8976 results about "Nuclear power" patented technology

The invention relates to a nuclear power plant working robot and a control system thereof, which belong to the fields of robots and automation equipment. The nuclear power plant working robot is a crawler-type mobile manipulator and is composed of a mobile platform driven by double crawlers and a four freedom degree manipulator carried on the mobile platform. The nuclear power plant working robot can move inside a nuclear power plant, has two control modes of manual remote control and autonomous control, and is remotely controlled by a wireless or wired mode. The control system of the nuclear power plant working robot includes a host monitoring and planning control system and a robot control system which are matched to control the operation of the robot. The robot operates autonomously, is safe and reliable, can complete certain dangerous tasks in high radioactivity environment; the robot has small size, stable performance, great maneuverability and low operation cost; a crawler-type chassis has strong gripping force as well as certain climbing and obstacle clearing ability, and is suitable to walking over complex terrains; and the robot has high intelligence degree and can realize autonomous control and manual remote control.

The invention belongs to safety equipment for a nuclear power plant, in particular to a passive and active combined special safety system for the nuclear power plant. The system comprises a passive high-pressure core water supply tank, an accumulator, a low-pressure safety injection pump, a refueling water tank, a secondary-side passive residual heat removal heat exchanger, a vapor condensation water tank, a containment spray system, a passive reactor cavity water injection system, related valves and related pipes. When the nuclear power plant has a design basis accident or beyond design basis accident, through a series of passive and active safety facilities used in all steps, the circuit of a reactor and the core can be cooled effectively, so that the nuclear power plant can enter a safe cold shutdown condition smoothly; and thus, the serious accident consequence of the reactor is inhibited or relieved, damage caused by accidents is relieved, and the safety of the nuclear power plant is improved.

The invention discloses a modeling method for a third generation pressurized water reactor nuclear power generating unit. The modeling method comprises the following steps of: 1, decomposing a nuclear power generating unit system into a plurality of subsystem models; 2, establishing the subsystem models in the step 1 according to heat engineering and energy transfer and conversion rules; 3, combining the subsystem models obtained in the step 2 into a nuclear power generating unit full system model, and connecting the nuclear power generating unit full system model with a power system model toobtain a combined model of a nuclear power generating unit and the power system; and 4, establishing a customized model of the third generation pressurized water reactor nuclear power generating uniton the basis of the combined model of the nuclear power generating unit and the power system, and simulating the performance of the nuclear power generating unit and machine-grid interaction according to the customized model. The method effectively solves combined emulation of the nuclear power generating unit and a power unit, can be applied to machine-grid coordination analysis of a nuclear power plant and a power grid, and has high practicability.

This invention relates to a method and apparatus for nuclear power station equipment risk evaluation by computer. Wherein, using a computer to quantize the fault effect and store the information in a database; creating a logic relation between fault and facilities abnormity, as well as the abnormity and parameters; periodic acquiring device real-time data to substitute into the logic relation and calculate probable fault and risk; if over the early-warning value, producing alarm signal. This invention can monitor the plant for security, automatic evaluates risk to eliminate human factor, and obtains much accurate result.

The invention belongs to the technical field of pipe whip restraint steel structures of main power houses of nuclear power station conventional islands, in particular to a production process method of the pipe whip restraint steel structure of the main power house of the nuclear power station conventional island, which comprises the lofting process, the marking-off and scribing process, the cutting processing process, the bevel processing process, the hole-making process, the correction process, the polishing surface, the material splicing process, the pre-splicing process of a steel member, the assembly process, the processing process of a friction surface, the welding process of the steel structure and the anti-slip test of the friction surface of the steel member before leaving a factory, sandblasting, derusting and coating of a base coat are carried out in the factory, and the production of the steel structure is divided into the production processing of a welded H-shaped steel column, the production of a steel beam, the assembly and the welding of a support part, the production of a combined steel beam, the assembly and the welding of a girder box body and an inclined support below the girder box body, and the assembly and the welding of a pipe whip restraint key. The production process method can improve the drilling precision, utilize a numerical control planar drilling machine to complete the drilling on a gusset plate, determine a variety of processing processes and welding process parameters, and ensure the dimension of the member after the assembly and the smooth proceeding of field installation.

