34results about How to "Shorten the commissioning period" patented technology

The invention relates to a nuclear power station DCS debugging system and a method thereof. The system comprises: a computer server, an operation terminal and a test dolly which are connected through network communication. The operation terminal is used to receive initial condition input by a user and debugging operation information and display an operation simulation result of the computer server so as to be used for DCS debugging analysis. The computer server simulates a continuous production process of the nuclear power station according to the initial condition and the debugging operation information so as to generate dynamic test data. The test data is sent to DCS equipment through the test dolly. A DCS control instruction from the DCS equipment is received and the test data is recalculated. By using the system and the method of the invention, logic preview before nuclear power units are started can be realized so as to reduce a nuclear power unit debugging and starting risk, shorten debugging construction time and save project construction costs.

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 discloses a system for debugging a half-speed steam turbine protection system of a nuclear power plant. The system for debugging the half-speed steam turbine protection system of the nuclear power plant comprises a simulation machine and a valve debugging device, wherein the simulation machine is connected with the steam turbine protection system and used for simulating multiple operating parameters of a steam turbine and sending the multiple operating parameters of the steam turbine to the steam turbine protection system, so that protection action of the steam turbine protection system is tested; and the valve debugging device is connected with a main steam valve of the steam turbine and used for simulating a control signal of the steam turbine protection system to the main steam valve, and whether action of the main steam valve is matched with action of the steam turbine protection system or not is tested by testing opening and closing of the main steam valve. The invention further discloses a method for debugging the half-speed steam turbine protection system of the nuclear power plant. By adoption of the system and method for debugging the half-speed steam turbine protection system of the nuclear power plant, the risks of machine tripping and reactor tripping can be lowered, and the safety and reliability of the system are improved.

The invention discloses a method for adjusting valves of a half-speed turbine of a nuclear power plant. The method comprises the steps that a high-speed recorder collects operation parameters of the half-speed turbine of the nuclear power plant under the operation state; the characteristic of a sensor of the half-speed turbine of the nuclear power plant is determined according to the operation parameters; the valves of the half-speed turbine of the nuclear power plant are adjusted by a special valve adjusting device according to the characteristic of the sensor, and the adjusting process at least comprises adjusting on a main air valve and / or adjusting on an adjusting valve. As the operation parameters of the half-speed turbine of the nuclear power plant under the operation state are collected by the high-speed recorder, and the valves of the half-speed turbine of the nuclear power plant are adjusted by the special valve adjusting device, an adjusting scheme of the nuclear power plant is optimized. The invention further discloses a system for adjusting the valves of the half-speed turbine of the nuclear power plant.

The invention belongs to the technical field of nuclear power station digital instrument control system debugging. The invention particularly relates to a simulation test system and test method of a nuclear power station safety level DCS system. The system comprises a man-machine interface, an input simulation module, an output simulation module, a simulation operation environment database moduleand a plurality of logic processors, the input simulation module is connected between the input end of the simulation operation environment database module and the man-machine interface, and the output simulation module is connected between the output end of the simulation operation environment database module and the man-machine interface; and the simulation operation environment database moduleis also connected with the plurality of logic processors. According to the method, the simulation test of the dynamic working condition of the safety-level DCS system is established during nuclear power station debugging, any hardware facility does not need to be introduced, the field manpower and material cost is reduced, and the debugging efficiency is improved.

The invention discloses a method and a device for flushing vapor side of high-low pressure heater in large-sized heat-engine plant. The valves of the normal drainage conduit and the emergency drainage conduit of a high-low pressure heater system are closed before adjusting; and water is fed into a vapor side pipe of the high-low pressure heater system through a vapor side exit; when the water pressure is close to the biggest bearable pressure of the high-low pressure heater system, the valve of the emergency drainage conduit is opened to drain water. By adopting the probability of blocking the filtering nets at the inlets of a condensate pump and a boiler water feed pump and unexpected stoppage caused by water-level accident are reduced greatly; the reliability of the equipment is improved; the debugging time is shortened; compared with other set of the same type, by adopting the technique, the filtering net blockage is greatly improved, the times for washing the filtering net at the inlet of the condensate pump are decreased by 8 times; if the expense of stopping a large-sized heat-engine set is 600,000 RMB, 4,800,000 RMB can be saved.

