114 results about "Pressurizer" patented technology

The invention discloses a self-heating type ammonia decomposition hydrogen production system applied to a mobile terminal in the technical field of ammonia hydrogen production. The system comprises an ammonia storage tank, a heat exchanger, a pressurizer, an ammonia fuel engine, a self-heating type ammonia decomposition reactor, a hydrogen buffer tank and a tail gas aftertreatment device, in the ammonia decomposition hydrogen production reactor, ammonia gas in an ammonia storage tank and hydrogen generated by ammonia decomposition are mixed and combusted to supply heat; tail gas generated after mixed combustion of ammonia and hydrogen in the ammonia fuel engine and the self-heating type ammonia decomposition reactor is used for preheating ammonia gas to enter the ammonia decomposition reactor, and then the tail gas is discharged after being treated by the tail gas treatment device; ammonia gas is supplied in three paths and is respectively used for hydrogen production through ammonia decomposition, combustion in an engine and combustion heat supply in a reactor; and hydrogen is used in two paths and is used for supplying heat for ignition fuel in the engine and combustion in the reactor respectively. The system fully considers the use requirement of the mobile terminal and energy recycling, and has the characteristics of compact structure, high energy utilization rate, adaptation to an ammonia fuel engine and the like.

The invention provides a pressurization storage tank and a pressure filling tank truck with the pressurization storage tank. The pressurization storage tank comprises a tank body, a liquid level detection device, a pressurization pipeline, a pressurizer and a liquid outlet valve. The liquid level detection device is used for detecting liquid level information in the tank body; one end of each pressurizing pipeline communicates with the bottom of an inner cavity of the tank body, the other end of each pressurizing pipeline communicates with the top of the inner cavity of the tank body, and the multiple pressurizing pipelines are arranged in parallel; the superchargers are communicated with the supercharging pipelines, and each supercharging pipeline is provided with one supercharger; the liquid outlet valves are communicated with the pressurizing pipelines and located on the upstream of the pressurizer, and each pressurizing pipeline is provided with one liquid outlet valve. When a worker uses the pressurizing storage tank to unload liquid, the superchargers with different numbers or different powers can be started and stopped according to the liquid level information detected by the liquid level detection device, so that the self-adaptive matching between the pressurizing capacity and the size of a gas phase space in the tank body is realized, and the whole liquid unloading process is more stable and efficient.

The purpose of the present invention is to suppress the solidification of a pressure medium and to perform a pressurization process at a required pressure. The isostatic pressing device (10) uses a pressure medium having the property that the higher the pressure is, the higher the viscosity is. An isostatic pressing device (10) is provided with: a pressure vessel (12) in which a processing space (12a) capable of accommodating a pressure medium is formed; a supercharger (14) that pressurizes the pressure medium in the processing space (12a) to obtain a set pressure; a first heater (37), which is provided in a high-pressure pipe (32) connecting the supercharger (14) and the pressure vessel (12), and which heats the pressure medium to a target temperature before the pressure medium is introduced into the processing space (12a); and a second heater (39) that is provided upstream of the first heater (37) in the high-pressure pipe (32) and heats the pressure medium before reaching the first heater (37).

The utility model provides a safety type gas water heater heat exchanger which comprises a water heater body and a heat exchanger, the heat exchanger is installed in the water heater body, a first water inlet pipe is arranged at the bottom of the heat exchanger, a filtering assembly is arranged at one end of the heat exchanger, and a second water inlet pipe is arranged at the bottom of the water heater body. The second water inlet pipe is connected with the filtering assembly through a supercharger; a first water outlet pipe is arranged on one side of the heat exchanger and connected with a second water outlet pipe at the bottom of the water heater body through a connecting pipe. A pressure sensor is arranged on the first water outlet pipe and electrically connected with a controller arranged on one side of the water heater body. According to the heat exchanger, the filtering assembly is arranged at one end of the first water outlet pipe, cold water needs to pass through the heat exchanger firstly and then enters the heat exchanger, double filtration of the cold water is achieved through the filtering assembly, various impurities in water can be intercepted, the chance that corrosive substances make contact with the heat exchanger is reduced, and the risk that the heat exchanger is corroded is reduced.

