134 results about "Radioactive environment" patented technology

The invention relates to a non-radioactive environment-friendly energy-accumulation luminous pervious concrete pavement which structurally comprises a soil matrix, a base layer, a reinforced pervious concrete structure layer, a luminous pervious concrete surface layer and a protection layer from bottom to top. The pavement disclosed by the invention has a good ornamental value in daytime, can absorb and storage light energy, can emit light at night to play a role in illumination and indication, has a favorable decoration property and a good energy saving effect and can be widely applied to sidewalks on two sides of courtyards, public areas, scenic spots and driving roads.

The invention discloses a quick replacement visual positioning system for a mechanical arm tool in a nuclear environment and a positioning method, and relates to the technical field of special equipment. The quick replacement visual positioning system comprises an image acquisition unit, a target feature extraction unit, a target position and pose calculation module, a mechanical arm attitude calculation module and a mechanical arm control system which are communicated and connected in sequence, and is characterized in that the target feature extraction unit is further communicated and connected with a camera calibration module, and the target position and pose calculation module is further connected with a hand-eye calibration module, thereby solving a problem of how to quickly and accurately position a tool to be clamped on a tool placement frame by a mechanical arm tail end tool clamping head during the process of tool replacement in a radioactive environment, improving the efficiency of tool replacement, realizing multiple purposes of a manipulator, reducing the cost of nuclear three-waste processing, and improving the working efficiency of nuclear three-waste processing.

The invention relates to a radiographic testing method for welding beams under the radioactive environment of a nuclear power station. The radiographic testing method is used for testing the welding seams through rays under the radioactive environment. The radiographic testing method comprises three stages of preparation, operation and after-treatment, wherein the preparation of a tag system, the assembly of a hidden bag system, the debugging of an exposure system, the manufacture of an auxiliary accessory system and the budgeting of a data computing system are involved in the preparation stage; in the operation stage, a lead rule and a tag identification label are connected near the welding seams to locate the welding seams, the hidden bag system is fixed so as to cover the welding seams, and a spherical center exposure method or a central exposure method or a double-wall single image exposure method or a double-wall double-image exposure method is adopted for imaging on a photographic film; and in the after-treatment stage, the photographic film is processed into a negative film, and the negative film is evaluated. The radiographic testing method has the advantages that the working procedures and tools in the traditional radiographic testing processed are optimized, the accuracy is high, less time is consumed, the imaging quality is high, and the transillumination risk of workers in a high radiation region is effectively reduced.

A protective garment for nuclear environments is formed of a tri-laminate 30/30/30 water resistant barrier fabric. The garment can be incinerated so as to provide a disposable, one time use coverall particularly adapted for use in nuclear/radioactive environments. The coverall provides integrated elements for water resistant (i.e., splashproof), breathable, comfortable contamination protection. It is adapted for use with various types of breathing apparatuses, included external air lines, back-mounted self-contained breathing apparatuses (SCBA), and emergency breathing bottles or apparatuses. Air tanks and bottles are covered by the garment and thus do not need to be decontaminated. The garment also includes elements for use with air sampling devices and/or dosimetry equipment that are often worn by such workers.

The invention relates to an intrinsic safety opto-acoustic spectrum gas monitoring system based on an optical acoustic sensor. The Intrinsic safety opto-acoustic spectrum gas monitoring system comprises a light source device which is connected with a photoacoustic cell device through optical fibers and an optical fiber collimator, and the incident direction of laser emitted from the light source is collinearly aligned with the axle center of the photoacoustic cell device; and phase-shifting erbium-doped grating optical fiber with the 1/4 wavelength of the optical acoustic sensor is annularly paved on the inner wall of the photoacoustic cell device, the photoacoustic cell device is communicated with a gas to be tested, and the grating optical fiber is connected with a demodulation device and a data acquisition device. The invention has the advantages of high detection sensitivity, fast response speed, and the like and can realize fast, accurate and long-term on-line monitoring of trace toxic and harmful gases or other specific gases, in particular to accurate measurement and analysis of gases under some special detection environments, such as the strong electromagnetic environment, the radioactive environment, the environment in a gas-production coal mine which is not allowed to use a power supply device on site, and the like.