The invention provides a water injection replacement and pressure maintenance test method for a hydrogen storage tank of nuclear power station. The method comprises the following steps that 1) SED water is filled into the hydrogen storage tank to replace air in the tank; 2) nitrogen is used to carry out pressure maintenance test on the hydrogen storage tank; 3) hydrogen is used to replace in the SED water in the hydrogen storage tank, and blows to discharge pollution till the hydrogen is qualified; and 4) the pressure of hydrogen storage tank is increased for standby. Compared with the prior art, the method in the invention reduces the safety risk and the debugging cost, shortens the debugging period, and is highly safe, economical and practical.

An intermittent supercritical unit stabilized-pressure pipe blowing method is characterized in that boiler stoppage and shutdown is omitted in the process of supercritical boiler stabilized-pressure pipe blowing, reduced-pressure pipe blowing is performed in hot grinding time first, stabilized-pressure pipe blowing is gradually applied instead, reduced-pressure pipe blowing is applied 2 hours after blowing, a stabilized pressure method is applied after reduced-pressure blowing is performed 5-10 times, and the adverse influences of long pipe blowing period and high oil consumption caused by low condition disturbance in the whole stabilized-pressure pipe blowing process are avoided. The intermittent supercritical unit stabilized-pressure pipe blowing method has the advantages that the defects of long pipe blowing period and high oil consumption of a supercritical unit can be improved, pipe blowing quality is guaranteed, debugging period can be shortened effectively, and fuel is greatly saved.

The invention discloses a step-by-step debugging method of a ladle turret electric system of a continuous casting machine. The method is characterized by comprising the following steps: an electric circuit is checked before electrification; in a decoupling state, joint test and position detecting switches of all input / output points of related substations of a ladle turret are primarily positioned; lifting / descending functions of a ladle cantilever are tested; lifting / descending and shifting-in / shifting-out functions of a ladle capping device are tested; a rotating function of a rotary table is tested; a driving motor monomer of the rotary table is in trail operation; the driving motor of the rotary table drives machinery to perform trail operation; and the 0 position of a motor position encoder is determined. The debugging method finishes the checking work of the electric circuit before electrification of all substations of a PLC, finishes input and output interface tests of all the substations in the decoupling state, and finishes most electric system debugging operations before feeding of a ladle hydraulic and lubricating system, so that the electric system debugging operation safety risk is greatly reduced when the debugging quality is guaranteed and the debugging period is shortened.

The invention provides a nuclear power unit safety level DCS network structure, and belongs to the technical field of nuclear power station safety protection. The system comprises a man-machine data bus, a safety bus and a safety system bus which form a looped network, and a nuclear power unit safety level DCS is arranged in the looped network; arrangement positions of the nodes in the man-machinedata bus, the arrangement positions of the nodes in the safety bus and the arrangement positions of the nodes in the safety system bus meet the conditions that the arrangement nodes of the multiple sub-cabinets with the same panel table are adjacent, and the arrangement nodes of the multiple sub-cabinets with the same power supply are adjacent. The influence on other equipment of the safety-levelDCS when the sub-cabinets with the same panel table and the same power supply are powered off or maintained off the network can be avoided to the greatest extent. The debugging and overhauling work efficiency and debugging efficiency of the safety-level DCS are improved, and the debugging period is shortened; and the influence range of single control station or single-row control cabinet shutdownmaintenance is reduced, and the maintainability and reliability of the system are improved.

The invention discloses a starting method of a combined cycle unit. The combined cycle unit mainly comprises two Siemens combustion engine generators, two waste heat boilers, a steam turbine generator and three main transformers. Firstly combustion engines are ignited so as to cooperate with boiler heating; when the main steam parameters meet the conditions that the pressure ranges from 2.4 MPa to 2.6 MPa, the temperature ranges from 320 DEG C to 350 DEG C and the main steam superheat degree is greater than 56 DEG C, the steam turbine generator prepares impulse starting, gets latched and fully heats the combustion engines, the boilers prepare warming and pressurizing, the quality of steam water is monitored in the warming and pressurizing process of the boilers, sewage discharge is carried out, speed increase is carried out after combustion engine heating is completed, a main oil pump is switched after the constant speed of the unit is stabilized, and various service tests are carried out. According to the starting method of the combined cycle unit, various operation modes of combined cycle of the combustion engines, the waste heat boilers and a steam turbine can be realized, the one-driving-one operation mode, the two-driving-one operation mode and then the one-driving-one operation mode can be realized on the condition without stopping the combustion engines, and the adjustment period can be shortened. According to the starting method, the starting time of combined cycle is shortened, and the starting steps are simplified.

