35 results about "Accident environment" patented technology

Disclosed are an apparatus and method for reconstructing the scene of a traffic accident. The apparatus includes an information collection unit for receiving images and sounds of a scene of a traffic accident and a stationary object and a moving object located around the scene. A stationary object reconstruction unit reconstructs a 3D shape of the stationary object, and constructs a 3D accident environment. A moving object reconstruction unit aligns the images in time, detecting motions of the moving object from the aligned images, and combines the detected motions of the moving object into the 3D accident environment including the reconstructed stationary object according to times. A reproduction unit reproduces the scene of the traffic accident at corresponding time based on results of combination in response to a time-based playback request, the scene of the traffic accident being reproduced so that the 3D moving object is moved.

The invention provides an estimation method for a critical accident environment release source item of MOX fuel. The method comprises the following steps: (1) determining the total number of fissures;(2) determining the release of aerosol; (3) determining the release of inert gas and radioactive iodine; (4) determining the influence of ventilation and exhaust equipment and purification measures;And (5) calculating the critical accident radiation quantity. The method provided by the invention can estimate the critical accident release amount of the MOX fuel.

A semi-quantitative risk analysis method for the gas pipeline industry based on a risk matrix includes the following steps: (1) determining accident probability grades of the risk matrix; (2) determining seriousness grades for personal loss consequences of accidents; (3) determining seriousness grades for environmental loss consequences of the accidents; (4) determining seriousness grades for property loss consequences of the accidents; (5) determining seriousness grades for reputation effect consequences of the accidents; (6) determining accident consequence seriousness grades of the risk matrix; (7) determining accident scenario risk grades; (8) achieving corresponding functions of the risk matrix through relevant software. The semi-quantitative risk analysis method provided by the invention includes five sub-modules: an information acquisition and input module, an accident probability module, an accident consequence seriousness module, a risk grade judging module, and a risk result output module; each sub-module is provided with specific and detailed computation and assessment methods, so that accident scenario risks can be specifically and strictly defined.

The invention discloses a structural material ultra-high temperature corrosion experiment system and method under a serious accident of a nuclear reactor. The system comprises a gas supply system, a vacuum system, an experiment section, a cooling system and a tail gas analysis system; the gas supply system can be used for preparing corrosive gases with different water vapor contents; the experiment section is composed of a high-temperature radiation furnace, a low-temperature radiation furnace, a ceramic reaction tube, a heating wire, an air-cooled copper tube and heat preservation cotton, andtwo quartz glass windows are formed in the side wall of the high-temperature radiation furnace and used for containing a high-speed camera and an infrared temperature measurement probe respectively;the cooling system can provide necessary cooling for key equipment; the tail gas analysis system can measure the concentration of each component of the corrosion reaction tail gas on line, so that high-precision continuous measurement of reaction kinetics is realized; the experiment system further comprises a power distribution system, a numerical control system and a data measurement and acquisition system. The invention further provides an experimental method. By using the method and system, key data are provided for nuclear reactor safety design by carrying out a structural material ultra-high temperature corrosion experiment in a severe accident environment of the nuclear reactor.

The invention provides a nuclear class-1 equipment performance test method and a nuclear class-1 equipment performance test system, which can test the performance of third-generation and second-generation pressurized water reactor power plant nuclear class-1 equipment under the conditions of the in-accident and after-accident environments in a safety shell, ensure the realization of the temperature and pressure control precision in a preset time period in a thermal shock period and obtain the parameters meeting the requirements of international standards on the test of the performance of third-generation and second-generation pressurized water reactor power plant nuclear class-1 equipment under the conditions of the in-accident and after-accident environments in the safety shell.

The invention relates to a device and a method for measuring temperature and radioactive rays with fiber bragg grating (FBG) sensors. The invention relates to a technology that accurate measurement can be carried out by covering a hollow radioactive ray shielding member on a sensor with two FBG sensors to separate the radioactive ray values and temperature values obtained from the two sensors. According to the invention, no matter in a nuclear station in a normal state or an apparatus generating the radioactive rays, the device can be used as a commonly used sensor system for measuring temperature and radioactive ray quantity, and also realizes commercialization. When a nuclear accident happens, the device also can be used as a sensor system which can remotely measure the temperature and radioactive ray radiation quantities that play critical facts for mastering inner information of accident environment by means of a fiber circuit.

The invention relates to the field of a cable, and particularly to a coaxial cable for a nuclear power station. The cable comprises a conductor. A first insulating layer, a second insulating layer, a first woven shielding layer, a first inner sheath, a second woven shielding layer, a second inner sheath, a metal corrugated pipe and an outer sheath successively wrap the external surface of the conductor. The first insulating layer is made of a thin-wall extruded poly-ether-ether-ketone modified cable insulating material. The second insulating layer is made of radiating crosslinked polyolefin. The thickness ratio between the first insulating layer and the second insulating layer is 1:3-20. The coaxial cable satisfies a requirement for signal transmission among a reactor workshop neutron detector and a junction box and a through member and among an auxiliary workshop through member and a pre-amplifier and a signal processing cabinet in a Chinese third-generation nuclear power plant instrument system. Furthermore the coaxial cable satisfies a requirement for executing a safe function in a designed reference accident environment condition of the third-generation nuclear power plant.

The invention relates to a coal mine accident environment monitoring and rescuing system which comprises a rescue car. The rescue car is provided with a monitoring unit and an alarm unit, wherein the monitoring unit comprises a camera, and the alarm unit comprises an alarm. The rescue car comprises a car body; car windows and car doors are arranged on the side faces of the car body; wheels are arranged at the bottom of the car body, and comprise front wheels and rear wheels; the number of the front wheels is two; a front axle is connected between the two front wheels; the front axle is connected with the bottom of the car body through a front suspension; the number of the rear wheels is two; a rear axle is connected between the two rear wheels; the rear axle is connected with the bottom of the car body through a rear suspension; and a gasbag is arranged on the top of the car body. The coal mine accident environment monitoring and rescuing system is high in rescue efficiency and good in rescue effect, avoids injuries to rescue workers, improves the automatic degree, and meets the demand of practical conditions.