The invention discloses a nuclide recognition device in a high-level radioactive environment. The device consists of a digitalized gamma energy spectrum acquisition system, a monitoring host, mobile equipment and a wireless network, wherein the digitalized gamma energy spectrum acquisition system and the mobile equipment are controlled by the monitoring host through the wireless network. The nuclide recognition device has the advantages that: in the high-level radioactive environment, full-automatic nuclide detection is realized; the potential health harm suffered by workers during manual detection in the high-level radioactive environment is avoided and the shortcoming of the manual detection is overcome; meanwhile, the problem that information acquisition is finite during conventional nuclide detection is solved.

A method and apparatus for monitoring a parameter in an irradiated environment and communicating a signal representative of the monitored parameter to a less caustic environment that employs a wireless transmitter that is powered by the irradiated environment. The power for the wireless transmitter is derived from a self-powered radiation detector disposed within the radioactive environment.

A method of monitoring a condition of a nuclear reactor pressure vessel disposed in a radioactive environment is provided. The method includes the steps of sensing a condition of the reactor pressure vessel with an instrument, transmitting a signal indicative of the condition of the reactor pressure vessel from the instrument to a powered wireless transmitting modem disposed in the radioactive environment, wirelessly transmitting a signal indicative of the condition of the reactor pressure vessel from the transmitting modem to a receiving modem in the line of sight of the transmitting modem, transmitting a signal indicative of the condition of the reactor pressure vessel from the receiving modem to a signal processing unit, and determining the condition of the reactor pressure vessel from the wirelessly transmitted signal.

The DGA n-MOSFET layout of the present invention can properly operate in a radioactive environment by blocking leakage current paths that may be created by radiation. Hence, the DGA n-MOSFET layout can be applied to design of electronic components operable in radioactive environments, such as outer space, planetary exploration, and in nuclear reactors in nuclear power plants. In addition, semiconductor design efficiency can be increased by enabling rapid modeling of electrical characteristics of a semiconductor device such as a DGA MOSFET when the channel region geometry is diversified according to design of the semiconductor device.

The invention relates to the technical field of reactor engineering, in particular to a detecting positioning device for a spherical element. The device comprises a pressure bearing housing, an innercomponent and a performing component, wherein the pressure bearing housing comprises a box body, a sphere feeding connecting pipe and two sphere discharging connecting pipes; the sphere feeding connecting pipe and the two sphere discharging connecting pipes are correspondingly arranged on the box body; the inner component is arranged in a rotor sunken hole and comprises a lined ring and a limitingring; the performing component comprises a turntable and two supporting lugs. The device can perform automatic material separating, accurate positioning and directional conveying of the spherical element; the device is compact in structure, and simple to control, and meets the requirement of running reliability and maintainability under long-term intermittent running in a high-radioactivity environment.

The invention discloses a remote replacement device for an O-shaped ring. The remote replacement device for the O-shaped ring comprises an O-shaped ring supporting mechanism and a lever mechanism used for controlling the O-shaped ring to ascend and descend. The supporting mechanism comprises a base and a supporting base, wherein the base and the supporting base are connected through a connecting rod. A center shaft is arranged between the base and the supporting base. The upper end of the center shaft penetrates through the supporting base to be connected with a rotary disk. A plurality of connecting rods are connected to the rotary disk in the circumferential direction. The sliding rods are connected with sliding shafts. The sliding shafts can slide in long straight grooves formed in the supporting base. The upper portions of the sliding shafts are connected with supporting rings. A bearing ring is arranged outside the supporting rings. The bearing ring is connected with the level mechanism. By the adoption of the remote replacement device for the O-shaped ring, the O-shaped ring can be replaced under the condition of remote operation. The remote replacement device for the O-shaped ring is particularly suitable for a radioactive environment or a toxic environment. Operators can be prevented from touching a radioactive medium or a toxic medium, the danger coefficient of an operator is greatly reduced, and the replacement safety is improved.

