45 results about "Pressurizer" patented technology

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 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 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 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 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.

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.

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 utility model relates to the technical field of stock bin cleaning, in particular to a pulse unblocking mechanism for a stock bin, which comprises a mounting frame, a first sealing box body is slidably mounted at the upper end of the mounting frame, an extension pipe is fixedly mounted at the upper end of the first sealing box body, a pressurizer is mounted at the side end of the first sealing box body, and the extension pipe is fixedly mounted at the lower end of the first sealing box body. And a second sealing box body is slidably mounted at the side end, away from one side of the pressurizer, of the first sealing box body, two stop blocks are rotatably mounted in the second sealing box body, and a sliding rod is slidably mounted in the extension pipe. According to the improved pulse unblocking mechanism for the stock bin, a pressurizer is matched with a conveying pipe to pressurize the interior of the device, a second driving motor is matched to drive a gear to transmit, and then two rotating rods are driven to rotate so as to drive two stop blocks to downwards press a fixing plate, so that the device can be rapidly pressurized during use, and the use efficiency of the device is improved. And meanwhile, the structure is simple, and use is convenient.

Disclosed is a method for dismantling metal equipment of a heat transport system in a containment building at a nuclear power plant, the metal equipment including a heat transport pump, a steam generator, a pressurizer, a condenser, and a D2O tank, including: a first dismantling step of dismantling the heat transport pump; a second dismantling step of dismantling the steam generator after the first dismantling step; a third dismantling step of dismantling the pressurizer after the second dismantling step; and a fourth dismantling step of dismantling the condenser and the D2O tank after the third dismantling step.

A method of operating a nuclear reactor system includes operating a first nuclear reactor to generate steam, the first nuclear reactor positioned in a wellbore extending from a surface through one or more subterranean formations; closing the first nuclear reactor; placing a second nuclear reactor into the wellbore; and operating the second nuclear reactor to generate steam. A method of controlling a nuclear reactor system includes boron injection and removal, and regulating a pressure of at least one of a pair of regulator vessels. The first regulator vessel is in fluid communication with the primary coolant at a first depth of the reactor vessel. The second regulator vessel is in fluid communication with the primary coolant at a second depth of the reactor vessel. The reactor vessel is positioned in a wellbore extending from the earth surface through one or more subterranean formations.

The utility model discloses a spray head for detecting the waterproof performance of a product, which relates to the field of spray heads for detecting the waterproof performance of the product and comprises a base, a support arranged at the top of the base, a water storage barrel arranged at the top of the support, a water line arranged on the outer wall of the water storage barrel, and a high-pressure water inlet arranged at the bottom of the water storage barrel. A common water inlet is formed in the end, close to the high-pressure water inlet, of the bottom of the water storage barrel, a pressurizer is installed in the water storage barrel, a high-pressure water pipe is installed at the bottom of the pressurizer and installed in the high-pressure water inlet, a common water pipe is installed in the common water inlet, and first nozzles are installed at the two ends of the common water pipe. A common nozzle is installed at the front end of the first nozzle, second nozzles are installed at the two ends of the high-pressure water pipe, high-pressure nozzles are installed at the front ends of the second nozzles, a detection box is installed at the top of the base, and high-pressure water outlets are formed in the top and the bottom of the detection box.

To suppress a rise in water level of a pressurizer when a filling flow control valve malfunctions.SOLUTION: A pressurizer water level control method comprises a step (S1) of acquiring a water level of a pressurizer connected to a primary coolant system during a steady-state operation of a nuclear reactor, steps (S1, S2) of adjusting a primary coolant filling flow rate from an extraction flow rate of the primary coolant from the primary coolant system 10 and a filling flow rate of the primary coolant based on the water level of a pressurizer 14, and a step (S5) of increasing an extraction amount of the primary coolant when the estimated filling flow rate based on the adjustment of the filling flow rate is inconsistent with an actual filling flow rate (S3) and the water level of the pressurizer 14 is high (S4).SELECTED DRAWING: Figure 4

This invention provides a method for analyzing low-flow and temperature deviations in the spray valve of a pressurizer in a nuclear power plant, comprising the following steps: Step 1: Establishing a heat transfer model for the spray valve pipeline to calculate heat transfer under different flow rates and predict temperature change trends; Step 2: Calculating the flow resistance coefficient of the pipeline at different valve core rotation angles under low flow rates; Step 3: Performing thermal expansion analysis of the valve core-seat clearance and transmission splines caused by temperature to obtain the flow area and flow resistance coefficient at the corresponding temperature; Step 4: Establishing an analysis model for the factors affecting the flow rate and temperature deviation of the spray valve, and conducting fault factor diagnosis analysis. This invention establishes a calculation model and analysis method for heat transfer, valve core rotation, and transmission mechanism linkage under the coupled effects of temperature, flow resistance, and flow rate, and ultimately establishes a design method for controlling temperature deviation and a fault analysis method for causing temperature deviation.

