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4099 results about "Nuclear power plant" patented technology

A nuclear power plant is a thermal power station in which the heat source is a nuclear reactor. As is typical of thermal power stations, heat is used to generate steam that drives a steam turbine connected to a generator that produces electricity. As of 2014, the International Atomic Energy Agency reports there are 450 nuclear power reactors in operation in 31 countries.

Microminiature operation underwater robot of nuclear power plant

The invention relates to a microminiature operation underwater robot of a nuclear power plant, and the robot comprises an underwater robot body and an onshore control system, wherein two propellers are respectively arranged in the horizontal and vertical directions of the robot body, a depth gauge is arranged on the right side of the front part of the robot body, a manipulator is arranged at the bottom in front of the robot body, and a sonar is arranged on the top of the robot body; a control cabin is arranged in the middle rear part of the robot body; an outer cabin is sealed by a transparent glass cover, and is provided with a rearview camera and an auxiliary lighting light-emitting diode (LED) lamp; a front-view camera system is arranged at the front part of the robot body, and comprises a zooming radiation resistant camera tube, a tripod head and a lighting lamp; a video image and control signal is transmitted to the onshore control system through a shield cable; and the control system comprises a movement control rod, a manipulator control button, a keyboard, a main display screen and a speed governing knob. The microminiature operation underwater robot of the nuclear power plant is used for the monitoring and the simple foreign body fishing of a core pool, a spent fuel pool and a component pool of the nuclear power plant.
Owner:BEIHANG UNIV

Active-passive combined reactor core residual heat removal system for nuclear power station

ActiveCN102903404AReduced risk of serious accidentsGuaranteed completeness of security functionsNuclear energy generationCooling arrangementNuclear powerNuclear engineering
The invention relates to an active-passive combined reactor core residual heat removal system for a nuclear power station. The active-passive combined reactor core residual heat removal system comprises a safety injection system, a containment spraying system, an auxiliary water supply system, a reactor cavity water injection system, a secondary side passive residual heat removal system, a passive containment heat leading-out system and related valves and pipelines. The active-passive combined reactor core residual heat removal system provided by the invention realizes three safety functions of controlling reactivity, discharging reactor core heat and containing radioactive substance when an accident occurs in an active-passive combined multi-redundancy diversity manner. The active-passive combined reactor core residual heat removal system provided by the invention can completely realize the safety functions of safety injection and safety spraying under the condition that the accident occurs in a nuclear power plant, reactor cavity water injection under the serious accident working condition and the like, effectively improve reliability of a safety system, enhance coping capability of the safety system under the working condition that the accident occurs in the nuclear power station, can effectively prevent and relieve the serious accident, reduce the reactor core melting probability and risk probability of large-scale radioactivity release and greatly improve safety performance of the nuclear power station.
Owner:CHINA NUCLEAR POWER ENG CO LTD

A Modeling Method for the Third Generation Pressurized Water Reactor Nuclear Power Unit

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.
Owner:STATE GRID HUBEI ELECTRIC POWER RES INST +1

Large-scale passive nuclear plant reactor core catcher with bottom water injection and external cooling

The invention provides a large-scale passive nuclear plant reactor core catcher with bottom water injection and external cooling. The catcher comprises a reactor cavity coating the lower middle part of a reactor pressure vessel, and a reactor cavity concrete soleplate is formed at the bottom of the reactor cavity; a refractory layer is formed on the side surface of the reactor cavity and the bottom of the reactor cavity concrete soleplate; a steel cylinder is sleeved outside the refractory layer; an external cooling passage is formed at the bottom of the steel cylinder, and a cooling passage inlet and a cooling passage outlet are respectively formed at the two outward-extending ends of the external cooling passage; and dozens of nozzles are fixed at the bottom of the steel cylinder, and the upper ends of the nozzles extend into the reactor cavity concrete soleplate while the lower ends of the nozzles extend into the external cooling passage. According to the invention, the dilution and the temperature reduction of a melt are implemented through the melting of concrete by adopting the reactor cavity concrete soleplate as a sacrificial material. A reactor core melt is collected in the refractory layer after the reactor cavity concrete soleplate is molten through, so that the security and the reliability of a nuclear plant are further improved.
Owner:SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD

Nickel-based welding wire for main equipment of nuclear island of nuclear power station

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.
Owner:INST OF METAL RESEARCH - CHINESE ACAD OF SCI

Large-scale passive pressurized water reactor nuclear power plant reactor core catcher with melt expansion room