The invention discloses a nuclear power plant emergency power source power supply test method and system, the method is as follows: making a circuit system in the pressure relief state; opening a voltage stabilizer evacuation valve; providing main pump shaft seal water; dismantling a cut-off valve element from a material replacing water tank to a high-pressure safety injection pump inlet; presetting low pressure safety injection pump outlet valve opening degree; in the reactor pressure vessel covered condition, triggering a safety injection signal; starting a low pressure safety injection pump to pressurize a high-pressure safety injection pump to take water from the material replacing water tank to injecting water into a circuit; and due to the dismantling of the cut-off valve element from the material replacing water tank to a high-pressure safety injection pump inlet, flowing water from the low pressure safety injection pump outlet back to a low pressure safety injection pump inlet to form large flow circulation to star an emergency power source power supply test under full load conditions. The beneficial effects are that: the method can be performed without the reactor pressure vessel cover opening condition, and is not limited by test execution windows, other debugging work may not be restricted during the test period, and the debugging working period can be saved.

The invention discloses a safety injection and containment spray mutual standby pipeline system of a nuclear power station. The safety injection and containment spray mutual standby pipeline system comprises at least one group of H4 pipelines. The H4 pipelines are arranged between safety injection systems and containment spray systems in a connected manner, each group of H4 pipelines comprises a first connecting pipeline, a second connecting pipeline and a containment spray pump backflow pipeline; one end of each first connecting pipeline is arranged on an outlet pipeline of a containment spray pump in a communicated manner, and the other end of each first connecting pipeline is arranged on an outlet pipeline of a low-pressure safety injection pump in a communicated manner; one end of eachsecond connecting pipeline is arranged on an outlet pipeline of a containment spray heat exchanger in a communicated manner, each containment spray heat exchanger is positioned on downstream of the corresponding containment spray pump, the other end of each second connecting pipeline is arranged on an outlet downstream pipeline of the corresponding low-pressure safety injection pump in a communicated manner, and a joint of each second connecting pipeline and the downstream pipeline of the corresponding low-pressure safety injection pump is positioned on upstream of a high-pressure safety injection joint; one end of each containment spray pump backflow pipeline is arranged on an outlet downstream pipeline of the corresponding containment spray heat exchanger in a communicated manner, and the other end of each containment spray pump backflow pipeline is arranged on an inlet pipeline of the corresponding containment spray pump in a communicated manner. The invention further provides a test method on the basis of the safety injection and containment spray mutual standby pipeline system of the nuclear power station.

The invention discloses a venturi and porous plate combined cavitation device with an adjustable relative position. The venturi and porous plate combined cavitation device comprises a venturi front section, a front section rectangular groove, a front section flange, a venturi rear section, a rear section rectangular groove, a rear section flange, bolts, nuts, a position adjustment block set, a porous plate, flange bolts and flange nuts; the position adjustment block set and the porous plate are arranged in a rectangular groove formed after splicing of the venturi front section and the venturirear section, the bolts penetrate coincided threaded holes of the rectangular groove, the position adjustment block set and the porous plate to be fastened by the nuts, the flange bolts penetrate coincided threaded holes of the front section flange and the rear section flange to be fastened by the flange nuts, and accordingly, the entire cavitation device is formed; through adjustment of the position of the porous plate in the position adjustment block set, the cavitation characteristics of the cavitation device can be changed. The venturi and porous plate combined cavitation device has the advantages of wide applicable working condition, convenience in processing, reduced material, protection on the integrity of a cavitation flow field, and convenience in cleaning of internal components.