The invention discloses a photo-acoustic spectrum gas detecting system based on a distributed feedback optical fiber laser, belonging to the gas detection technologies. The photo-acoustic spectrum gas detecting system comprises a coherent light source, a distributed feedback optical fiber laser and the like, wherein the coherent light source is connected with a modulator through a self-supplied tail fiber, and the modulator is connected to a photoacoustic cell through a common optical fiber to form a sound signal excitation optical path; a 980 pump semiconductor laser is connected with a 980nm end of a wavelength division multiplexer through the tail fiber to form a detection optical path with a subsequent optical path. The invention is characterized in that the distributed feedback optical fiber laser is used as a sensor for probing sound and fixed in the photoacoustic cell, and one end thereof is connected to a common end of the wavelength division multiplexer through the common optical fiber; an 1550nm end of the wavelength division multiplexer is connected with an isolator; an output end of the isolator is connected with a wavelength demodulation system of the far end through the common optical fiber. The photo-acoustic spectrum gas detecting system can be normally used in the environment of strong electromagnet and radioactivity, can be used for detecting a special gas environment, and is convenient for forming a network by multiplexing a plurality of the systems so as to realize remote monitoring of multiple points.

The invention belongs to the technical field of nuclear power station equipment or part nondestructive test and use and relates to a vector control underwater planktonic video inspection device. The device comprises a shore control system, an umbilical cable folding and unfolding device, an umbilical cable, a submersible main body and an underwater control system. The underwater control system is installed in the submersible main body. The submersible main body is connected to the shore control system through the umbilical cable. The umbilical cable folding and unfolding device realizes folding and unfolding of the umbilical cable. The submersible main body comprises a floating block, a power platform and an underwater high definition shooting assembly. The elliptical floating block is installed at the upper part of the power platform. The underwater high definition camera assembly is installed at the lower part of the power platform. The device is suitable for an inaccessible underwater radioactive environment, is suitable for indirect visual detection and routing inspection of pressurized water reactor nuclear power station primary circuit main parts, nuclear fuel assemblies and a pool cladding plate in normal material change of a nuclear power station and satisfies radiation environment on-site observation real demands after an accident.

A water filling system for a reactor water level gauge is provided for filling a reactor water level gauge instrumentation pipe in a reactor building with water and filling the reactor water level gauge with water even in an unexpected abnormal event where the reactor building is brought into a highly radioactive environment. The water filling system for a reactor water level gauge includes a water filling instrumentation pipe guided from the reactor water level gauge instrumentation pipe in the reactor building to an outside of the reactor building and filling the reactor water level gauge instrumentation pipe in the reactor building with water even in an unexpected abnormal event of a nuclear power plant.

The invention provides a radioactive environment large-scale shield main pump integral dismantling device and dismantling process and belongs to the technical field of nuclear power station large-scale shield main pump maintenance. The radioactive environment large-scale shield main pump integral dismantling device comprises a main bolt pneumatic disassembling and assembling tool, an upper C-typering internal residual liquid draining tool, an upper C-type ring cutting tool, a pump case shielding protective tool and an impeller shielding and rotor locking tool. The radioactive environment large-scale shield main pump integral dismantling device is easy to operate and capable of safely and efficiently completing dismantling of a large-scale shield main pump.

The invention relates to an underwater operation device used for disassembling a reactor core former bolt and is suitable for the underwater disassembling operation of the reactor core former bolt in a high-radioactivity environment formed after radiation. The underwater operation device comprises a locating mechanism, a transmission mechanism and a driving mechanism, wherein the locating mechanism comprises a suspending frame, lifting rods and a working platform, and the lifting rods are connected between the suspending frame and the working platform; the transmission mechanism and the driving mechanism are mounted on the working platform, and the front end surface of the working platform is close to the outer surface curvature of an operated object; the transmission mechanism comprises a sleeve head, a transmission box and a driving shaft, the transmission box is connected with the driving shaft, one end of the sleeve head is connected with the output end of the transmission box, the other end of the sleeve head is a sleeve, and the transmission box changes the direction and speed of a torque transmitted by the driving shaft and transmits the torque to the sleeve head; and the driving mechanism is connected with the driving shaft. The sleeve head of the device can be closely matched with the head of the former bolt and also has a reasonable space. The sleeve head not only is strong enough to support the weight of the bolt but also helps monitoring and controlling the head sleeving-in depth of the former bolt during operation.

