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

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.