24results about How to "Reduce exposure dose" patented technology

The invention discloses an in-reactor fuel irradiation test loop based on the working condition of a pressurized water reactor. The in-reactor fuel irradiation test loop comprises a main circulation system, a purification system, a fission substance release monitoring system, a water supplementing system, an emergency cooling system, a cooling water system, an in-reactor device pressure failure online monitoring system, a reactor shutdown protection system, a thermal parameter measurement system, a power supply system and an air ventilation and exhaust system. According to the loop, a pressurized water reactor working condition environment is realized, and various technical indexes such as temperature, pressure, flow velocity and water quality required by fuel test are ensured to be reached; the safety level of each system is reasonably configured, so that the requirements of laws and regulations are met, and the safety performance of the loop is improved; by reasonably arranging a multi-stage cooling water system, an air exhaust system and the like, the radioactive activity of an exhaust flow is reduced, the environmental safety is ensured, the release of radioactive aerosol in a process is eliminated, the exposure dose of workers is reduced, the safety of the workers is ensured, the safety risk of devices in the reactor to the reactor under the working condition of a fracture accident is eliminated, and the reliability of the system is improved.

The utility model discloses a cleaning device and a pressure vessel top cover C-ring groove cleaning device thereof, the pressure vessel top cover C-ring groove cleaning device comprises a cleaning fluid collecting box, a cleaning fluid collecting box, a cleaning fluid collecting box, a cleaning fluid collecting box cover, a cleaning fluid collecting box cover, a cleaning fluid collecting box cover, a cleaning fluid collecting box cover and a cleaning fluid collecting box cover, and the cleaning fluid collecting box is internally provided with a guide rail and a tooth row; the tooth row extends in the length direction of the cleaning liquid collecting box, and the tooth row and the guide rail are arranged at intervals. The cleaning assembly comprises a mounting frame, a cavity for storing cleaning liquid is formed in the mounting frame, and a plurality of nozzles are arranged on the cavity; the mounting frame is mounted on the guide rail, a first driving part is arranged on the mounting frame, a gear is arranged at the driving end of the first driving part, and the gear is meshed with the tooth row. By applying the cleaning equipment and the pressure vessel top cover C ring groove cleaning device thereof, the working intensity and the exposure dose of field operators can be reduced. And the cleaning liquid collecting box can collect used cleaning liquid, so that splashing of the cleaning liquid in the cleaning process can be prevented, and recycling of the cleaning liquid can be achieved.

The invention relates to the technical field of medical auxiliary instruments, and provides a tumor radiotherapy protection device which comprises a multi-shaft mechanical arm and a rotating frame, a carrying arm is installed at the execution end of the multi-shaft mechanical arm, the rotating frame is rotationally connected to the carrying arm, a hollow rotating shaft is rotationally installed on the rotating frame, a motor is installed on the carrying arm, and the hollow rotating shaft and the rotating frame are both driven by the motor. The radial variable-pressure frame is connected to the rotary frame in a sliding mode, a radial variable-pressure mechanism for driving the radial variable-pressure frame to circularly vibrate in a variable-amplitude mode is arranged on the rotary frame, a massage pressing frame is connected to the radial variable-pressure frame in a sliding mode, a torque driven shaft and a pressing shaft are rotationally connected to the massage pressing frame, a radial transmission gap is formed between the hollow rotary shaft and the torque driven shaft, and the hollow rotary shaft and the torque driven shaft are in transmission connection; a torsion spring is installed between the torque driven shaft and the pressing shaft. According to the invention, the limitation that the existing radiotherapy protection device only has a single ray shielding function is broken through, and the integration of protection, nursing and adjuvant therapy functions is realized.

The invention belongs to the technical field of nuclear facility decommissioning, and particularly discloses an underwater laser cleaning and cutting combined machining device and a using method, cleaning and cutting are achieved through refraction and reflection of cleaning laser by scanning an X / Y-axis galvanometer set and a dichroscope and transmission of cutting laser by the dichroscope, and coaxial focusing is achieved through a common field lens; a gas-liquid coaxial composite nozzle is arranged at the bottom, and center auxiliary airflow and annular high-pressure laminar flow water can be independently regulated and controlled; millisecond-level process switching is matched, and instant cutting is carried out after cleaning is completed at the same underwater station. Aiming at the problems of low efficiency, high safety risk, more secondary pollution, poor cutting quality and the like in the decontamination and disintegration process of the high-level metal part of the nuclear power station, the invention does not generate radioactive waste liquid, effectively avoids secondary pollution, remarkably improves the cutting quality, the operation safety and the system reliability, and is suitable for green and efficient retirement operation in a high-radioactivity environment.