The invention belongs to the determination technology of elements in a radioactive environment, and specifically relates to a graphite crystal pre-diffraction energy dispersive X-ray fluorescence analysis system, which consists of an X-ray tube excitation system, a graphite crystal diffraction optical path, a Si(Li) detector multi-channel system, and a computer. Spectrum processing system, in which the X-ray tube excitation system is composed of X-ray tubes and corresponding circuits and shielding bodies; the graphite crystal diffraction optical path includes optical filters, sample boxes and graphite diffractometers, and graphite diffractometers are cylindrical graphite bodies. Place the shielding body, the energy dispersive X-ray fluorescence analysis system uses internal standard or scattering internal standard to correct the measured intensity; the X-ray tube excitation system uses a low-power X-ray generator of 150-350W; the shielding body in the graphite diffractometer is cylindrical . The system has a short distance from the focal spot to the sample and a compact structure; the shielding body in the graphite diffractometer has a simple structure, lower detection limits, and less sampling volume.

The invention discloses an electric control circuit and electric control method for an electrically operated valve. The electric control circuit comprises a valve opening travel mixed reverse power transmission circuit, a valve opening torque mixed reverse power transmission circuit, a valve closing travel mixed reverse power transmission circuit and a valve closing torque mixed reverse power transmission circuit, wherein the valve opening torque mixed reverse power transmission circuit is the is a standby circuit of the valve opening travel mixed reverse power transmission circuit and the valve closing torque mixed reverse power transmission circuit is a standby circuit of the valve closing travel mixed reverse power transmission circuit. Through adoption of the electric control circuit and the electric control method, the operation reliability of the electrically operated valve is increased greatly and the maintenance cost and frequency of the electrically operated valve used in a radioactive environment can be reduced.

The invention discloses a radioactive energy spectrum analysis system based on a beam combiner flickering optical fiber. The radioactive energy spectrum analysis system comprises a beam combiner flickering optical fiber, a multi-mode optical fiber, a photoelectric converter, a signal processing module and an energy spectrum analysis module; the beam combiner flickering optical fiber is obtained through tapering and coupling multiple flickering optical fibers to form a sensing probe measuring radioactive environment physical parameters; one end after tapered coupling is fused to a common multi-mode optical fiber, and one end of the multi-mode optical fiber is connected to a photoelectric converter; the probe portion of the beam combiner flickering optical fiber is placed in a radioactive environment to generate scintillation photons; the scintillation photon is inputted into the photoelectric converter through the multi-mode optical fiber to obtain a corresponding electronic pulse signal, and collection analysis is performed on the electronic pulse signal through a rear end system to obtain a radioactive performance spectrum of the radioactive environment. The probe portion of the radioactive energy spectrum analysis system is skillful; a single detector has a wide measurement range; the electronic portion of the detector can be far away from the radioactive field and has a better electromagnetic stability; after beam combination of multiple flickering optical fibers, an output quantity of the photons can be effectively improved and sensitivity of the system is improved as well; and besides, radioactive energy spectrum analysis system measures the energy spectrum of the radioactive performance and can better analyze the composition of the radioactive source.

The invention relates to a preparation method of long-chain nylon ultrafine powder. The long-chain nylon ultrafine powder is prepared by carrying out radiation to the long-chain nylon resin by a ray technology and then adopting a crushing technique. The preparation method comprises the following steps of: using radioactive ray to carry out radiation to the long-chain nylon resin in a radioactive environment; mixing radiated long-chain nylon resin and an auxiliary agent, and using a double-screw extruder for extruding and modifying; putting the modified materials of the double-screw extruder into an abrasive disk grinder for coarse grinding; using an air flow grinder to carry out air flow grinding on the materials by coarse grinding under normal temperature; adjusting a size grading device of the air flow grinder to obtain the long-chain nylon ultrafine powder; and the long-chain nylon ultrafine powder prepared by applying the method has even size distribution, low energy consumption for the whole grinding process and high production efficiency.

