SCI & TECH

Control rod guide cylinder hoisting device and control rod guide cylinder hoisting method

ActiveCN110803612BMove quicklySolve the problem of safe and stable graspingLoad-engaging elementsEngineeringActuator
The invention discloses a control rod guide cylinder hoisting device and a control rod guide cylinder hoisting method. The control rod guide cylinder hoisting device includes a hoisting assembly for connecting with lifting equipment, a gripper actuator for picking and placing the guide cylinder, And at least one set of connecting rod assemblies connected between the suspension assembly and the gripper actuator; the gripper actuator includes a guide rod for extending into the guide cylinder, passing through the guide rod and A moving rod that can move back and forth along the axial direction of the guide rod, an umbrella-shaped support that is connected between the guide rod and the moving rod and that opens and closes with the movement of the moving rod; the umbrella-shaped support is open state, its top is used to abut against the support surface below the guide plate in the guide cylinder; when the umbrella-type support is in the closed state, it extends along the axial direction of the guide rod and fits on the guide rod superior. The invention realizes the safe, accurate and reliable hoisting operation of the control rod guide cylinder.
Owner:LINGDONG NUCLEAR POWER +3

Simultaneous emission of multiple gamma photons for drug time consistent nuclear medicine imaging system and method

The invention discloses a multi-gamma photon simultaneously emitting drug time coincidence nuclear medicine imaging system and method, which belongs to the field of nuclear medicine imaging. The system comprises a plurality of detector probes arranged in a non-parallel manner, a time coincidence module and a computer platform. , each detector head is composed of a collimator and a gamma photon detector with time measurement function, detecting multiple gamma photons emitted by radionuclide within a short time constitutes a multi-gamma photon coincidence event; The method calculates the position of the point where the sum of the distances of the projection lines determined by each gamma photon event in the multi-gamma photon coincidence event is the shortest point, which is the position where the radionuclide decays, and accumulates a certain number of multi-gamma photon coincidence events. Events can achieve the acquisition of radionuclide distribution in organisms. The imaging system and method simplifies the reconstruction algorithm, improves the signal-to-noise ratio of the reconstructed image, reduces the demand for total counting of gamma photons, and reduces the radiation risk of patients.
Owner:TSINGHUA UNIV

Reaction device and method for degrading radioactive waste resin based on fenton method

The invention belongs to the field of nuclear waste treatment, and specifically discloses a reaction device and method for degrading radioactive waste resin based on the Fenton method. The device includes a stirring reaction module, a resin feeding module, an acidifying catalyst regulating module, a heating regulating module, a hydrogen peroxide regulating module, a reaction liquid processing module, and a reaction gas circulation module control equipment, and the control equipment is used for real-time collection of the reaction substances in the main body of the stirring tank. The temperature and pH value are used to regulate the delivery volume of the acidification catalyst regulation module, the heating regulation module and the hydrogen peroxide regulation module in real time. The method includes adding waste resin, acidification catalyst and hydrogen peroxide into the stirring reaction module according to the feeding order, and real-time regulation of the reaction temperature and pH value, and post-processing the product after the waste resin particles are oxidized and decomposed. The invention can effectively degrade the waste resin, reduce the generation of pollutants, and at the same time reduce the risk of radioactive leakage through a highly automated device.
Owner:HUAZHONG UNIV OF SCI & TECH

A method and device for determining an ideal single count rate

The invention, which belongs to the technical field of the computer, discloses a method and apparatus for determining an ideal single-lifting counting rate. The method comprises: distances between unit regions in a curved surface formed by rotation of a bar source of radioactive activity in a direction parallel to an axial direction of positron emission tomography (PET) equipment at a first distance being a distance to the axis of the PET equipment and all crystals of the PET equipment as well as angles of each unit region and each crystal are determined; and according to the distances between the unit regions and the crystals and the angles of each unit region and each crystal as well as a preset ideal single-lifting counting rate algorithm, a current ideal single-lifting counting rate of each crystal is determined. Therefore, being close to a radioactive solution by a technicist for long time can be avoided and thus the risk of radiation on the technicist can be reduced; and an accident can be prevented.
Owner:赛诺联合医疗科技(北京)有限公司

Preparation method of 3D printing combined guide plate suitable for femoral neck system