The invention belongs to the technical field of welding materials, and particularly discloses a nickel-based welding wire for main equipment of a nuclear island of an AP1000 nuclear power station. The method is applicable to welding pressure containers of reactors (including welding of driving tube seats, safe seats of connecting tubes and supporting blocks of reactor cores) and welding of steam generators (including build-up welding of tube plates and welding of tubes and the tube plates), and solves problems that welding wires of the kind in the prior art are always imported, cost is high and the like. Basic chemical components of the nickel-based welding wire include, by weight ratio, from 28.0 to 31.5% of Cr, from 7.0 to 11.0% of Fe, from 0.4 to 1.0% of Ti, from 0.25 to 1.10% of Al, from 0.90 to 1.5% of Al+Ti, lower than or equal to 1.0% of Mn, lower than or equal to 0.02% of Nb, lower than 0.04% of C, lower than or equal to 0.15% of Si, lower than 0.005% of P, lower than 0.005% of S, lower than 0.001% of B, lower than 0.02% of Zr, lower than 0.005% of Ca, lower than 0.005% of Mg, lower than 0.02% of Ta, lower than 0.02% of Cu, lower than 0.05% of Co, lower than 0.5% of Mo and the balance Ni. By the aid of the welding wire, microalloying of weld joints can be realized, the weld joints meet standard requirements, and the welding wire can replace imported welding wires.

The invention discloses a method and system for testing a configuration logic design of a DCS (Distributed Control System) of a nuclear power station. The method comprises the following steps of: importing a designed configuration logic diagram to be tested into a selected minimal configuration DCS; communicatively connecting the selected minimal configuration DCS with an engineering simulation process platform; according to the preset test progress, running the configuration logic diagram to be tested on the minimal configuration DCS, and interacting data with the engineering simulation process platform, then recording a test result; and according to the test result, modifying the configuration logic diagram to be tested. According to the method and system disclosed by the invention, the configuration logic diagram is tested by using the minimal configuration DCS and the engineering simulation process platform, the correctness and completeness of the result can be virtually verified without depending on real field equipment, the debugging work period is shortened, and the safety and reliability of the design process is guaranteed.

The invention relates to a multi-operating mode energy-saving controlled combined type thermostatic and humidistatic air conditioning unit with a thermometal compound box body structure special for nuclear power stations. The air conditioning unit comprises a control system and a box body structure, wherein a primary-efficiency filter, a medium-efficiency filter, a surface cooler, a heater, a humidifier and a blow-off device are sequentially arranged in the box body; the front side of the primary-efficiency filter is provided with a fresh air and return air mixing section, and inlets of fresh air and return air are respectively provided with a fresh air proportioning valve and a return air proportioning valve; the control system adopts a programmable logic controller (PLC) and adopts air conditioning multi-operating mode zone control to realize the energy-saving operation of the unit; the surface cooler adopts a large temperature difference cold water heat exchanging technology and can save the investment and operation expenses of a water system; and the box body adopts a double-layer compound structure and an anti-shock device to meet the special requirements on the nuclear power stations. The invention has the characteristics of high efficiency, energy saving, good tightness, strong anti-shock capacity, safety, reliability, long service life, and the like.

The invention discloses a testing device of a nuclear power station digitized instrument and control system. The testing device relates to the field of automation control and comprises a control device and a signal processing device, wherein the control device comprises an industrial control computer, a collection card installed in the industrial control computer and a control software controlling the testing process; the signal processing device comprises a layplate and a conditioning card; two ends of the layplate are connected with the collection card and the conditioning card through signal wires respectively; and the other end of the conditioning card is connected with a DCS (data communication system) control cabinet to be tested through a signal wire. The testing device adopts the DCS control cabinet or process system as a unit for testing, and can enable all the signals to be simultaneously connected into the testing device for finishing all the test items of the DCS control cabinet or the process system by one time, thus improving testing efficiency and saving human resource. The control method shows the testing state and expected result in real time, the simulation software can simulate the control loop of the process system, and the control accuracy and control effect of the process system state testing can be set according to the needs.

