55 results about "Nuclear environment" patented technology

The invention belongs to robot equipment used for a nuclear power plant, and particularly relates to a multifunctional actuator for nuclear power plant operation and a control method thereof. An actuating mechanism consists of a base, a three-joint five-degree of freedom mechanical arm, a square claw plate and four switchable mechanical hands arranged on the claw plate; and a plurality of cameras and sensors are arranged on the actuating mechanism; and with the adoption of the sensors and a control system, switching, locking and positioning operations of the four mechanical hands and obstacle avoidance and action planning of the mechanical arm can be realized. The actuator can realize integral operation of various high-risk tasks such as search, pollution discharge, recycling, and equipment maintenance of objects under nuclear radiation environment, thereby realizing intelligent autonomous operation under the nuclear environment.

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 discloses a visual attention mechanism-based method for detecting a target in a nuclear environment. The method includes: extracting brightness, color, direction features collected by an ordinary camera, and so as to obtain three feature saliency images; performing weighing fusion on the abovementioned saliency images to obtain a weighting saliency image; obtaining regions of interest according to the weighing saliency image and performing feature extraction on the region of interests; extracting features of a gamma camera mixed graph; and using an SIFT method to fuse the regions of interest with the mixed graph, and detecting the position of the target. The visual attention mechanism-based method for detecting the target in the nuclear environment uses a bottom-up data drive attention model to extract the plurality of regions of interests, and greatly reduces the calculated amount of a later matching process; then combines the plurality of regions of interest with the up-down task drive attention model to establish a bidirectional visual attention model, detection precision and processing efficiency of target areas in the images can be greatly improved, and a matching process eliminates interference of unrelated regions in a scene, thereby enabling extracted operation target to have better robustness and accuracy.

A method and apparatus for determining the attitude of a satellite using crosslink information is disclosed. The method and apparatus integrates data from the crosslinks with data available from other sources including, for example, star sensors, inertial sensors, and earth limb sensors to derive an accurate estimate of the satellite attitude, even in harsh nuclear environments.

The invention discloses a method for non-uniform I/O access of virtual machine resource migration in a virtual multi-nuclear environment. The method comprises the steps of acquiring a thread memory distribution matrix of each virtual CPU thread through VMM and host machine memory access detection, and recording the matrixes in a monitoring module; acquiring an access delay matrix of each node to which each thread has access through access delay data of each memory node of a host machine, and recording the access delay matrixes in the monitoring module; marking the most loaded thread on a CPU as a migration required state when the load of a certain node is higher than a certain threshold value; obtaining a target migration node by means of a formula and conducting migration; feeding back to a management module, canceling thread marking and continuing monitoring after migration ends. The method solves the problem of scheduling of non-uniform I/O access of virtual resources in a virtual multi-nuclear environment, and the utilization rate of physical bandwidth in a high-performance network is improved.

The invention, which relates to the field of the spatial location and intensity information estimation of radioactive sources, provides a radioactive source positioning and intensity estimation methodin a mobile robot's nuclear environment, thereby solving problems that the mobile robot not only can not searching for the source based on the gradient information but also locate the radioactive source based on a regression algorithm. According to the invention, the involved algorithm is based on the particle filter framework, concepts of a measurement active range and a weight correction factorare introduced and a particle swarm is driven to move towards a true state based on a Poisson observation model; the particle weight is corrected by using Gaussian process regression and a sigmoid function, so that the predictive convergence of the particle group is accelerated; clustering processing is carried out on the state space by introducing a mean-lifting algorithm technology and the location of an effective radioactive source is identified and calculated rapidly. Therefore, high-precision and high-efficiency positioning of the radioactive source are realized; the robustness to the environmental radiation drift is high. The method is suitable for the radioactive source localization.