This invention belongs to the technical field of nuclear reactor systems, specifically relating to an automatic depressurization system for a pressurized water reactor. It includes four stages of depressurization valves. The first three stages are connected to the pressurizer steam chamber and share a connecting pipe with two of the three pressurizer safety valves. The discharge from the first three stages is collected and then enters the depressurization water pool inside the containment via a sprayer, and is subsequently discharged into the containment through the depressurization water pool. The automatic depressurization system proposed in this invention has a simpler configuration, reduces the number of devices by 20%, has higher reliability, simplifies operation, and reduces the power supply load. The fourth stage uses an electric valve instead of the explosion valve in units such as the AP1000, meeting the start-up and operation requirements of the passive safety injection system and improving the safety of the nuclear power unit.

This invention relates to the field of chemical automation technology, specifically to an automatic switching continuous gas supply system for argon, comprising a gas source module including a liquid argon vacuum storage tank and a multi-parameter interlocking control system. The liquid argon vacuum storage tank is connected to an ambient temperature vaporizer, and the downstream end of the ambient temperature vaporizer is connected to a gas buffer tank. The output end of the gas buffer tank is connected to an argon pressure regulating valve group. The liquid argon vacuum storage tank includes a tank body and a self-pressurization control system. The liquid argon is pressurized to 1.0 MPa by the self-pressurization control system and then enters the ambient temperature vaporizer to complete the gas-liquid conversion. The vaporized argon is depressurized to 0.65 MPa by the argon pressure regulating valve group and then supplied to the electroslag furnace at the gas-consuming terminal. This system combines two modes: gravity-driven self-drainage of the storage tank and passive vaporization pressurization by the self-pressurizer. When the tank pressure is acceptable but the flow rate is insufficient, gravity-driven self-drainage is relied upon. When the pressure is below the operating threshold, the self-pressurization control system is triggered to utilize ambient waste heat for vaporization pressurization.

A substance processing system includes a pressurizer configured to pressurize air and a processing chamber configured to process a substance. The system also includes a heat exchanger coupled between the pressurizer and the processing chamber. A nozzle is coupled to the processing chamber such that output from the nozzle comprises a substantially even pressure distribution.

Test chamber 4 is the main work area wherein all the control parameters, e.g., pressure and temperature, are controlled as per the defined parameters. Non-pneumatic pressurizer 100 may operate as a high pressure pumping unit with forward and backward pressure regulation, works with PLC 140 and uses feedback from a pair of pressure transducers 130,132 to control pressurization and de-pressurization rate as per the defined parameters and also regulates pressure inside test chamber 4 corresponding to heat generated inside test chamber 4 because of heat generated from test equipment.

An air purifying filter cleaning apparatus for cleaning an air purifier including an air purifying filter disposed between a contaminated air inlet and a purified air outlet. The air purifying filter cleaning apparatus includes: a nozzle portion disposed to face the purified air outlet and for discharging a first cleaning solution to the purified air outlet; a cleaning solution storage in which a second cleaning solution discharged from the contaminated air inlet is collected; a first purifier for removing contaminants contained in the second cleaning solution received from the cleaning solution storage; a first storage tank in which a third cleaning solution, which is a solution remaining after the contaminants are removed from the second cleaning solution by the first purifier, is stored, and a pressurizer for supplying the third cleaning solution stored in the first storage tank to the nozzle portion.

The application provides a method for removing hydrogen in a pressurized water reactor nuclear power plant primary loop, which comprises the following steps: removing hydrogen through control of a pressurizer exhaust hydrogen removal process and simultaneous control of a hydrogen dissolution process in the primary loop coolant, so that the hydrogen dissolution in the primary loop after the pressurizer exhaust cavity is less than 5 cc / kg, and the primary loop is in an atmospheric condition. The hydrogen removal method determines the completion judgment standard of the pressurizer exhaust and the prerequisite condition of the pressurizer exhaust cavity, and simultaneously determines the matching hydrogen dissolution control strategy in the primary loop coolant during shutdown, so that the hydrogen dissolution in the primary loop system after the pressurizer exhaust cavity is less than 5 cc / kg, the main line work period of the large repair shutdown is shortened, the low-temperature crack propagation of the primary loop system caused by the hydrogen dissolution is avoided, and the economic benefits are maximized.