The invention relates to a device and a system for monitoring and displaying normal operating condition of a unit of a nuclear power plant. The nuclear power generating unit has a plurality of operating modes; on a display device, a monitoring module is imported aiming at one operating mode; the monitoring module comprises four units displaying simultaneously, namely a trend tracking unit, a value display unit, a device state unit and an accident condition indication unit. The technical scheme of the invention is that: a reactor operating mode is dominant so as to perform a system monitoring design; according to the change of the normal operating state of the nuclear power generating unit, for a certain working mode, frequent and intersystem monitoring and analysis are needed; parameters and equipment to be monitored are concentrated in a unified monitoring module and displayed through the display device so as to facilitate the monitoring and operation of the total state of the nuclear power generating unit; and the defect of a DCS (digital control system) in the aspect of intuition is overcome, the advantages of a control room of the DCS are fully played, and the safe and stable operation of the nuclear power plant is ensured.

The invention relates to a water reducing agent with high efficiency used in polycarboxylate concrete and a synthetic method thereof, which is characterized in that: plyethylene glycol methylacrylic acid single armor esterification (MPEGMA) macromonomer synthesized by (methyl) acrylic and polyethylene glycol monomethyl ether added with catalyst and other (methyl) acrylic or (methyl) allyl sodium monomer are grafted and copolymerizated to synthesize into binary or polybasic copolymer comprising carboxyl, sulfonic group and polyoxyethylene chain side under the effect of initiator and chain transfer agent. The products synthetically prepared by the invention has the advantages of high water reducing ratio, low chlorine and low alkali; the cement mixture is high in fluidity and good in mixability, and can restrain slump loss effectively, when 0.7 to 1.2 percent by weight of cement material is added. The water reducing agent with high efficiency used in polycarboxylate concrete is simple in technology, easy in control of reaction condition and reasonable in cost, does not pollute environment, and can be used as the important component of high performance concrete, marine concrete, nuclear power station concrete and anticorrosion concrete and is widely used in the field of industry, civil building, water conservancy, road traffic and nuclear power engineering.

The invention belongs to a nuclear power station safety system, and in particular relates to a nuclear power station non-active engineering safety system. The system comprises a secondary non-active residual heat removal exchanger, a steam condensation water tank, a non-active reactor cavity water injection system, a non-active high pressure reactor core water supplementing tank and related valves and pipelines. When a nuclear power station is in a design basis accident or a hyper design basis accident, a series of non-active and active safety devices are invested in steps, and a reactor primary circuit and a reactor core are timely, rapidly and effectively cooled, thus a nuclear power station smoothly enters into a safe cold shut-down amplifier state, a reactor disaster consequence is inhibited or alleviated, incident harm is reduced, and the safety of the nuclear power station is improved.

The invention is concerned with an assembled and seal method of box crane beam with ring type orbit using for nuclear power plant, belonging to the establishment construction technology field of nuclear power plant. It relates to rectification of stuff, sealing inner and outside webs and clapboard, sealing upper and down wing edge and the inner and outside webs, sealing stiffened panel, sealing end plate and the rectify after seal. Assemble and seal the web and inner muscle plate to a type of H to reduce the distortion and keep the seal quality, while the temporary backboard controls the final seal distortion when sealing the end plate. It will control the distortion effectively to reach the demand of the first level of nuclear quality and nuclear safety through easy adjustment of circle crane beam after sealed with steady quality.

The invention provides an irradiation-crosslinked low-smoke halogen-free inflaming retarding insulation material for a nuclear power station cable. The insulation material comprises the following components in parts by weight: 100 parts of basic resin (A), 2-5 parts of antioxidant (B), 3-10 parts of irradiation-resisting agent (C), 110-170 parts of fire retardant (D), 2-10 parts of compatilizer (E), 0.1-0.8 part of anticopper agent (F), 0.2-2 parts of lubricant (G) and 2-10 parts of cross-linking sensitizing agent (H), wherein the basic resin (A) comprises a combination of polyethylene-octeneelastomer (POE) ethylene-butyl acrylate (EBA) and linear very low density polyethylene (VLDPE), and the weight ratio of the POE to the EBA to the VLDPE is (10-20):(65-80):(10-20).