The invention discloses a self-heating device thermal shock water entry accident scene simulation test device and test method, which can complete various test types such as a thermal shock test, a thermal shock water entry test, a seawater simulation test, a seabed long-term storage state environment adaptability assessment test, a seabed vibration environment adaptability assessment test and thelike. The experiment types can comprehensively simulate various accident environment loads of the self-heating device in launching and falling accident scenes, an analysis tool can be provided for product state response of the self-heating device from a dynamic scene to a deep sea storage scene, and technical support is provided for accident environment adaptability evaluation, improved design andthe like of products. The test piece launching device is used for simulating a scene when the test piece falls into seawater, can simulate the water entry angle of the test piece and can also simulate the water entry speed of the test piece, and compared with the traditional technology, the scene simulation is more real, and the detail consideration is richer.

A power distribution room emergency robot first-aid repair decision-making method comprises the steps that field real-time data are obtained through an emergency robot sensor, an analytic hierarchy process is adopted, a priority order of first-aid repair equipment is calculated according to a given criterion index so as to make a first-aid scheme, and first-aid knowledge in a system library and historical equipment operation data in the scene are utilized to give emergency rescue strategies and prompts, augmented information superposition is carried out based on the augmented reality technology, guidance is provided for emergency rescue operation, interactive emergency repair is completed, emergency rapid emergency repair response under the power equipment accident environment is achieved, and the loss degree of the power equipment in the emergency repair process is reduced to the minimum degree to the maximum degree.

The invention discloses a high-entropy alloy film for an accident fault-tolerant nuclear fuel cladding and a preparation method of the high-entropy alloy film, and the method sequentially comprises the steps of grinding and polishing, cleaning and blow-drying, vacuum pressure reduction, sputtering deposition and the like, so that the high-entropy alloy film with an amorphous structure is formed in a magnetron sputtering mode. According to the method, the influence of different contents of different elements on the accident fault tolerance performance of the coating can be researched, meanwhile, the film prepared through the method is high in integrity and compactness, the high-temperature water vapor oxidation resistance of the zirconium alloy substrate in the nuclear reactor accident environment is effectively improved, and the service life of the zirconium alloy substrate is prolonged. And the method can effectively reduce the manufacturing process complexity and the production cost of the accident fault-tolerant nuclear fuel cladding.

The invention relates to an information processing technology, and provides a public emergency evacuation path optimization method under a nuclear accident. The method comprises the steps: determining the range of an emergency planning area, gridding the emergency planning area, determining a nuclear accident environment release source item, and acquiring wind field data in the emergency planning area; calculating each radionuclide activity concentration of each grid in the emergency planning area according to the accident source item and the wind field data, and evaluating a radiation dose rate in the emergency planning area; determining public emergency evacuation path road nodes according to an emergency planning area road network, and the connection relation and attribute information between the nodes, and forming an evacuation network; according to the grids to which the starting points and the ending points of the evacuation paths belong, obtaining all evacuation path sets with relatively low public radiation dose rates based on an improved chaos ant colony algorithm; and performing multi-objective decision optimization according to the evacuation time and the radiation deterministic effect of each path in all the evacuation path sets to determine an optimal path. The method provides an important basis for the formulation of a nuclear emergency plan.

The invention relates to an anti-vibration anti-loosening environment-resistant connector and a cable assembly thereof, the anti-vibration anti-loosening environment-resistant connector comprises a plug and a socket, the plug is installed on a floating support, and the socket is installed on a fixed support; the floating support comprises a base and an upper pressing plate which are detachably connected, a rubber pad is further arranged in a circular ring formed by the base and the upper pressing plate, and the plug is fastened in the circular ring formed by the upper pressing plate and the base to form a flexible supporting structure; and a fixed square plate is arranged on the fixed support, a mounting panel is arranged on the socket, and the mounting panel is fixedly connected with the fixed square plate, so that the socket is mounted on the fixed support, and a rigid fixed structure is formed. According to the invention, the connector body is directly arranged on the corollary equipment by adopting the fixed support and the floating support, so that a cantilever beam structure is avoided, and the anti-vibration and anti-loosening performance of the connector is improved; in addition, the connector adopts complementation of multiple sealing forms, sealing redundancy design is carried out, the overall environment resistance of the connector is improved, and the connector can tolerate extremely harsh working condition environments and severe accident environments caused by natural disasters.

The invention discloses a novel self-heating product anti-accident packing container inner container structure. As the design ideals of high strength and high rigidity are adopted, after a packing container is suffered from such accident environments as falling, a main structure of an inner container and a sealing structure are in good condition without leaking harmful materials; the inner container is positioned in a buffer part on overall structure to reduce the size of the sealing structure; the inner container adopts the design concepts of high strength and high rigidity to guarantee reliability of the sealing structure under accident environments; under the precondition of guaranteeing the strength and the rigidity, a reinforcing rib structure is adopted to relieve the weight of the inner container as far as possible; the high-temperature influence is eliminated to adopt the following measures: an upper cover cutter edge, a base cutter edge and a metal gasket mutually extrude for installation to realize high-temperature sealing; a specific disc-shaped spring is provided for eliminating the influence caused by thermal deformation to realize stable and reliable sealing; and a layer of high-temperature lubricant is coated on a thread for preventing the blockage phenomenon of contacted surfaces between a screw and a base screw hole by the effects of high-temperature thermal expansion and heat erosion.