The present invention provides a feed gas pressurization system and a control method therefor, belonging to the technical field of low-carbon blast furnace feed gas processing equipment. The system comprises a gas supply pipeline and a liquid supplementation pipeline; a pressurizer has an inlet and an outlet, the gas supply pipeline and the liquid replenishing pipeline each being in communication with the inlet of the pressurizer; a heat recovery device has a first heat exchange channel and a second heat exchange channel for mutual heat exchange; a gas-liquid separator has a mixture inlet and a gas outlet, the outlet of the pressurizer is communicated with an inlet of the first heat exchange channel, an outlet of the first heat exchange channel being in communication with the mixture inlet of the gas-liquid separator, and the gas outlet of the gas-liquid separator being in communication with an inlet of the second heat exchange channel. The present invention purifies feed gas, and reduces the probability of subsequent equipment being blocked or failing due to impurities in the feed gas. At the same time, the purified feed gas is used to cool a gas-liquid mixture, which is beneficial for gas-liquid separation of the gas-liquid mixture, and fully utilizes heat absorbed by the gas-liquid mixture, to improve energy utilization efficiency.

The present application relates to a kind of nuclear power plant surge line nozzle heat shield sleeve structure and system, comprising: support ring, fluid distribution cover, heat shield sleeve, nuclear power plant surge line nozzle and cladding layer.The nuclear power plant surge line nozzle heat shield sleeve structure and system described above when actually used, through the one end of support ring and the cladding layer of surge line nozzle connection, the other end and fluid distribution cover connection, the one end of heat shield sleeve is inserted into support ring and is connected with support ring, to form gap between the other end of heat shield sleeve and the safety end of surge line nozzle, radioactive particles generated in the annular space between heat shield sleeve and surge line nozzle during reactor operation can be discharged from the gap, thereby avoiding the difficulty and cost of in-service inspection caused by the fact that the safety end of heat shield sleeve surge line nozzle forms a sealed space, so that the risk of high radiation faced by inspection and maintenance personnel is reduced.

A pressure control method and a pressure stabilizing control system. The method comprises: acquiring a pressure measurement value and a pressure setting value of a pressurizer (101); determining a pressure deviation value on the basis of the pressure measurement value and the pressure setting value (102); if the absolute value of the pressure deviation value is less than or equal to a first preset value, regulating the charging flow and the letdown flow of a circuit on the basis of the pressure deviation value and the pressure measurement value, so as to control the pressure of the pressurizer (103); and if the absolute value of the pressure deviation value is greater than the first preset value, on the basis of the pressure deviation value, controlling the pressurizer to inflate or deflate so as to control the pressure of the pressurizer (104). The method and the system can improve the pressure stabilizing effects of pressure stabilizing control systems.

The application discloses a method for reducing the maintenance frequency of a converter gas centrifugal pressure booster, and relates to the technical field of industrial automation control, comprising the following steps: obtaining the operation instruction of the converter gas centrifugal pressure booster and the pipe network pressure fluctuation data; determining the current working condition mode of the converter gas centrifugal pressure booster based on the pipe network pressure fluctuation data; generating a variable frequency control logic, including a segmented speed-up strategy and a segmented speed-down strategy corresponding to the working condition mode, wherein the segmented speed-up strategy and the segmented speed-down strategy both comprise a first speed stage and a second speed stage higher than the first speed stage, and the speed change rate of the second speed stage is smaller than that of the first speed stage; and calling the corresponding strategy from the variable frequency control logic to control the operation of the converter gas centrifugal pressure booster based on the operation instruction. Under the premise of guaranteeing the safe response of the pipe network pressure, the application significantly inhibits the unstable shedding of the attached objects and prolongs the dynamic balance maintenance period of the fan.