The present invention relates to an underwater stripping device for radioactive metal channels, belonging to the field of nuclear, biological and chemical safety protection technology. The device comprises an underwater stripping device body, a control cabinet, a compressed air system and a special water tank. The special water tank is sealed on four sides and the bottom, and is open at the top. When in use, it is placed in a spent fuel storage pool. The underwater stripping device body comprises a rotating lifting assembly and a cutting unit. The rotating lifting assembly is arranged on the top of the special water tank. The rotating lifting assembly comprises a fixed operating frame, a rotating unit and a clamping lifting unit. The fixed operating frame provides support for the rotating unit and the clamping lifting unit. The rotating unit is used to control the rotation of the process pipe. The lower end of the clamping lifting unit is connected to the cutting unit. The cutting unit is arranged inside the special water tank. The lifting and lowering of the cutting unit is controlled by the clamping lifting unit, so as to realize cutting of process pipes of different lengths. The device provided by the present invention can solve the problem of spent fuel leakage in the underwater thermal cutting process.

The invention discloses a nuclear power station operation radiation risk monitoring system and method, and relates to the technical field of nuclear power station radiation protection, and the system comprises a server which is used for automatically loading nuclear power station operation data of which the work permission takes effect, and carrying out the screening according to the radiation risk level and the time priority, and obtaining the nuclear power station operation which needs to be emphatically supervised; the supervision device is electrically connected with the server, is installed on a nuclear power station operation site needing to be intensively supervised, and is used for collecting site supervision information of nuclear power station operation needing to be intensively supervised and uploading the collected site supervision information to the server; and the server is also used for judging the collected field supervision information according to the protection measures corresponding to the field supervision information to obtain corresponding rectification requirements. The nuclear power station field operation radiation safety risk can be supervised in real time, field radiation protection personnel are reminded to pay attention and prepare, key radiation work supervision links cannot be omitted, and the radiation safety supervision work efficiency is effectively improved.

This invention discloses a dual-wavelength accelerated curing photopolymerization 3D printing method and apparatus, relating to the field of additive manufacturing technology. It employs a dual-wavelength responsive photopolymerization ink, which comprises a polymerizable monomer, a photoinitiator sensitive to a first wavelength, a photosensitizer sensitive to a second wavelength, a singlet oxygen quencher, and a solvent. The photosensitizer is excited under second-wavelength light irradiation, converting ambient oxygen into singlet oxygen. The singlet oxygen quencher consumes singlet oxygen to reduce local oxygen concentration. The first and second wavelengths are spectrally orthogonal. This dual-wavelength accelerated curing photopolymerization 3D printing method and apparatus eliminates oxygen inhibition in localized low-oxygen environments, reduces exposure dose, and increases printing speed.

The present invention provides a photoresist composition, a preparation method and an application thereof, and a method for forming a photoresist pattern, and specifically relates to the field of photoresist technology. The photoresist composition comprises a poly(p-hydroxystyrene) homopolymer and a photodeactivator, and the mass ratio of the two is 100-600:2-50. The weight average molecular weight of the poly(p-hydroxystyrene) homopolymer is 1000-20000. The photoresist composition has strong photosensitivity, and after exposure by a 248nm deep ultraviolet lithography light source, the exposure dose can be reduced to 10mJ / cm at a film thickness of 500nm. 2 The poly(p-hydroxystyrene) homopolymer has no protective group and can participate in cross-linking, so it has a higher carbon atom content, significantly improves dry etching resistance, improves etching ratio, greatly improves customer production efficiency, and reduces production costs.

The present invention belongs to the technical field of internal contamination of valve chambers, and specifically relates to an automatic device and method for removing radioactive contamination from valve chambers, including a movable trolley, a filter, a fluid transmission pump, a mechanical arm, and a connecting pipe. The device and method can replace manual work to automatically remove radioactive substances deposited inside the valve chamber, residual radioactive liquid, and metal particles generated by grinding, thereby reducing the risk of radiation exposure and contamination of personnel, improving the decontamination effect, reducing the radiation source items of the unit, reducing the amount of radioactive waste generated, and improving on-site work efficiency.