The invention discloses cobalt-free nickel-based alloy powder. The cobalt-free nickel-based alloy powder comprises the following components in percentage by weight: 1.0 to 1.2 percent of carbon (C), 24.0 to 28.0 percent of chromium (Cr), 4.0 to 6.0 percent of wolfram (W), 2.4 to 2.8 percent of silicon (Si), 6.0 to 10.0 percent of aluminum (Al), 4.0 to 6.0 percent of molybdenum (Mo), 0.8 to 1.0 percent of boron, 1.0 to 5.0 percent of yittrium oxide (Y2O3) and the balance of nickel (Ni). The alloy coating prepared by combining the formula of the cobalt-free nickel-based alloy powder with the laser cladding process has a compact structure and no defects, can be well and metallurgically combined with a nuclear valve substrate and has high wear resistance at a high temperature, so that the cobalt-free nickel-based alloy powder is particularly suitable for a nuclear valve sealing face and meets the requirements of the valve working in a nuclear environment.

The invention discloses a cobalt-nickel-free based alloy for a strengthening coating of a sealing surface of a nuclear power valve. The alloy contains the following components by weight percentage: 37.5%-38.5% of chromium, 5.0-6.0 % of carbon, 2.0%-2.5% of silicon, 1.0%-1.5% of boron, 0.5%-1.5% of yttrium oxide and the balance of nickel. The mixing alloy powder is compounded, and the strengthening coating is prepared by a laser cladding technology. The obtained cobalt-nickel-free based alloy strengthening coating of the sealing surface of the nuclear power valve has the relative parameters as follows: the average hardness HRC is 45-50, and is 39-43 higher than the traditional cobalt-nickel alloy coating; the grain size is 11-12, and is finer than the traditional plasma spray-welding coating of 9-10 and the flame surfacing welding layer of 8-9, which is favorable for the comprehensive mechanical property correspondingly; the combined bandwidth of the coating and the base body is 25-40 mum, and is compacter than the traditional plasma spray-welding combined band with the width of 80-120 mum and the flame surfacing welding combined band with the width of 20-300 mum. The invention has the advantages of saving of noble metal, i.e. cobalt, cost reduction, simple preparation technology, conformance to special requirement of nuclear environment, and the like.

The invention discloses a nickel-base alloy coating for a sealing surface of a nuclear power valve, and is characterized in that the nickel-base alloy coating is prepared according to a method of conducting laser-cladding on nickel-base alloy powder. The nickel-base alloy powder comprises the following constituents by weight percent: 20.0 to 24.0 percent of Cr, 4.0 to 4.2 percent of Si, 3.0 to 3.5 percent of P, 3.0 to 3.2 percent of Mo, 8.0 to 8.5 percent of Fe, 1.0 to 1.2 percent of C, 0.8 to 1.0 percent of yttrium oxide, and Ni in balancing amount. The laser-cladding process adopts a synchronous powder feeding method and a pre-coating method. The nickel-base alloy powder mixture contains no noble metal Co, thereby particularly meeting requirements on valves under nuclear environments; and due to the formulation design of the mixture, and the advantage of the laser-cladding technology in coating preparing, the coating on the sealing surface has a favorable high-temperature property.

The invention relates to a CaO-MgO-Al2O3-SiO2 glass encapsulating method for a SiCf/SiC nuclear cladding tube port, wherein part of the raw materials being low in reaction activity and nuclear radiation decay rate and having no side effect on the process of the nuclear reaction is chosen, the raw material is prepared into a glass brazing filler metal through a melting-water cooling method, and a SiCf/SiC composite nuclear cladding tube is encapsulated/connected under the non-pressure condition at the applicable temperature (less than or equal to 1450 DEG C) of the domestic three-generation SiCfiber by depending on the fluidity of the glass and the wetting of a SiCf/SiC composite. The CaO-MgO-Al2O3-SiO2 glass encapsulating method has the beneficial effects that: the raw material of an encapsulating/connecting agent adopts a low-activity element, the nuclear radiation decay rate of the raw material is low, the raw material has no side effects on the process of the nuclear reaction, andthe severe nuclear environment is met. A piece of CMAS (Ca-Mg-Al-Silicate) glass is used as the encapsulating/connecting agent, the coefficient of thermal expansion is matched with that of SiC/SiC, and the interface crack caused by thermal mismatch is effectively prevented and the internal residual stress is reduced. In addition, the encapsulating/connecting condition meets the requirement of thedomestic SiCf/SiC composite.