The application discloses a gas parameter adjusting method for a reaction kettle and belongs to the field of high-temperature and high-pressure equipment control. The gas parameter adjusting method for the reaction kettle adjusts and controls the gas temperature and pressure in the control kettle and the reaction kettle through adjusting the gas booster and the heating belt, realizes two-stage accurate regulation and control of the gas temperature, pressure, concentration and other parameters before and after entering the kettle and real-time dynamic supplement, guarantees high consistency between the test working condition in the kettle and the field working condition; on the other hand, the application solves the problem that the gas composition and the proportioning accuracy in the reaction kettle are reduced due to the fact that the mixed gas formed by the reaction medium solution volatilization and the reaction gas under the simulated actual working condition cannot be realized in real time and accurately during the reaction gas proportioning process, thereby guaranteeing the high consistency between the test environment in the reaction kettle and the actual working condition and the reliability of the test result, and significantly improving the safety.

The utility model discloses a fire hose pressure measuring pump which comprises a measuring pump assembly main body and a hose fixing base, the front surface of the measuring pump assembly main body is fixedly connected with an output pipe, and the front surface of the measuring pump assembly main body is connected with a pressure retaining valve in a limiting mode. A pressure release valve is connected to the front surface of the measuring pump assembly body in a limiting mode, a pressurizer is fixedly connected to the front surface of the measuring pump assembly body, a limiting assembly is movably clamped to the upper surface of the water hose fixing base in a limiting mode, and a clamping block is movably connected to the inner ring surface of the limiting assembly in a limiting mode; the inner ring surface of the limiting assembly is in limiting connection with a pressing block, and the inner ring surface of the limiting assembly is in limiting clamping connection with a limiting nut. According to the device, through the arrangement of the mounting plate fixedly connected with the back surface of the measuring pump assembly main body and the multiple mounting openings formed in the mounting plate in a penetrating mode, a user can conveniently carry out use limiting mounting on the mounting plate and the measuring pump assembly main body through bolts.

This invention discloses an automatic beveling device for repairing surfacing welds on pressurizer bushings, belonging to the technical field of nuclear power plant nuclear island maintenance equipment. The automatic beveling device includes a mechanical body comprising a clamping assembly, a rotating platform, a radial movement mechanism, an axial feed mechanism, a cutting head assembly, and a monitoring assembly. The automatic beveling device provided by this invention processes the surfacing weld into a spatial elliptical J-shaped bevel, laying the structural foundation for subsequent welding. It addresses the need for automatic beveling when repairing the bottom bushing of the pressurizer lower head using a cutting and surfacing welding method on-site. It provides an important automatic beveling function for on-site repair of the sealing weld of the pressurizer bushing, while also enabling remote control and monitoring, reducing the impact of personnel radiation dose.

The present disclosure belongs to the field of nuclear power technology, and specifically relates to a method and apparatus for determining the real-time leakage rate of a nuclear power plant's main system. The disclosed method for determining the real-time leakage rate of a nuclear power plant's main system determines the leakage rate of the nuclear power plant's main system during a detection period based on changes in the liquid level of the control box, the liquid level of the pressurizer, and the temperature of the primary circuit. Main system parameters can be collected in real time and the leakage rate of the main system calculated, thereby enabling timely and accurate monitoring of leakage in the main system, avoiding human error and reducing human radiation exposure. This method has been successfully used to monitor the real-time leakage rate of the main system of nuclear power plant units.

The invention relates to the field of novel silicon carbon deposition equipment, in particular to a gas external circulation system applied to a fluidized bed type silane deposition furnace, which comprises a bracket, a column type fluidized bed, a three-way pipe, a bearing frame, a cooler, a pressurizer, a heater, a breather pipe, an exhaust pipe and a gas injection pipe, a column type fluidized bed is mounted on the bracket; the column type fluidized bed is communicated with a three-way pipe; the support is provided with a bearing frame. The bearing frame is sequentially provided with a cooler, a pressurizer and a heater from top to bottom; the cooler, the pressurizer and the heater are jointly communicated with a breather pipe; the breather pipe and the column type fluidized bed are jointly communicated with an exhaust pipe; and the breather pipe and the three-way pipe are jointly communicated with an air injection pipe. The process gas is filtered through the dust collection cloth capable of being flexibly adjusted, and the problems that in the prior art, filtering dust removal equipment can be cleaned only after silane deposition furnace equipment is cooled, and non-stop cleaning or replacement of the filtering dust removal equipment cannot be achieved are solved.

