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

System and method for debugging half-speed steam turbine protection system of nuclear power plant

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.
Owner:中广核工程有限公司 +1

Step-by-step debugging method of ladle turret electric system of continuous casting machine

ActiveCN107321967AReduce safety risks in commissioning operationsGuarantee debugging qualityMelt-holding vesselsElectricityDrive motor
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.
Owner:SHANGHAI ERSHIYE CONSTR CO LTD

Nuclear power unit safety level DCS network structure

ActiveCN110324224AImprove the efficiency of commissioning and maintenance workImprove reliabilityLoop networksBus networksMaintainabilityNuclear power
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.
Owner:中广核工程有限公司 +2

A method for starting a combined cycle unit

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.
Owner:中国能源建设集团华北电力试验研究院有限公司

Nuclear power plant emergency power source power supply test method and system

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.
Owner:中广核工程有限公司 +1

Safety injection and containment spray mutual standby pipeline system of nuclear power station and verification method on basis of safety injection and containment spray mutual standby pipeline system

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.
Owner:中广核工程有限公司 +1

Venturi and porous plate combined cavitation device with adjustable relative position

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.
Owner:XI AN JIAOTONG UNIV

Venturi mixing device with position-adjustable injector holes in throat part

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.
Owner:XI AN JIAOTONG UNIV

Checking testing device for pool liquid meter of PTR of nuclear power station and testing method of checking testing device

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.
Owner:中广核工程有限公司 +2

System and method for debugging a half-speed steam turbine protection system in a nuclear power plant

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.
Owner:中广核工程有限公司 +1

A calibration test device and test method for a liquid level gauge in a nuclear power plant ptr pool

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.
Owner:中广核工程有限公司 +2

Assembly type heat exchange station

PendingCN111998421ACompact and convenient installation and commissioningSmall footprintHeating fuelLighting and heating apparatusThermodynamicsProcess engineering
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.
Owner:CHINA RAILWAY DESIGN GRP CO LTD

Reserved auto-switch-on method requiring free setting of fixed value based on trend direction partition topology

The invention relates to a reserved auto-switch-on method requiring free setting of a fixed value based on a trend direction partition topology. The reserved auto-switch-on method is applied to powersystem network, wherein the power system network comprises a plurality of reserved auto-switch-on areas which are subjected to superior-junior series connection; and each of the reserved auto-switch-on areas comprises four kinds of equipment including a superior power supply, a corresponding level bus bar and incoming line, a corresponding level bus bar outgoing line, wherein the corresponding level bus bar outgoing line is used as the superior power supply of the next level of reserved auto-switch-on area. The reserved auto-switch-on method comprises the following steps: acquiring configuration parameters of all equipment in the power system network; judging the state of all equipment according to the configuration parameters and preset criterions; controlling the various reserved auto-switch-on areas, and searching the topmost level of reserved auto-switch-on area which can recover the power supply to apply the auto-switch-on action according to the sequences from the superior to thejunior in association with the configuration parameters, the state of the equipment and the action logic of the reserved auto-switch-on. According to the reserved auto-switch-on method disclosed by the invention, reserved auto-switch-on fixed values are not needed to be set from mounting and debugging of the device to operating maintenance.
Owner:BEIJING SIFANG JIBAO AUTOMATION

Transformer substation monitoring system debugging method based on digital twinning

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.
Owner:STATE GRID ZHEJIANG ELECTRIC POWER CO LTD JINHUA POWER SUPPLY CO

Circulating water purifying and conveying integrated device for assembled air-conditioning water system and operation method of circulating water purifying and conveying integrated device

PendingCN114315004ACompact and convenient installation and commissioningReduce civil areaMultistage water/sewage treatmentControl cellProcess engineering
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.
Owner:CHINA RAILWAY DESIGN GRP CO LTD

The step-by-step debugging method of the electrical system of the ladle turntable of the continuous caster

ActiveCN107321967BReduce safety risks in commissioning operationsGuarantee debugging qualityMelt-holding vesselsEngineeringOperation safety
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.
Owner:SHANGHAI ERSHIYE CONSTR CO LTD

Debugging method, device and system for steam turbine control system of nuclear power plant

The invention discloses a debugging method of a nuclear power station steam turbine control system. The method comprises the steps that a nuclear power station steam turbine control system simulation model is established, the simulation model at least comprises a simulation debugging device; the nuclear power station steam turbine control system is connected with the simulation model, the nuclear power station steam turbine control system at least comprises one of a steam turbine adjusting subsystem, a steam turbine protecting subsystem, a steam turbine monitoring subsystem (GME) and a steam turbine shaft seal subsystem, each subsystem is subjected to simulation debugging through the simulation debugging device, and according to the simulation debugging results, the functions of the subsystems are verified. According to the debugging method of the nuclear power station steam turbine control system, the simulation model is used for being connected with the steam turbine control system, system function verifying is carried out in advance, nuclear power plant debugging scheme optimizing is achieved, the debugging period is shortened, and the risk of steam turbine unexpected halt and the risk of reactor unexpected tripping after a nuclear power unit is started are lowered. In addition, the invention further discloses a debugging device and system of the nuclear power station steam turbine control system.
Owner:中广核工程有限公司 +1
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