The invention provides a large-scale passive pressurized water reactor nuclear power plant reactor core catcher with a melt expansion room. The large-scale passive pressurized water reactor nuclear power plant reactor core catcher with the melt expansion room comprises a reactor cavity which coats the middle lower portion of a reactor pressure vessel, a reactor cavity concrete base plate is arranged on the lower portion of the reactor cavity, and a reactor cavity refractory layer is arranged on the lower portion of the reactor cavity concrete base plate. The upper end of a melt release passage is communicated with the reactor cavity refractory layer, and the lower end of the melt release passage is communicated with the melt expansion room. The inner wall of the melt release passage surrounds the refractory layer. An expansion room concrete base plate is arranged on the lower portion of the melt expansion room, an expansion room refractory layer is arranged on the lower portion of the expansion room concrete base plate, and an expansion room outside cooling passage is arranged on the lower portion of the expansion room refractory layer. Two ends of the expansion room outside cooling passage extend outwards and are respectively an outside cooling passage entrance and an outside cooling passage exit. The large-scale passive pressurized water reactor nuclear power plant reactor core catcher with the melt expansion room is used for successively implementing expansion, retention and cooling of the melt when the a pressure container loses efficacy and can strengthen capacity of relieving severe accidents of the large-scale passive pressurized water reactor nuclear power plant.
Owner:SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD

Testing device of nuclear power station digitized instrument and control system

ActiveCN102184750AFirmly connectedOvercome the problem of not being able to test several related devices in parallel at the same timeNuclear energy generationNuclear monitoringProcess systemsNuclear power
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.
Owner:CHINA TECHENERGY +1

Device and system for monitoring and displaying normal operating condition of unit of nuclear power plant

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.
Owner:CHINA GENERAL NUCLEAR POWER CORP +1

Method and device for controlling starting and stopping of turbo generator set of nuclear power plant, and digital control system (DCS)

The invention is applied in the field of nuclear power control, and provides a method for controlling the starting and stopping of a turbo generator set of a nuclear power plant, a device for controlling the starting and stopping of the turbo generator set of the nuclear power plant, and a digital control system (DCS). The method comprises the following steps of: detecting the running state and running parameters of the turbo generator set, the running state and running parameters of an auxiliary system of the turbo generator set, and fault information in the running of the turbo generator set; displaying the detected information on the same function tracking interface in a centralized way; and directly controlling the starting and stopping of the turbo generator set according to the information displayed on the function tracking interface. The method provided by the embodiment of the invention can make an operator directly and rapidly discover the anomaly of the turbo generator set, rapidly and accurately obtain key parameters and judge reasons, so that the operator can directly, rapidly and accurately control and intervene the starting and stopping of the turbo generator set of the nuclear power plant to ensure the security of the turbo generator set of the nuclear power plant.
Owner:GUANGDONG NUCLEAR POWER JOINT VENTURE +1

Ultrasonic automatic scanning device for large-aperture pipeline in nuclear power plant

The invention relates to an ultrasonic automatic scanning device for a large-aperture pipeline in a nuclear power plant. The ultrasonic automatic scanning device comprises a mechanical scanning part, an electric control part and a pipeline part, wherein the mechanical scanning part comprises a circumferential guide rail part, a circumferential moving module and an axial moving module; the circumferential guide rail part comprises an annular body and a plurality of supporting legs which are mounted on the inner side of the annular body and are capable of moving along the radial direction of the annular body; the circumferential moving module comprises a circumferential guide rail fixed on the annular body, an arc-shaped fixed plate which is detachably mounted on the circumferential guide rail and is capable of moving along the circumferential guide rail, and a circumferential driving motor which is fixed at one end of the arc-shaped fixed plate and is meshed with the circumferential guide rail; the axial moving module comprises an arc-shaped frame detachably mounted on the arc-shaped fixed plate, a probe disk which is parallel to the arc-shaped fixed plate, can slide in the arc-shaped frame and is used for fixing ultrasonic probes, an axial driving motor fixed on the arc-shaped frame, and a transmission mechanism which is connected with the axial driving motor and is used for driving the probe disk. On one hand, the mechanical scanning part is modularized, so that the occupation space can be effectively reduced, and the mechanical scanning part can conveniently move and be mounted in the narrow space of the nuclear power plant; on the other hand, the mechanical scanning part is in a detachable quick connection locking mode, so that the mounting time is shortened.
Owner:CGNPC INSPECTION TECH +2

Simulation system of loading and unloading operation processes in pressurized water reactor nuclear power plants

The invention relates to a simulation system of loading and unloading operation processes in pressurized water reactor (PWR) nuclear power plants. The system comprises an LED (light emitting diode) display screen, a touch screen, an operation control table consisting of a component part consisting of a button, a switch, an operating rod, an indicator lamp and an alarm, an information communication and processing device consisting of a programmable logic controller PLC (programmable logic controller) and a PC graphic workstation, a display device consisting of a scene display and a camera, and an industrial personal computer. The simulation system of the loading and unloading operation processes is designed in strict accordance with functions of real loading and unloading machines, is featured with rich simulated objects, reliable simulation data and strong reality, simulates various common abnormal states or failure states, allows interactive operation, clears faults and has a component showing function; the touch screen has an interface control function; the system simplifies layout of an operation table, expands subsequent functions, effectively trains loading and unloading operators and is widely applied to nuclear power stations and related analogue simulation systems.
Owner:STATE NUCLEAR POWER PLANT SERVICE
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