The invention relates to the field of nuclear power equipment installation and maintenance, in particular to a quick wiring device for an electric heater of a voltage stabilizer. The device comprises a male plug and a female plug which can realize coupling; a jack is arranged at the front end of the male plug, at least one metal insertion rod is arranged in the jack, and a wiring end is arranged at the rear end of the metal insertion rod; an arc-preventing head is arranged at the head of the metal inserting rod; the end part of the female plug is provided with a plug-in part which can be inserted into the jack, the end part of the plug-in part is provided with a metal insertion tube, the metal insertion tube is internally provided with an elastic conductive sleeve, and the elastic conductive sleeve can be used for the insertion of the metal insertion rod and is in fit contact with the outer wall of the metal insertion rod; a plurality of arc-shaped elastic pieces protruding in the axis direction are distributed on the side wall of the elastic conductive sleeve in an annular array mode. A female plug shell is arranged outside the female plug, an insulating seat is arranged in the female plug shell, at least one second mounting hole is formed in the insulating seat, the metal insertion tube is mounted in the second mounting hole, and the insulating seat is made of a ceramic material. The device is high in safety efficiency, easy to replace and low in maintenance dependence.

The invention provides a multifunctional test bench for researching the performance of a primary loop voltage stabilizer of a reactor and a test method. The test bed is mainly composed of a water supplementing system, a main loop system, a steam and inert gas pressure stabilizing system and a drainage system. The test bench can be used for simulating the cold-state starting process of a primary loop of a traditional reactor, starting characteristics of the loop when a steam pressure stabilizer and an inert gas pressure stabilizer serve as the loop are obtained respectively, and a basis is provided for performance evaluation of different pressure stabilizers.

This invention discloses a pressurized heat exchange hydrogen supply device and method for a solid-state hydrogen storage system, relating to the field of solid-state hydrogen storage technology. The device includes: a filter for filtering hydrogen output from the solid-state hydrogen storage system; a first hydrogen booster for increasing hydrogen pressure to a target range; a first heat exchanger for reducing the pressurized hydrogen to a preset temperature range; a regulating valve for regulating hydrogen flow rate; and a pressure transmitter, temperature transmitter, and flow meter for measuring hydrogen pressure, temperature, and flow rate, respectively. A PLC dynamically adjusts the operating status of the first hydrogen booster, the opening of the regulating valve, and controls the start and stop of the first heat exchanger. This invention integrates the pretreatment unit, the pressurized heat exchange unit, and the flow regulation unit into a single unit. It employs an automatic control system with a PLC controller at its core, combining the real-time acquisition of outlet parameters by the temperature transmitter, pressure transmitter, and flow meter to dynamically adjust the opening of the flow regulating valve, achieving constant control of the output pressure or flow rate.

The present invention belongs to the field of condensate removal technology and specifically discloses a vacuum pump condensate removal system, comprising a control terminal, a vacuum buffer tank, a condensate collection tank, an underground waste liquid collection tank, and several pump body assemblies, each pump body assembly comprising a vacuum pump and a vacuum pump inlet separator tank; a first solenoid valve is provided between the vacuum buffer tank and the condensate collection tank, a second solenoid valve is provided between the condensate collection tank and an external pressurizer, and a third solenoid valve is provided between the vacuum device and the condensate collection tank; a fourth solenoid valve is provided between the condensate collection tank and the underground waste liquid collection tank, and a fifth solenoid valve is provided at the second discharge port end of the bottom of the vacuum pump inlet separator tank; the first, second, third, fourth, and fifth solenoid valves are all connected to the control terminal. This system automatically and promptly removes condensate, allowing for thorough condensate removal even when the vacuum pump is operating, preventing damage to the vacuum pump caused by excessive condensate.