The invention relates to the technical field of irradiation test loop equipment, and provides an ion exchange column suitable for an irradiation test loop, the ion exchange column comprises an outer cylinder and an inner cylinder used for placing the ion exchange column, the lower end of the outer cylinder is provided with a water outlet pipe communicated with the inner cylinder, the upper end of the outer cylinder is connected with an end flange, and the inner spherical surface of the end flange is cooperatively connected with a sealing plug. The sealing plug is provided with a water inlet pipe communicated with the inner cylinder, the end flange is in bolted connection with a gland flange used for pressing the sealing plug and fixing the sealing plug in the end flange, the outer cylinder and the inner cylinder are arranged in a sleeve structure, and the gland flange and the end flange are connected through bolts so as to abut against the sealing plug and the end flange, so that spherical surface sealing fit is achieved; the requirement for assembly precision is lowered, the flexibility and quickness of assembly are improved, and therefore the exposure dose of operators is reduced.

The invention provides a nuclear-grade sealing joint suitable for quick release requirements, which comprises a joint body, and the joint body comprises a connecting part and a thread part which are connected in sequence; one end of the threaded part is connected with the connecting part, and the other end of the threaded part is a first wedge-shaped surface; the end plug is provided with an internal thread, a sealing part is arranged in the end plug, and the end face, close to one end of the thread, of the sealing part is a second wedge-shaped face; the connecting pipe connecting piece comprises a pipe cap, a first clamping sleeve joint and a second clamping sleeve joint; the pipe cap is provided with an internal thread, the first clamping sleeve connector and the second clamping sleeve connector are arranged in the pipe cap, the first clamping sleeve connector abuts against the pipe cap, the second clamping sleeve connector abuts against the first clamping sleeve connector, and the end face of the end, close to the thread, of the second clamping sleeve connector is a third wedge-shaped face; the joint body is connected with the end plug to plug a pipeline; the connector body is connected with the connecting pipe connecting piece to be connected with a pipeline. The device is convenient to disassemble and assemble and not prone to leakage.

The invention discloses a tube plate crawling robot arranged on a tube plate of a steam generator, which comprises a first crawling arm, a second crawling arm, a first connecting piece, a second connecting piece and a probe guide device, and pneumatic locking devices are respectively arranged on the first crawling arm and the second crawling arm; the tube plate crawling robot can crawl on a tube plate through the crawling arms and the pneumatic locking devices matched with the crawling arms, the probe guiding devices and the crawling arms are connected through the rotatable connecting pieces, the two crawling arms are connected through the rotatable connecting pieces, and therefore the tube plate crawling robot has multiple degrees of freedom and can crawl on the tube plate after installation is completed, and the tube plate crawling robot is convenient to use. The heat transfer tubes on the whole tube plate can be detected through one-time installation, secondary installation by maintainers is not needed, and the exposure dose of the maintainers is reduced; meanwhile, after the robot moves in place, the covered heat transfer tube area is large, the positioning efficiency is high, and the detection efficiency is improved.

The invention discloses an isotope irradiation target long-distance manual self-aligning cutting clamp which comprises a supporting seat, a movable sliding table, a bubble type gradienter, two clamping blocks, an adjusting screw, a fixing screw, a locking screw rod and the like, the movable sliding table is of a delta-like structural form, the structure is compact, the size is small, and the weight is light; the transfer in the limited space of the hot chamber is facilitated; by rotating the adjusting screw and the locking screw rod, the levelness of the clamp can be adjusted, and the clamp can be clamped and loosened; the center position of the clamp is adjusted by rotating the fixing screw rod; the structure facilitates operation of the master-slave mechanical arm, the whole operation process is simple, and high practicability is achieved.

The invention discloses a medium- and low-level organic waste liquid pyrolysis process, which relates to the technical field of radioactive waste treatment, including S1: separating medium- and low-level organic waste liquid from oil and water to obtain radioactive medium- and low-level TBP / OK organic waste liquid and low-level waste liquid; S2: filtering the TBP / OK organic waste liquid, and rectifying it in a short-range molecular distillation device to obtain concentrated TBP organic waste liquid and light component kerosene; S3: stirring the lime milk preparation liquid and the concentrated TBP organic waste liquid to prepare a suspension; S4: transporting the suspension to a pyrolysis furnace to be decomposed into pyrolysis gas and pyrolysis ash; S5: the pyrolysis gas enters a combustion furnace; the pyrolysis ash is cemented to form a cement solidified body; S6: the flue gas discharged from the combustion furnace is purified and discharged to the atmosphere. The invention tests the inorganic treatment of low-level organic waste liquid through the processes of oil-water separation, short-range molecular distillation, pyrolysis in a pyrolysis furnace, combustion in a combustion furnace, cement solidification, etc., and the generated pyrolysis ash forms a stable solidified body for disposal, thereby realizing the minimization and final disposal of waste.