The invention relates to a preparation method of a 3D printing combined guide plate suitable for a femoral neck system.The preparation method is composed of a fracture three-dimensional CT data collection part and a guide plate design part, and the guide plate design part is composed of a central guide needle guide hole design, an anti-rotation guide needle guide hole design, a lesser trochanter positioning and fixing guide hole design and a detachable fixing base design; according to the invention, the accuracy of screw placement can be effectively improved, the safety of screw placement is improved, the operation time is shortened, and the exposure times and time of patients and medical personnel under X-rays are reduced.
Owner:张家港市第一人民医院

Citrus fruit fly irradiation non-emergence epidemic prevention processing system and treatment method

The invention discloses a citrus fruit fly irradiation non-emergence epidemic prevention treatment system and a treatment method. The system comprises a detection chamber. At least one irradiation assembly is arranged in the detection chamber. A detection table is also located in the detection chamber. The system is characterized in that a protection layer is arranged on the outer wall of the detection chamber. An irradiation part inside the irradiation assembly is arranged in an outer cover body, and the outer cover body is connected with a scattering ball. The outer cover body is connected with the detection chamber through a telescopic part. The detection chamber is in the form of an internally hollow containing cavity. A ceiling is arranged at the upper part of the detection chamber. At least one ventilation device is arranged on the ceiling. An inlet is formed in the detection chamber, and an outlet is formed in the opposite side of the inlet. A transition plate bridge is arrangedat the inlet, and the detection table is supported by at least one lifting column.
Owner:PLANT PROTECTION RES INST OF GUANGDONG ACADEMY OF AGRI SCI +1

Radioactive liquid extraction equipment, extraction method and application thereof

The present invention provides a radioactive liquid extraction device and method and use thereof, the extraction device is configured to extract a radioactive liquid from a liquid storage bottle, the extraction device comprises: a base configured to place the liquid storage bottle containing the radioactive liquid; a movable bracket configured to be movable in a direction substantially perpendicular to the base station; the puncture needle tube is supported by the movable bracket and is configured to penetrate through the rubber plug of the liquid storage bottle; the high polymer material tube is configured to enter the puncture needle tube from the end, away from the base station, of the puncture needle tube and penetrate out of the end, close to the base station, of the puncture needle tube so as to enter the liquid storage bottle to extract the radioactive liquid.
Owner:BEIJING SINOTAU INT PHARMA TECH CO LTD +1

Positioning guiding system and method of C-arm machine

The invention provides a positioning guiding system and method for a C-arm machine. The positioning guiding system comprises HoloLens glasses and a communication module, the HoloLens glasses are in communication connection with the server through the communication module; the HoloLens glasses are used for acquiring and displaying a pre-stored three-dimensional human body model from the server according to the suspension gesture; the control module is further used for projecting the three-dimensional human body model to the body of the patient according to the suspension gesture, adjusting the size of the three-dimensional human body model according to the body of the patient to enable the three-dimensional human body model to coincide with the body of the patient, and presenting the placement position of the C-arm machine for the user based on the adjusted three-dimensional human body model; wherein a plurality of to-be-scanned parts are arranged on the three-dimensional human body model, and each to-be-scanned part corresponds to the placing position of the C-arm machine. According to the invention, a user can be assisted to quickly and accurately place the C-arm machine at a proper position, the placing time is shortened, and the ray radiation risk of a patient and a doctor is reduced.
Owner:上海涞秋医疗科技有限责任公司

Automatic scanning device for welding seam of positioning plate of heat exchanger water chamber in nuclear power plant

The invention belongs to the technical field of nondestructive inspection of a nuclear power station, and particularly discloses an automatic welding seam scanning device for a water chamber locatingplate of a heat exchanger of a nuclear power station. The automatic welding seam scanning device comprises an installation rail and a scanning assembly arranged on the installation rail in a sliding manner, wherein the scanning assembly comprises a framework arranged on the installation rail in a sliding manner, one or more scanning rail segments rotatably connected with the framework and a scanning rail car provided with a welding seam inspection device; and the scanning rail segments are unfolded to form a scanning rail for the movement of the scanning rail car. The scanning rail of the device adopts a folded structure, and the scanning rail can be folded in the installation and disassembling process, thereby reducing the overall size; after entering the water chamber, the scanning railcan be unfolded to form a long rail, thereby widening the scanning range of the device; and the installation and disassembling of the device are performed outside the water chamber, so that personneldo not need to enter the water chamber, thereby reducing the irradiation risk of the personnel.
Owner:CGNPC INSPECTION TECH +3

A passive online rehydration device and method for containment filtration and discharge system