The invention belongs to the technical field of polyurethane waste treatment, and particularly relates to a device and method for oxidation treatment of polyurethane. The polyurethane oxidation treatment device comprises a polyurethane storage bin, a water purification tank, a preheater, an oxygen tank, a pressurizer and an oxidation kettle, a discharging opening of the polyurethane storage bin is communicated with a feeding opening of the oxidation kettle, and the polyurethane storage bin is used for conveying polyurethane waste into the oxidation kettle; purified water stored in the purified water tank is conveyed to the oxidation kettle after being heated by the preheater, and is used for providing supercritical water for the oxidation kettle; oxygen stored in the oxygen tank is pressurized by the pressurizer and then is conveyed to the oxidation kettle for providing high-pressure oxygen for the oxidation kettle. The device for oxidation treatment of polyurethane has the beneficial effects that the device for oxidation treatment of polyurethane can efficiently treat polyurethane under the low-temperature condition, meanwhile, pollutants such as nitrogen oxides can be prevented from being generated, and generated CO2 gas is purer and is convenient to capture so as to reduce the greenhouse effect.

The present invention relates to the technical field of nuclear power plant maintenance optimization, and particularly to a method, device, computer device and storage medium for determining the defect position of a nuclear power plant pressurizer. The method includes receiving a detection instruction for defect detection of a nuclear power plant pressurizer; the nuclear power plant pressurizer includes a pressurizer shell and at least one branch pipe; a curved surface is provided on the pressurizer shell, and the branch pipe is arranged on the curved surface and connected to the curved surface through a pressurizer weld; determining a defect scanning device and defect scanning parameters for defect detection of the nuclear power plant pressurizer according to the weld parameters and the pressurizer parameters; causing the defect scanning device to perform phased array ultrasonic defect detection from the outside of the pressurizer weld according to the defect scanning parameters to generate a defect detection waveform; and determining defect position information corresponding to the pressurizer weld according to the defect detection waveform and the obtained preset detection map. The present invention improves the defect detection efficiency, accuracy and safety.

The present invention relates to an apparatus (100) for applying a coating material to a wire (106), the apparatus (100) comprising: a coating chamber (102) for applying a coating material to a wire (106) passing through the coating chamber (102), the coating chamber (102) having an inlet port (120) configured to receive the wire (106) and an outlet port (121) configured to discharge the wire (106); an elongated injection channel (103) having a first portion (131) and a second portion (132), the first portion (131) including an opening (130) for receiving a predetermined amount of coating material in a solid state, the second portion (132) being in communication with the coating chamber (102); and at least one heating element (104) configured to increase the temperature of the coating material as it flows through the injection channel (103). According to the invention, the coating device (100) further comprises: a pressurizer (105) configured to operate according to a first operating phase, in which the pressurizer (105) applies a predetermined pressure to the coating material in the first portion (131) of the injection channel (103), and a second operating phase, in which the pressurizer (105) is in a position in which the injection channel (103) can receive a predetermined amount of solid coating material; and a cooling system (119) configured to cool at least a portion of the first portion (131) of the injection channel (103).

This invention relates to a continuous spray regulation method for a nuclear power unit pressurizer, comprising the following steps: performing pre-test state settings for a steam generator auxiliary feedwater system pump test; after completing the pre-test state settings for the steam generator auxiliary feedwater system pump test, performing pre-test state settings for continuous spray regulation of the pressurizer; performing initial state settings for the continuous spray regulation test of the pressurizer; and after completing the initial state settings, performing fine-tuning for the continuous spray regulation test of the pressurizer. The continuous spray regulation method for the pressurizer of this invention eliminates the coarse-tuning portion during execution, avoiding mutual interference between coarse-tuning and the steam generator auxiliary feedwater system pump test, significantly reducing test time. Furthermore, it can quickly locate the initial point for fine-tuning, greatly reducing fine-tuning time. Since it does not interfere with the steam generator auxiliary feedwater system pump test, it reduces unit risk and reliably completes the continuous spray regulation of the pressurizer.

A hydroelectric power generating device utilizing a siphon mechanism is provided. [Solution] A hydroelectric power generation device characterized by having a siphon mechanism that performs siphon motion and includes a water tank (1), a hydraulic pressurizer (14), a rotating cylinder central axis (4), a rotating cylinder water wheel (11), a straightening plate (13) fixed to the water tank (1), a rotating cylinder (2), a spiral plate (3) installed inside the rotating cylinder (2), a vacuum water tank (7), an air valve (8), a water level sensor (19), a water conduit (9), and an on-off valve, all of which are inside the device, utilizing the characteristics of siphon motion, in which a liquid ascends through a pipe with no gaps and is transported past a point higher than its original position; a water intake mechanism that sucks up water for power generation from the water tank (1) inside the device to the vacuum water tank (7); and a power generation mechanism that generates power from the vacuum water tank (7), including the water conduit (9), a power generation water wheel (10), and a discharge pipe (12).