The invention relates to a radiopharmaceutical passive skin anaphylaxis test method, which comprises the following steps: animal grouping: dividing test animals into a positive control group, a negative control group and a drug group, and marking; preparing the medicine: respectively mixing the negative reference substance, the positive reference substance and the radiopharmaceutical with the adjuvant to obtain each group of mixed emulsion; preparing antibody serum: taking a plurality of test animals from each group, performing drug injection, sampling blood on the fourteenth day after the last sensitization, separating the serum, and diluting to obtain antibody serum with medium, high and low concentrations; passive sensitization: taking a plurality of normal test animals from each group, injecting corresponding antibody serum into each group, and carrying out passive sensitization; and excitation: after sensitization is carried out for 48 hours, injecting each group of solutions containing dye liquor into each group of test animals for excitation, measuring the size of blue spots, and determining that the test animals with the diameter greater than 5 mm are positive. The method can be used for safely, effectively, simply and conveniently carrying out preclinical evaluation research on the sensitization of various radiopharmaceuticals.

The invention provides a nuclear power plant reactor refueling pool radiation measurement and radioactive decontamination device which is installed on a refueling crane and comprises a guide rail arranged on the refueling crane, and a radiation measurement module, a radioactive decontamination module and a compressed air purging module which are installed on the guide rail in a sliding mode. The invention further provides a radiation measurement and radioactive decontamination method for the refueling pool of the reactor of the nuclear power station. The device is compact in structure, has scalability, and can be flexibly installed according to actual working conditions on site. Meanwhile, the refueling crane is used as a carrier, the device moves back and forth through the moving track of the refueling crane, and full-coverage radiation level measurement and radioactive decontamination on the refueling pool are ensured in the mode that the telescopic driving arm and the device guide rail are used for moving up and down and left and right.

An automatic feeding and green body transferring device of a uranium plutonium oxide multi-punch press comprises a feeding part and an automatic green body transferring part. The feeding part comprises a material tank lifting and overturning device and a pressing and feeding device, the right end of the horizontal vibration device is connected with a discharging pipeline, a rotary mixing and distributing device is arranged in the middle of the discharging pipeline, and the lower end of the discharging pipeline is connected with a middle mold through a hopper; the automatic green body transferring part comprises a shifting piece. According to the automatic feeding method for the uranium plutonium oxide multi-punch press, materials are conveyed to the pressing and feeding device through the material tank lifting and overturning device, enter the horizontal vibration device through the discharging ball valve, then enter the rotary mixing device through the discharging pipeline made of a rubber hose material, and finally enter the middle die to be pressed. According to the uranium plutonium oxide multi-punch press green body transferring method, a material hoof pushes a green body to a transferring platform, and the green body can be transferred to a conveying belt through a shifting piece; in the conveying process of the conveying belt, the direction of the green bodies is adjusted to be parallel through the stainless steel guide grooves.

This utility model relates to the technical field of nuclear medicine protective equipment, and in particular to an integrated protective kit for a nuclear medicine radiopharmaceutical injector, which simultaneously achieves effective radiation shielding and prevents contamination caused by exposed needles; it includes a first protective tube and a second protective tube; the first protective tube is sleeved on the outside of the injector's volume tube, and a viewing window is provided on the first protective tube along the length of the injector; the first protective tube also has a first protective cover for closing the viewing window; the second protective tube is sleeved on the outside of the injector needle portion, and the second protective tube is slidably connected to the first protective tube, and a second protective cover is provided at the front end of the second protective tube; the second protective tube also has an opening and closing unit for driving the opening and closing of the second protective cover, and the opening and closing unit is connected to the first protective tube through a transmission mechanism.

The invention discloses a polyimide positive photoresist based on an acid deactivation mechanism, which comprises the following components in percentage by weight: 10-50% of polyamic acid resin, 10-50% of acid catalyst, 10-50% of photoinduced deactivator and 10-50% of solvent. 0.5%-10% of an acidic catalyst; 0.5%-10% of a photoinduced deactivating agent; and 50%-90% of a solvent. The invention provides a polyimide positive photoresist based on an acid deactivation mechanism, the photoresist belongs to a chemical amplification photoresist, the photosensitivity is strong, the exposure dose can be reduced to 50-70mj / cm < 2 > by taking the photoresist thickness of 3 microns as an example, meanwhile, the imidization photoresist thickness loss is smaller, the production efficiency can be greatly improved, and the production cost can be reduced.