The invention discloses a disassembling device and a disassembling process for a large-sized shielding main pump in a radioactive environment, and belongs to the technical field of nuclear power station large-sized shielding main pump maintenance. The disassembling device comprises an impeller nut locking pin dismounting assembly, a C-shaped ring cutting assembly and a lower radial bearing dismounting and rotor core-pulling assembly, and the impeller nut locking pin dismounting assembly comprises an upper plate, a lower plate, a connecting screw, a double-end lead screw, a fixing nut and an adjusting nut; the C-shaped ring cutting assembly comprises a wall-mounted assembly and a cutting assembly; the wall-mounted assembly comprises a pressing plate and a wall-mounted main body; the lower radial bearing dismounting and rotor core-pulling assembly comprises a foundation plate, a foundation plate support used for connecting the foundation plate and a pump body, a double-end lead screw used for connecting the foundation plate and a lower radial bearing, a nut connected to the double-end lead screw and a lifting lug arranged on the foundation plate, a rotor supporting tool and a cushionblock which are used for connecting the foundation plate and a pump shaft, and a main bolt used for connecting the foundation plate and the pump body. The disassembling method is easy to operate, anddisassembling of the large-sized shielding main pump can be completed safely and efficiently.

The present invention relates to a crane used in a highly radioactive environment. The crane comprises a crossbeam, and traveling wheels disposed under two ends of the crossbeam to drive the crossbeam to travel. A moving trolley capable of reciprocating motion on the crossbeam is disposed on the crossbeam. A direction of motion of the crossbeam is perpendicular to a direction of motion of the moving trolley. The crane further comprises a first driving mechanism, a second driving mechanism having the same structure as the first driving mechanism, and a transmission mechanism that transfers the driving force of the first driving mechanism and the second driving mechanism to the moving trolley. The first driving mechanism comprises a driving motor, a front-end sprocket wheel and a tail-end sprocket wheel that are not disposed on the crossbeam, and a transmission sprocket wheel case that is disposed on the crossbeam. The front-end sprocket wheel is connected to a power output end of the driving motor. The front-end sprocket wheel, the sprocket wheel in the transmission sprocket wheel case, and the tail-end sprocket wheel are in transmission connection with one another by means of a chain. According to the present invention, the driving mechanisms in the crane can be prevented from highly radioactive pollution, thereby prolonging the service life of the crane and also facilitating later maintenance.

The invention discloses a non-contact leakage detecting method of a double-layered packing sealing structure and a system. A packing support (6) is arranged between double packing layers (1 and 4), the double packing layers (1 and 4) are separated by the packing support (6), so that a closed cavity is formed, an air inlet tube (3) and an air outlet tube (5) are respectively arranged on the closed cavity, an air source supplies air for the closed cavity via the air inlet tube (3), the closed cavity becomes a closed air cavity with certain pressure, a pressure transmitter arranged on the outside of a heat chamber measures the pressure of the closed air cavity, and the dynamic sealing effect of the sealing device in a radioactivity environment can be monitored in real time.

The invention discloses a preparation method of a radioactive isotope tracer agent. The preparation method comprises the following steps of: step 1, adding a radioactive iodine salt solution and an oxidant into a certain reaction container, and heating to generate iodine steam; step 2, conveying the iodine steam to the bottom of an adsorption tower filled with a porous adsorption material, and efficiently adsorbing the iodine steam by the porous adsorption material; step 3, after adsorption, circulating a very small amount of the iodine steam remained at the upper part of the adsorption tower into the reaction container; and step 4, after circulating adsorption, uniformly adsorbing all radioactive iodine-131 isotopes; and step 5, carrying out organic coating on the porous adsorption material. By adopting the method disclosed by the invention, a small amount of the radioactive iodine salt solution is added into the oxidant to generate an iodine simple substance; iodine is sublimated at 45 DEG C and the generated high-humidity iodine steam is sucked into a high-pore adsorbent with an impregnant; the whole preparation technology consumes 1 to 2h and the preparation efficiency is greatly improved; the exposure time of operators under a radioactive environment is greatly shortened.