The invention relates to a liquid-state metal electromagnetic pump. Aiming at solving the problem that an existing electromagnetic pump cannot meet application requirements of a space nuclear power supply system, the invention provides a liquid-state metal electromagnetic pump for a space nuclear environment. The electromagnetic pump is composed of a pump groove assembly, an electromagnetic excitation structure assembly, a gas sealing shell assembly and a power transmission assembly. According to the liquid-state metal electromagnetic pump, an iron core structure has relatively good magnetism conducting efficiency and the weight and volume of the electromagnetic pump are easy to reduce; an annular flow channel of liquid-state metal can effectively improve the working efficiency of the electromagnetic pump; the electromagnetic pump is compact and firm in structure and can bear vibration and impacts from a launching phase to an orbit injection phase of a spacecraft; the gas sealing shell assembly and inert gas can provide effective protection for an electromagnetic excitation structure so that the service life is extremely prolonged and the reliability is extremely improved; and the electromagnetic pump adopts a relatively reasonable design structure so that the control of temperature distribution is facilitated and the electromagnetic pump can stably work for a long period in a vacuum environment.

The invention provides an intelligent emergency lamp for nuclear environment. The intelligent emergency lamp comprises a casing, a liner assembly, a lamp holder, an indicator lamp light passing assembly, a handle, a support plate, a wire inlet mouth, a wire outlet mouth and a circuit device, wherein the liner assembly mainly includes a liner, a rubber sealing strip, a storage battery protection cover, and a circuit board protection cover; the casing and the liner form a double-layer protection structure; the lamp holder and the handle are fixedly mounted on the support plate; the indicator lamp light passing assembly and the wire inlet mouth are mounted on the casing and the liner; and the circuit device is mounted in the liner. The circuit device includes an illuminating lamp, an on-off power supply, a storage battery, an alarm, a test button, an indicator lamp and a circuit board, wherein the an intelligent control circuit is arranged on the circuit board; and the circuit device can provide continuous emergency lighting for 8 hours or more through the illuminating lamp when the normal lighting is interrupted. The intelligent emergency lamp provided by the invention is resistant to impact, voltage, radiation, shake, moisture, and corrosion, has high on-off switching speed, and is convenient in detection and test by using a combined test button.

The invention belongs to the field of insulating conductors, in particular to a poly (ether ether ketone) film lapping-high temperature sintering insulating conductor and a manufacturing process thereof, which aim to solve the problem that the prior insulating conductor has reduced insulativity after working for a long time under a nuclear environment. The conductor consists of an inner conductor(1) and an insulating layer (2) closely attached to the inner conductor (1), wherein the diameter of the inner conductor (1) is between 0.8 and 40mm; and the thickness range of the insulating layer (2) of the insulating conductor is between 0.05 and 0.8mm. The invention also provides a process for manufacturing the conductor, which comprises five steps of aligning the inner conductor, processing the surface of the inner conductor, coating a film, fusing the film and cooling. The insulating conductor and the process have the advantages of high temperature resistance, radiation resistance, hightemperature hydrolyzation resistance, good consistency of the insulating layer material, no toxic substance generation in a sintering process, simple process, and suitability for all kinds of manufacturing, and for insulating layer manufacturing of full wire diameter conductors.

The invention relates to an anti-radiation camera shooting device comprising an anti-radiation key shielding device and a high-radiation shielding protection device, wherein the anti-radiation key shielding device comprises ZF6 lead glass I, a movement, a cylinder I, a back end cover I and a cable connector; the high-radiation shielding protection device comprises ZF6 lead glass II, a cylinder II and a back end cover II; the cylinder I is provided with a cylinder pin I and a cylinder pin II which are respectively positioned with a pin groove I and a pin groove II in the cylinder II and are tightly pressed by a thread ring. According to the anti-radiation camera shooting device, the cylinder I of the anti-radiation key shielding device is filled with lead balls to focally shield gamma ray and damages of neutrons to a camera CMOS (Complementary Metal-Oxide-Semiconductor Transistor) and a circuit microprocessor; the whole structure is cylindrical and no devices, parts or standard parts are arranged on the surface, so that the anti-radiation camera shooting device is suitable for use in a nuclear environment condition; and meanwhile, the whole structure is reasonably sealed and the protection grade can reach IP68; therefore, the anti-radiation camera shooting device is suitable for monitoring operation conditions of fuel workshops of nuclear power stations and equipment in nuclear islands.