According to the torque overload protection hand wheel and the valve, the driving disc of the driving unit and the driven disc of the driven unit are coaxially arranged in the mounting cavity and make rolling contact, and the driven disc and the driving disc are elastically connected through the disc spring assembly of the disc spring unit; a ball-disc spring type structure is additionally arranged on the hand wheel operation ring, so that overload protection of the hand wheel in the operation process is achieved. When the operation torque is too large, the torque protection function is triggered, and the hand wheel idles. Therefore, the valve with the torque overload protection hand wheel fundamentally eliminates the defect of valve clack crushing caused by large operating force of the hand wheel, reduces the failure rate of the valve, improves the reliability of the diaphragm valve, prolongs the service life of the diaphragm valve, and reduces the maintenance cost of the diaphragm valve. And for a radioactive medium valve, the exposure dose of maintenance personnel is reduced, radioactive waste generated due to damage of the valve clack is reduced, and the solid waste treatment cost is reduced.

The invention belongs to the technical field of nuclear power, and particularly relates to a radioactive waste gas adsorption bed transfer device. According to the invention, the box body is provided with a gas replacement system, a differential pressure gauge and radioactive gas monitoring equipment; the differential pressure gauge is used for collecting differential pressure data of air pressure in the box body and external air pressure, and the radioactive gas monitoring equipment is used for collecting radioactive substance concentration data in the box body; the gas replacement system is used for keeping the air pressure in the box body negative pressure; the gas replacement system is also used for purifying gas in the inner space of the box body; the control system is connected with the radioactive gas monitoring equipment and the gas replacement system, and the control system can obtain radioactive substance concentration data from the radioactive gas monitoring equipment and control the gas replacement system to work. The device can ensure that the adsorption bed is simple and convenient to operate, safe and reliable in the transfer process, prevents airborne radioactivity from leaking, reduces the exposure dose of personnel in the transfer process, and realizes convenience, safety and environmental friendliness of the whole transfer process.

The application belongs to the technical field of nuclear power equipment, and particularly relates to a sealing ring replacement device, which comprises a mounting frame, a fixing mechanism, a lifting mechanism, a rotating mechanism, a stop ring dismounting mechanism, a screw dismounting mechanism, a hoisting mechanism and a camera mechanism, the fixing mechanism is connected to the mounting frame and is used for fixed connection with a pump shell of a reactor coolant pump; the lifting mechanism is used for driving the rotating mechanism to lift, the rotating mechanism is used for driving the stop ring dismounting mechanism and the screw dismounting mechanism to rotate, the stop ring dismounting mechanism and the screw dismounting mechanism are respectively used for dismounting a stop ring and a screw; the hoisting mechanism is used for connection with a hoisting hole of the sealing ring; and the camera mechanism is used for acquiring graphic information of the sealing ring, so as to acquire positioning information of the sealing ring; the mechanical and graphic positioning mode is adopted, mechanical dismounting of the sealing ring is realized, and the dismounting efficiency and the dismounting quality of the sealing ring are improved.

The application provides a synchronous hoisting mechanism of a special machine for repairing a sealing weld, which comprises a plurality of clamping modules for being fixed on a scaffold platform, a hoisting frame and a synchronous hoisting module installed on the hoisting frame, the scaffold platform is arranged above a control rod drive mechanism to be repaired, the clamping module comprises a supporting leg fixing seat, the hoisting frame comprises a plurality of supporting legs and a supporting beam, the number of the supporting legs is the same as that of the supporting leg fixing seats, the lower ends of all the supporting legs are connected to all the supporting leg fixing seats one by one, the upper ends of the supporting legs are connected to the end portions of the supporting beam, the synchronous hoisting module comprises a fixing disc installed on the supporting beam, a plurality of groups of fixed pulley sets installed on the fixing disc and a plurality of groups of movable pulley sets connected to all the fixed pulley sets through pull ropes, and a lifting hook for being connected to a lifting opening of the special machine for repairing a sealing weld is installed on each group of the movable pulley sets. The synchronous hoisting mechanism can realize stable hoisting of the special machine.

The utility model discloses a blue oil test device for a lifting type check valve. The blue oil test device comprises a bottom plate, a guide sleeve, a lifting rod and an anti-rebound assembly, according to the lifting type check valve blue oil test device, the blue oil test can be carried out only by installing the valve clack on the lifting rod, assembling is easy and convenient, time and labor are saved in the blue oil test, the lifting rod is arranged to fully simulate the phenomenon that the check valve is seated through the dead weight of the valve clack, the blue oil test of the lifting type check valve is standardized and accurate, and the working efficiency is improved. Accuracy and reliability of blue oil test results are effectively guaranteed, and maintenance quality of equipment is improved. Meanwhile, an anti-rebound assembly is further arranged and used for preventing a valve clack of the check valve from rebounding after colliding with a valve seat of the check valve, the safety in the blue oil test process is guaranteed, the damage probability of the device is reduced, and if the device is located in a high-dose area, the irradiation dose of workers can be reduced.