The utility model discloses waste heat recovery energy-saving equipment of a device for preparing ethylene glycol through hydrolysis, which belongs to the technical field of chemical production and comprises a circulating liquid cooler and an ethylene glycol refining tower top cooler, and an ethylene glycol refining tower is arranged on one side of the ethylene glycol refining tower top cooler. A discharge port of the reactor is connected with a feed port of the reaction circulating liquid pump through a pipeline, a flow meter d, a flow control valve d and a waste heat recovery supercharger are arranged on the bypass pipeline, the bypass pipeline is connected with the waste heat recovery supercharger, and a flow meter e and a flow control valve e are arranged on the bypass pipeline. After being pressurized, process steam generated by the circulating liquid cooler and the ethylene glycol refining tower top cooler meets the requirement of 0.6 Mpa grade steam which can be used by a hydrolysis ethylene glycol preparation device, so that the problem of waste is avoided, meanwhile, the circulating water consumption of the device can be reduced, the steam unit consumption and the circulating water unit consumption in the operation of the device are reduced, and the energy consumption of the device is reduced. And economic income is increased for the device, so that the device is in efficient and energy-saving operation for a long time.

The invention relates to the technical field of data processing, in particular to a transient operation parameter prediction method and device and electronic equipment. The method comprises the following steps: acquiring actual acquisition data acquired by at least one data acquisition device in the nuclear power station at the current moment; inputting all the actually acquired data into a prediction model for prediction to obtain a predicted value of the transient operation parameter within a preset duration after the current moment; wherein the prediction model is obtained through training of historical collection data collected by all the data collection devices, and the transient operation parameters comprise one or more of the steam generator outlet steam mass flow, the voltage stabilizer fluctuation pipe temperature and the coolant flow; and generating a prediction result of the transient operation parameter based on the prediction value of the transient operation parameter.

Test chamber 4 is the main work area wherein all the control parameters, e.g., pressure and temperature, are controlled as per the defined parameters. Non-pneumatic pressurizer 100 may operate as a high pressure pumping unit with forward and backward pressure regulation, works with PLC 140 and uses feedback from a pair of pressure transducers 130,132 to control pressurization and de-pressurization rate as per the defined parameters and also regulates pressure inside test chamber 4 corresponding to heat generated inside test chamber 4 because of heat generated from test equipment.

The temperature and pressure control method comprises the steps that a high-pressure heating device is arranged on a high-pressure pipeline between a working cylinder and a supercharger, the supercharger communicates with a low-temperature liquid inlet pipe through a hydraulic pump, and during working, the hydraulic pump and the supercharger inject low-temperature liquid into the high-pressure heating device through the low-temperature liquid inlet pipe at the process set pressure intensity; and the liquid heated by the high-pressure heating device is injected into the working cylinder at the process set temperature and the process set pressure. According to the method, the liquid passing through the supercharger is low-temperature liquid, and high-temperature creep deformation and sealing failure cannot be generated on related parts of the supercharger in the supercharging process, so that the operation safety of equipment and the quality of processed products are guaranteed.

The utility model belongs to the technical field of fan devices, and particularly relates to a fan device for a shaft furnace pressurizing machine. A machine shell is arranged above the workbench, an impeller cavity is formed in the machine shell, an impeller main shaft is arranged in the impeller cavity, a draught fan upper shell is arranged above the machine shell, a drainage groove is formed in the connecting position of the draught fan upper shell and the machine shell, a flange supporting frame is arranged in front of the draught fan upper shell, and a dust filtering mechanism is detachably arranged on the flange supporting frame. An air inducing cavity shell is detachably arranged on the front side of the impeller cavity, a dustproof hole plate is detachably arranged on the air inducing cavity shell, the dust filtering mechanism comprises installation supporting frames detachably arranged on the flange supporting frame, steel filter screens are detachably arranged on the multiple sets of installation supporting frames, falling balls are arranged on the connecting lines, and the multiple falling balls are located between the steel filter screens. A shell plate is detachably arranged at the bottom of the dust filtering shell, a plurality of dust collecting boxes are arranged on the shell plate, and when the fan device of the shaft furnace pressurizing machine is used, the fan device has the dust filtering function.

The utility model discloses a numerical control machine tool with cleaning function, wherein including article main part, the lateral surface mounting of article main part is provided with liquid storage bucket, the lateral surface mounting of liquid storage bucket is provided with controller, the lateral surface mounting of liquid storage bucket is provided with pressurizer, the lateral surface mounting of pressurizer is provided with output pipe. When the user needs to use and clean the numerical control machine tool, the user needs to pour the cleaning fluid into the liquid storage bucket, then needs to open the pressurizer through the controller, after the pressurizer starts, the output pipe can output the cleaning fluid, the water outlet assembly can output through the distribution plate, finally through the setting of the liquid outlet head, the cleaning fluid can flow and clean on the article main part, then needs to push the handle, after the handle is pushed, the cleaning plate and the cleaning head can be pushed, therefore the user can use and clean the numerical control machine tool.