The invention relates to a method for separating and purifying xenon in the atmosphere by the use of active carbon and a device thereof. The method comprises the following steps of: adsorbing xenon in the air by using active carbon, collecting gases during the xenon desorption period by the utilization of desorption temperature difference of different substances on active carbon, separating foreign gases such as carbon dioxide, radon and the like, carrying out gradual enrichment and purification through a four-grade adsorption column, and concentrating and collecting the gas into a small container. According to the invention, separation and purification are carried out by the utilization of the desorption temperature difference of xenon and the foreign gases on the active carbon adsorption column, and adsorption, separation and purification are all carried out on the active carbon column so as to reduce a separate impurity removing device. The method is simple. The device provided by the invention can be used to monitor a nuclear power plant, a nuclear reactor, nuclear waste treatment, medical facility leakage and radioactive xenon isotope releasing, and is also used for monitoring the atmospheric nuclear environment.

The invention relates to the field of preparation of wear-resistant coatings, in particular to a preparation method of a nickel-based wear-resistant coating for a nuclear second-stage pump bearing, which solves the problem of difficulties in preparation of bearing wear-resistant coatings for a nuclear environment. The nickel-based wear-resistant coating for the nuclear second-stage pump bearing is prepared by spraying powder onto a matrix through a supersonic flame spraying technology. According to process parameters, the pressure of oxygen is 140 to 160psi; the pressure of propane is 80 to 100psi; the pressure of compressed air is 95 to 110psi; the flow of the oxygen is 340 to 370 standard cubic foot per hour (SCFH); the flow of the propane is 150 to 180SCFH; the flow of the compressed air is 880 to 920SCFH; powder feeding amount is 20 to 30g/min; and a spraying distance is 250 to 290mm. The wear-resistant coating prepared by the method is suitable for the nuclear second-stage pump bearing and has important application value.

The invention relates to a halogen-free flame-retardant heat-shrinkage material for a nuclear island, a halogen-free flame-retardant heat-shrinkage pipe for the nuclear island and a preparation methodof the halogen-free flame-retardant heat-shrinkage material, belonging to the technical field of heat-shrinkage materials for the nuclear island. The halogen-free flame-retardant heat-shrinkage material contains the following raw materials in parts by weight: a polymer base material, an inorganic flame retardant, a polyphosphazene flame retardant, a phosphorus-nitrogen flame retardant, ammonium octamolybdate, a 2,2,4-trimethyl-1,2-dihydroquinoline polymer, a compound antioxidant, an anti-radiation agent and a processing aid. The prepared ultra-long-life and high-radiation-resistance halogen-free flame-retardant heat-shrinkage material for the nuclear island has stable radiation resistance and good flame retardance and is low in smoke, halogen-free and low in toxicity. By adding an organic/inorganic anti-radiation agent into the polymer base material of the heat-shrinkage material, so that the damage effect of a gamma ray in a nuclear environment is effectively restrained, the breakageof C-C bonds among molecules of the polymer material caused due to the stimulation is reduced, and the service life of the material in the nuclear environment is prolonged.

The invention provides an accurate-positioning large-torque rapid locking device under nuclear environment. The accurate-positioning large-torque rapid locking device under the nuclear environment can perform accurate horizontal-plane, vertical-plane and central axis positioning on butting of a robot bottom plate and a blocking plate. Simultaneously, the locking device can perform secondary positioning on the robot bottom plate. The locking device comprises a positioning device and a pressing device. The accurate-positioning large-torque rapid locking device under the nuclear environment achieves rapid stable accurate positioning and large-torque rapid locking of a robot and prevents workers from being in radiation for long time.