The invention discloses a Venturi mixing device with position-adjustable injector holes in a throat part. The Venturi mixing device comprises a Venturi tube front section, a Venturi tube rear section,studs, nuts, single-head bolts, flange nuts, an injector hole cushion block, an adjusting cushion block group, a front section injector hole group, a front section bolt through hole group, a front section flange, front section injector holes, front section bolt through holes, a rear section injector hole group, a rear section bolt through hole group, a rear section flange, rear section injector holes, rear section bolt through holes and adjusting cushion blocks; the adjusting cushion block group and the injector hole cushion block are embedded into a cylindrical cavity spliced by the Venturitube front section and the Venturi tube rear section, and after the sections are fixed by the bolts and the nuts, the whole mixing device is formed; the mixing effect of the device can be changed by changing the insertion sequence of the injector hole cushion block in the adjusting cushion block group. The Venturi mixing device is applicable to multiple working conditions, manpower and time cost are saved, complete internal flow field of the device is protected, and elements in the tube are relatively convenient to clean.

The invention provides a checking test device for a pool liquid meter of a PTR of a nuclear power station and a test method of the checking test device. The test device comprises a communicating device connected with a demineralization water system and used for providing the water source, and a plurality of adapters respectively installed at the bottoms of liquid meters detachably in a sealing mode, wherein a plurality of connecting pipes are arranged on the communicating pipe, and a main needle-shaped valve is arranged on each connecting pipe; each adapter is connected with the connecting pipes through water injecting pipes, the water injecting pipes are further provided with branch pipe needle-shaped valves and branch joints, and the branch joints are arranged between the main needle-shaped valves and the branch pipe needle-shaped valves, and at least one water dividing opening is reserved in each branch joint and used for adjusting a single liquid level of each liquid meter. The testing method utilizes the testing device. The checking test device for the pool liquid meter of the PTR of the nuclear power station and the test method of the checking test device are restricted by on-site test conditions, the test cost is lower, the test process is more flexible and more efficient, and higher popularization and application value is achieved.

The invention discloses a logic simulation implementation method, device and equipment for a nuclear power plant field control object, and the method comprises the steps: obtaining a to-be-tested equipment list according to a field debugging demand; generating a simulation logic page in configuration software, and forming a simulation program in the simulation logic page according to the to-be-tested equipment list; carrying out incremental downloading on the simulation logic page; and executing a simulation program of the simulation logic page according to the simulation requirement so as tocarry out logic function verification on the corresponding to-be-tested local equipment. According to the invention, under the condition that the internal logic of the current configuration software is not changed, the simulation logic page is added to the configuration software of the DCS system platform to simulate the feedback signal of the field device, so that logic function verification canbe carried out under the condition that no field device exists, and the correctness of configuration is verified in advance.

The present invention provides a nuclear power plant PTR pool liquid level gauge verification test device and its test method, the test device includes: a communication device, connected to the desalinated water system for providing water source, the communication device is provided with a plurality of connecting pipes , each connecting pipe is provided with a main needle valve; a plurality of adapters are respectively detachably sealed and installed at the bottom of the liquid level gauge, each of the adapters is connected to the connecting pipe through a water injection pipe, and the water injection pipe is also connected to the connecting pipe. A branch needle valve and a branch joint are provided, and the branch joint is arranged between the main needle valve and the branch needle valve, and each branch joint has at least one water-splitting port pair, which is used to realize the Individual level adjustment for each of said level gauges. The test method uses the test apparatus described above. The nuclear power plant PTR pool liquid level gauge verification test device and the test method provided by the present invention are not restricted by field test conditions, the test cost is lower, the test process is more flexible and efficient, and has strong popularization and application value.

The invention discloses an assembly type heat exchange station, and relates to the technical field of heat exchange stations. The assembly type heat exchange station comprises a heat exchange controlunit, a water quality guarantee unit and a distribution balance unit. The heat exchange control unit comprises a first modular box body and a heat exchange control assembly arranged in the first modular box body. The water quality guarantee unit comprises a second modular box body and a water quality guarantee assembly arranged in the second modular box body. The distribution balance unit comprises a third modular box body and a distribution balance assembly arranged in the third modular box body. According to the technical scheme, the assembly type heat exchange station adopts an integrated system scheme, various devices, pipelines and matched valves of a conventional heat exchange station are integrated to form the three units according to functions, then the three units which are mutually independent are connected through pipelines, and therefore all the functions of the heat exchange station can be fulfilled. The assembly type heat exchange station can be directly installed in an indoor machine room and can also be combined with the building layout to be installed on the outdoor ground or a building roof, and machine-room-free installation is achieved.