The present application relates to a method and system for controlling the level of a pressurizer of a reactor coolant system of a nuclear power unit, comprising the following steps: switching to a newly added pressurizer water level set value control logic when the temperature of a primary loop is less than or equal to a first preset value; obtaining real-time temperature data of the primary loop after switching to the newly added pressurizer water level set value control logic; calculating the real-time temperature data to obtain a level setting value of the pressurizer; obtaining primary loop flow data and real-time level of the pressurizer; calculating the primary loop flow data, the level setting value and the real-time level to obtain valve position data; and adjusting the level of the pressurizer according to the valve position data. The present application switches to the newly added pressurizer water level set value control logic when the temperature of the primary loop is less than or equal to the first preset value, so as to raise the water level of the pressurizer to a reasonable level before connecting the residual heat removal system, thereby reducing the subsequent time length of the pressurizer steam elimination cavity, reducing the occupation of the overhaul critical path window, and significantly improving the economy.

The invention belongs to the technical field of surface strengthening, and particularly relates to an ultrahigh-pressure hot isostatic pressing method taking liquid metal as a medium based on a press machine. A to-be-treated workpiece and molten liquid metal are put into a liquid metal container, the whole container is filled with the liquid metal container, and then an upper cover is covered; applying pressure to the liquid metal container by using a press machine, and keeping the displacement unchanged; heating the liquid metal container by using a high-temperature furnace and preserving heat until the upper value of the force sensor is relatively stable; the steps are repeated without liquid metal in the liquid metal container, and the pressure intensity generated in the container is calculated according to the difference value of the two forces and the area of the container; and according to the obtained pressure intensity and temperature, the workpiece to be treated and the molten liquid metal are put into a liquid metal container, and after hot isostatic pressing treatment is conducted, the workpiece is directly taken out of the liquid metal to be rapidly cooled. Compared with traditional hot isostatic pressing achieved through gas and a supercharger, the method has the advantages of being simple in principle, convenient to operate and high in safety.

The utility model discloses a rack-mounted CDU liquid cooling heat dissipation structure which comprises a heat dissipation structure main frame assembly, a liquid storage assembly is installed on the side edge surface of the heat dissipation structure main frame assembly, and the front surface of the heat dissipation structure main frame assembly is fixedly connected with an operator assembly. A liquid storage component assembly is installed on the surface of the bottom of the operator component assembly, a pressurizer component assembly is fixedly connected to the front surface of the operator component assembly, a mounting plate is installed on the front surface of the heat dissipation structure main frame assembly, and a fixed limiting block is clamped to the front surface of the mounting plate in a limiting mode. According to the device, when a user needs to carry out liquid cooling heat dissipation, the user needs to turn on a motor, the motor can drive arranged fan blades to rotate after being started, then the user needs to turn on a pressurizer assembly through a controller, and liquid is circularly output through a refrigeration liquid conveying pipe assembly; in this way, a user can efficiently use and dissipate heat.

The invention discloses a sea water desalination device based on wave power generation, which comprises a shell, a power generation module and a sea water desalination module, the shell comprises a forecabin, the power generation module and the sea water desalination module are arranged in the forecabin, the power generation module comprises a support, a linear reciprocating mechanism and a generator, the support is connected in the forecabin in a manner of swinging back and forth, and the linear reciprocating mechanism is connected with the generator. The seawater desalination module comprises a distillation component, a pressurizer and a reverse osmosis membrane component, the distillation component is fixedly connected with the support and comprises an evaporation pond and a primary desalination water storage pond, a condensation top plate inclining towards the primary desalination water storage pond is arranged above the evaporation pond, and the reverse osmosis membrane component is arranged above the condensation top plate. A heater is arranged in the evaporation pond, a water outlet of the preliminary desalination water storage pond is connected to a pressurizer through a pipeline, the pressurizer supplies water to the reverse osmosis membrane component for reverse osmosis purification, and the generator provides electric energy for the heater and the pressurizer. The structure is compact, and convenient arrangement and application are facilitated.