The invention relates to a nuclear-environment-resistant cable insulation material. The cable insulation material is prepared from the following components in parts by mass: 100 parts of ethylene-propylene copolymer-methyl methacrylate copolymer, 135 to 145 parts of mixture of nanometer aluminum hydroxide and aluminum hydroxide, 15 to 20 parts of calcined kaolin, 2.5 to 4.5 parts of mixture of 2,2,4-trimethyl-1,2-hydrogenated quinoline and N-isopropyl-N'-phenyl-p-phenylenediamine, 2.5 to 3.6 parts of mixture of N,N'-bi(2,2,6,6-tetramethyl-4-piperidyl)-1,3-dimethyl formamide and 2-(2'-hydroxyl-5'-tert phenyl) benzotriazole, and the like. A preparation method of the cable insulation material comprises the following steps: sequentially carrying out mixing, rubber filtering, blending, screening and extruding on the matching materials under specific process parameters. According to the cable insulation material provided by the invention, the difficult technical problems that the cable insulation material is poor in irradiation resistance in a cable environment, namely, under a high irradiation condition, and the like, are solved. Thus, the demands of specific high-demand situations, namely, the third generation of nuclear power plants, are satisfied; the requirements of the cable insulation material resistant to a nuclear environment are completely met.

The invention provides a forced switching module of working modes of a nuclear industrial robot in a nuclear environment, and the forced switching module belongs to the field of robot control. The forced switching module aims to solve the problem that a robot is trapped in an accident region and is difficult to retrieve when the robot is out of control due to communication outage. According to the forced switching module, a signal intensity detector is arranged outside a radiation protection outer shell which is internally provided with a control circuit, the control circuit comprises a storage battery GB, an intermediate relay K1, a comparator A1, a slide rheostat RP, and NPN transistors VT1 and VT2. An inverting input end of the comparator A1 is connected to a wireless intensity signal output end of the signal intensity detector, a same-phase input end of the comparator A1 is connected to the slide rheostat RP, an output end of the comparator A1 is subjected to two-stage amplification through the VT1 and VT2 to drive a K1 coil to obtain electricity, and an independent control mode is started forcedly.

The invention discloses a nuclear environment wall lamp. The nuclear environment wall lamp comprises a lampshade. The end portion of the lampshade is provided with a clamping ring. The clamping ring is put into a heat dissipation installing groove of a heat dissipation device and is tightly pressed to the closed end of the heat dissipation installing groove through a reflector. The reflector is provided with a light reflecting installation hole, a light source plate is put into the light reflecting installation hole, after penetrating the light source plate, second screws are assembled and fixed to the heat dissipation device so that the light source plate can be fixed to the heat dissipation device, and the light source plate is provided with a light source. The outer side of the clampingring is tightly pressed into the heat dissipation installing groove through a pressing ring, and the pressing ring is assembled and fixed to a heat dissipation body on the heat dissipation device through first screws so that the pressing ring can compress the clamping ring. The pressing ring is provided with first through holes. The heat dissipation device is put into a first inner cavity of a first outer shell, and the closed end of the first outer shell is provided with a plurality of second through holes. After penetrating a second outer shell, third screws are assembled and fixed to heatdissipation installing columns so that the second outer shell, the first outer shell and the heat dissipation device can be assembled into a whole.

The invention discloses a rescue robot with a rescue mechanical arm. The rescue robot comprises a chassis and wheels; the rescue mechanical arm is arranged on the chassis, is a three-section mechanical arm, and mainly consists of such parts as a base, a frame, a movable arm, a head rod, a small arm, a connecting rod, a rocking rod, a quick change connector, a movable arm oil cylinder, a head rod oil cylinder, a small arm oil cylinder, a tool head oil cylinder and a tail end connecting plate; a micro camera is arranged at the middle part of the rescue mechanical arm; through a form of simulating an excavator, the rescue mechanical arm can perform various operations; the tail end connecting plate is arranged at the front end of the rescue mechanical arm, and can load a crushing hammer, a grab, a gripper and the like to realize various needed operations under complicated rescue environment or nuclear environment; and the micro camera is added at the middle part of the rescue mechanical arm, and is used for transmitting video signals, so that the control is more convenient, the remote control is more convenient, the comprehensive practicability is high, and popularization and application are easy.