The invention relates to a transformer substation monitoring system debugging method based on digital twinning, and the method employs a transformer substation monitoring system which comprises a station control layer, a spacing layer and a process layer. Comprising the following steps: S1, collecting configuration data of a running transformer substation; S2, realizing offline configuration and debugging work of an online system; S3, restoring and backing up the transformer substation on site; and S4, displaying static information and dynamic real-time running information of the transformer substation. The system has the advantages that the debugging interval of the transformer substation can be operated and visualized through the 3D holographic image information display system, a three-dimensional live-action model can be formed, after the digital twinning monitoring background is subjected to debugging change, the digital twinning monitoring background can automatically correspond to the change of the three-dimensional model, and the debugging efficiency of the transformer substation is improved. Defects such as abnormal configuration of a field operation transformer substation database can be synchronously judged through the digital twinborn monitoring background, the number of times of field repeated defect processing by maintainers in the past is reduced, and more than 30% of human resources can be saved.

The invention belongs to the technical field of air-conditioning water systems, and particularly relates to an assembly type air-conditioning water system circulating water purifying and conveying integrated device and an operation method thereof.The assembly type air-conditioning water system circulating water purifying and conveying integrated device comprises a modular box body, a control unit and a monitoring unit are arranged in the modular box body, and the modular box body is further internally provided with a circulating water conveying unit, a water inlet pipe, a water outlet pipe and a water outlet pipe; the circulating water conveying unit comprises a circulating water pump, a pipeline and accessories; the circulating water purification unit is connected with the circulating water conveying unit, the circulating water purification unit is divided into A type, B type and C type according to a water treatment process, and the circulating water purification unit comprises one or more of an A type purification unit, a B type purification unit and a C type purification unit. Integrated treatment is carried out, equipment is highly integrated, overall installation and debugging are compact and convenient, the civil engineering area is effectively reduced, the installation and debugging period is effectively shortened, the defects of a conventional air conditioner water system are overcome, and engineering implementation and operation maintenance are facilitated.

The invention relates to the field of wireless meter reading, in particular to an AMR / AMI combined meter reading system, device and method, and the method comprises the steps that a cloud server issues an AMR meter reading task instruction and / or an AMI meter reading control instruction; the AMR main control device receives an AMR meter reading task instruction, and the AMI main control device receives an AMI meter reading control instruction; the wireless water meter terminal receives an AMI reading control instruction from the AMI main control device; the wireless water meter terminal sendswater meter information to the AMR main control device and the AMI main control device. The AMR main control device and the AMI main control device send the received vehicle-mounted device end water meter information and the concentrator end water meter information to the cloud server. According to the invention, application requirements of different scenes and different users can be met, debugging and meter reading can be carried out while installation is carried out in the project implementation process, the debugging period in the project is shortened, the project cost is reduced, the deployment is simple, stable and reliable, and the cost is low.

The invention provides an integrated guide jet fan box. The integrated guide jet fan box comprises a jet fan module, silencer modules and flow guide modules. The jet fan module is located in the middle, the silencer modules are symmetrically connected to the two sides of the jet fan module, and the flow guide modules are connected to the silencer modules on the two sides respectively and are also symmetrically arranged relative to the jet fan module. According to the jet fan module, the silencer module and the flow guide module, profile steel frames independently form an appearance frame, stainless steel plates form an outer skin, a trapezoid box body is integrally formed, and a ventilation channel extending along the long bottom edge of a trapezoid is formed in the box body. A jet fan is arranged in the jet fan module, a silencer is arranged in the silencer module, and the end of the flow guide module is provided with a gradually-changed air opening. The problems that civil engineering reservation conditions are complex, and the construction period is long are solved.