The present invention relates to an automatic maintenance work platform for electric heaters in a nuclear power plant, comprising: a clamping mechanism for clamping the electric heater to be processed; an adjustment base, on which the clamping mechanism is installed, and the adjustment base is provided with an installation interface for installing operation tools; and a centering adjustment structure for adjusting the position of the adjustment base according to the state of the electric heater to be processed and locking and fixing the adjustment base after adjusting the position, so that the operation tools operate on the electric heater to be processed on the clamping mechanism. The automatic maintenance work platform for electric heaters can realize the follow-up adjustment of the positions and angles of operation tools such as cutting and welding of the pressurizer electric heater according to the position state of the electric heater to be processed, and solve the problem of position docking between the operation tools and the electric heater to be processed on the premise of meeting stability.

The invention provides a cutting device and a cutting system for an electric heater sleeve of a voltage stabilizer, and relates to the technical field of nuclear power. The cutting device for the electric heater sleeve of the voltage stabilizer comprises a clamping module and a cutting module, wherein the clamping module is suitable for surrounding and clamping the electric heater sleeve of the voltage stabilizer; the rotating module is rotationally connected with the clamping module, and the rotating module is suitable for being arranged on the electric heater sleeve of the voltage stabilizer in a sleeving mode and rotates with the sleeve axis of the electric heater sleeve of the voltage stabilizer as a rotating shaft; the at least one cutting module is fixedly connected with the rotating module, the cutting module comprises a cutter, and the cutter is suitable for cutting the casing pipe of the electric heater of the voltage stabilizer; and the stirring module is fixedly connected with the clamping module, and the stirring module is suitable for driving the cutter, located at the preset position, of the cutting module to move in the direction close to the axis of the sleeve when the rotating module rotates.

The utility model belongs to powder modification auxiliary equipment technical field relates to a kind of powder surface modification equipment, including the installation of modification cylinder, atomization pressurizer and hot air machine on support ring, and feed tank is hung on support ring, detachable installation has hot flow catalytic device on modification cylinder, hot air machine is connected hot flow catalytic device by air pipe, and modification cylinder bottom surface is equipped with stirring cleaning device, and modification cylinder inner chamber side and hot flow catalytic device are all closely attached stirring cleaning device.The utility model through hot flow catalytic device, not only can provide suitable temperature environment for modification reaction, accelerate the performance of chemical reaction, but also can be synergized stirring with stirring cleaning device, promote the flow of powder and modifier, enhance the contact and collision frequency between them, to speed up the speed of modification reaction, shorten modification cycle;Through stirring cleaning device, stick powder is promptly removed in stirring process, reduce the jam and blockage phenomenon of powder in equipment interior.

The invention relates to the technical field of nuclear power, in particular to a nuclear power unit primary circuit strength water pressure test method. The nuclear power unit primary circuit strength hydraulic pressure test method comprises the following steps: preparing equipment participating in the test; completing system online according to a hydrostatic test boundary, and performing a hydrostatic test in a primary loop cold state; reducing the pressure and the liquid level of the primary loop, establishing a nitrogen cushion in a pressure stabilizer, and starting a main pump to heat the primary loop to a hydrostatic test temperature after exhausting; the frequency converter adjusts the charging pump to gradually increase the primary loop pressure to each test platform for leak detection, then the frequency converter is used to gradually increase the outlet flow of the strength hydrostatic test pump, the primary loop pressure is increased to the pressure of the strength hydrostatic test platform, and then the primary loop pressure is reduced to the leak detection platform for leak detection; carrying out secondary loop strength hydraulic pressure test in cooperation with primary loop pressure reduction; recovering the system state after the hydrostatic test and preparing to heat the reactor. According to the invention, the accuracy and reliability of the test are effectively improved, the potential damage risk to the component is reduced, and the test period is shortened.