The invention provides a passive online rehydration device and method for a containment filtration and discharge system, which includes a plurality of rehydration tanks and rehydration pipelines. There is washing solution in the liquid replenishment tank; one end of the liquid replenishment pipeline is connected to several of the liquid replenishment tanks and the other end is connected to the Venturi water washing container, and the water washing solution in the liquid replenishment tank can be filled into the Venturi water washing container. Inside the container, rehydrate the venturi wash container. The invention improves the safety, reliability and convenience of liquid replenishment in the process of filtering and discharging, and ensures the safe operation of the filtering and discharging system under more severe conditions after serious accidents.
Owner:中广核工程有限公司 +3

Radiometer angular response detection method

The invention discloses a radiometer angular response detection method, which comprises the following steps of: installing a radiometer on a detection device, and performing angular response detectionon the radiometer by adopting radiation rays; the method specifically comprises the following steps: S1, respectively installing two radiation instruments in the radiation instrument accommodating spaces of a gamma measurement tool; S2, irradiating one of the radiometers with radiation rays for measurement; after measurement, rotating the dial by the motor to adjust the measurement angle, and continuously performing measurement until measurement of all angles is completed; S3, irradiating the radiation rays to another radiometer for measurement; and S4, taking down the two radiometer bodies after measurement is completed, and repeating the step S1-S3 to complete measurement of all the radiometer bodies. According to the invention, the angular response characteristic of the radiometer canbe accurately measured, and the risk that workers are radiated is reduced.
Owner:CHONGQING JIANAN INSTR

Large-capacity sample bearing device for hollow turbine blade detection

The invention discloses a large-capacity sample bearing device for hollow turbine blade detection, the device comprises a plurality of blade clamping boxes, a clamping box mounting rack and a two-dimensional moving mechanism, the plurality of blade clamping boxes are mounted on the clamping box mounting rack, the clamping box mounting rack is mounted on the two-dimensional moving mechanism, and the blade clamping boxes can clamp a plurality of blades at a time. According to the large-capacity sample bearing device for hollow turbine blade detection, a plurality of hollow turbine blades can be placed at a time, so that the blade detection efficiency is improved, operators are prevented from entering a shielding chamber for multiple times, the risk that the operators are radiated and the waste of neutron beams are reduced, the blades are clamped by adopting the blade clamping boxes, the stability of the hollow turbine blade in the detection process is guaranteed, and the turbine blade placed on the blade box placing frame is located in a neutron photography detection view field in cooperation with the two-dimensional moving mechanism.
Owner:INST OF NUCLEAR PHYSICS & CHEM CHINA ACADEMY OF

Sn-113/In-113m generator and preparation method

The invention discloses a Sn-113 / In-113m generator and a preparation method. The preparation method comprises the following steps: 1), adding bromine water to stannic chloride [113Sn] aqueous solution, and adjusting the radioactive concentration through acid aqueous solution; 2), setting a support in a lead protection tank, enabling the support to be connected with a heating piece, and enabling the heating piece to be connected with a power plug; 3), placing nano-zirconia particles into a glass separation column, adding the liquid obtained at step 1) from a liquid incoming pipe, carrying out the drip washing through sodium chloride aqueous solution, placing the glass separation column with the absorption Sn [113Sn] nano-zirconia particles in a device obtained at step 2) after drip washing, and enabling the heating piece to make contact with the external surface of the central part of the glass separation column. The method is high in efficiency of drip washing, is low in breakthrough rate, and is small in drip washing volume. The method is high in speed of drip washing, can enable a worker to shorten the operation time as much as possible, and reduces the irradiation risks.
Owner:天津汇康药业有限公司

Encapsulation method and system for nuclear industry radioactive material container

The invention relates to a method and system for packaging radioactive material containers in the nuclear industry. The method includes: a control system controls the moving mechanisms in the first sealed box and the second sealed box to package the container to be packaged for the first time; the control system acquires the second 2. The radiation information of the first sealed container detected by the detector in the sealed box, and confirm whether it meets the transfer-out standard; if not, control the movement mechanism in the N-1 sealed box and the N-th sealed box to align The container after the N-2th packaging is packaged for the N-1th time; and the radiation information of the container after the N-1th packaging detected by the detector in the N-th sealed box is obtained; and the N-1th packaging is confirmed. When the container meets the transfer-out standard, control the N-th sealed box to communicate with the safe transfer-out channel, and move the N-1th sealed container to the safe transfer-out channel for transfer out. The above method can effectively realize the automatic packaging of the radioactive material container and ensure the safety of the transported radioactive material.
Owner:HANGZHOU JINGYE INTELLIGENT TECH CO LTD
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