CN111977851A - Nuclear power generator inner cooling water treatment facilities - Google Patents
Nuclear power generator inner cooling water treatment facilities Download PDFInfo
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- CN111977851A CN111977851A CN202010861412.XA CN202010861412A CN111977851A CN 111977851 A CN111977851 A CN 111977851A CN 202010861412 A CN202010861412 A CN 202010861412A CN 111977851 A CN111977851 A CN 111977851A
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- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F9/00—Multistage treatment of water, waste water or sewage
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- H—ELECTRICITY
- H02—GENERATION; CONVERSION OR DISTRIBUTION OF ELECTRIC POWER
- H02K—DYNAMO-ELECTRIC MACHINES
- H02K9/00—Arrangements for cooling or ventilating
- H02K9/19—Arrangements for cooling or ventilating for machines with closed casing and closed-circuit cooling using a liquid cooling medium, e.g. oil
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- H—ELECTRICITY
- H02—GENERATION; CONVERSION OR DISTRIBUTION OF ELECTRIC POWER
- H02K—DYNAMO-ELECTRIC MACHINES
- H02K9/00—Arrangements for cooling or ventilating
- H02K9/26—Structural association of machines with devices for cleaning or drying cooling medium, e.g. with filters
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- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F1/00—Treatment of water, waste water, or sewage
- C02F1/001—Processes for the treatment of water whereby the filtration technique is of importance
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- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F1/00—Treatment of water, waste water, or sewage
- C02F1/42—Treatment of water, waste water, or sewage by ion-exchange
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- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F1/00—Treatment of water, waste water, or sewage
- C02F1/44—Treatment of water, waste water, or sewage by dialysis, osmosis or reverse osmosis
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- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F1/00—Treatment of water, waste water, or sewage
- C02F1/42—Treatment of water, waste water, or sewage by ion-exchange
- C02F2001/425—Treatment of water, waste water, or sewage by ion-exchange using cation exchangers
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- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F2101/00—Nature of the contaminant
- C02F2101/10—Inorganic compounds
- C02F2101/20—Heavy metals or heavy metal compounds
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- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F2103/00—Nature of the water, waste water, sewage or sludge to be treated
- C02F2103/02—Non-contaminated water, e.g. for industrial water supply
- C02F2103/023—Water in cooling circuits
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- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F2209/00—Controlling or monitoring parameters in water treatment
- C02F2209/06—Controlling or monitoring parameters in water treatment pH
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- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F2209/00—Controlling or monitoring parameters in water treatment
- C02F2209/40—Liquid flow rate
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- Engineering & Computer Science (AREA)
- Power Engineering (AREA)
- Life Sciences & Earth Sciences (AREA)
- Hydrology & Water Resources (AREA)
- Environmental & Geological Engineering (AREA)
- Water Supply & Treatment (AREA)
- Chemical & Material Sciences (AREA)
- Organic Chemistry (AREA)
- Separation Using Semi-Permeable Membranes (AREA)
Abstract
The invention relates to a nuclear power generator inner cooling water treatment device, which filters and sieves the nuclear power generator inner cooling water through a membrane component, wherein an inlet isolation door (10) is connected with a generator inner cooling water bypass (1), an outlet isolation door (22) of the device is connected with a nuclear power inner cooling water return pipeline (3), and finally the nuclear power inner cooling water return pipeline returns to the bottom of a nuclear power generator inner cooling water tank (8). The device can stably control the conductivity of cold water in the generator of the nuclear power unit, the pH value reaches the national standard, the content of copper ions is the lowest, the insulativity of the nuclear power generator unit is improved to the maximum extent, copper corrosion is inhibited, and the device has the advantages of simple and convenient operation, certain automation degree and capability of automatically running under the unattended condition for a long time.
Description
The technical field is as follows:
the invention relates to a nuclear power generator inner cooling water treatment device.
Background art:
the water-cooled generator has the characteristics of large single-machine capacity, small volume, light weight and the like, so the water-cooled generator is widely applied to large-scale generator sets. In order to prevent accidents caused by poor quality of internal cooling water, a great deal of research is carried out on the internal cooling water quality and the corrosion mechanism and the corrosion prevention method of copper at home and abroad, and the conclusion is obtained: a. the lower the conductivity of the inner cooling water is, the better the electrical insulating property is, and the insulation faults such as electrical flashover and the like can not occur; the root cause of copper corrosion is the presence of dissolved oxygen and dissolved carbon dioxide in the cold water, and in addition, the divalent copper ions generated during the corrosion process have an accelerating effect on the corrosion; c. corrosion products enter internal cooling water and are blocked by a generator magnetic field in the stator bar to be deposited, so that the hollow lead can be gradually blocked by copper corrosion products or the flow area is reduced, and the temperature rise and even burning loss of a generator coil are caused.
The hollow conductor of the water-cooled generator is generally made of industrial pure copper. The corrosion rate of pure copper in oxygen-free water is very low, only 10-4g/(m2H) of the order of magnitude. The water is slightly acidic due to the carbon dioxide and dissolved oxygen contained in the cold water of the phase modifier, and the corrosion rate of copper is greatly increased in the presence of oxygen. This is because the free carbon dioxide in the water damages the protective film on the copper surface, and the amount of copper elution gradually increases as the unit operation time becomes longer. When the copper content of the internal cooling water system rises faster and higher, the internal cooling water system in the stator bar is proved to have serious electrochemical corrosion. The corroded copper pipe surface is exposed out of the color of the matrix copper alloy, but has no metallic luster, the surface is basically flat or slightly uneven, the pipe wall is bright and fresh and is thinned, and the shape of uniform corrosion is formed.
In addition, an important characteristic of electrochemical corrosion is that copper corrosion products are accumulated at a low potential, only a small amount of the corrosion products are attached to the surface of the pipe wall of a corrosion part, and most of the corrosion products fall off from the pipe wall and enter a cooling medium. The hollow lead wire is gradually blocked by copper oxide or the flow area is reduced due to the deposition in the stator bar by the magnetic field of the generator, so that the temperature of the stator coil is increased, particularly, some copper scale is stripped off during the starting and stopping of the unit and can block the flow part of the bar, and the blocked coil or the iron core is increased in temperature and even burnt. Its harm has two points: generally, the corrosion rate of copper increases rapidly with increasing temperature. Thus, the coil temperature increases, which can lead to accelerated corrosion of the copper. If the control is not performed as early as possible, the generator bar is damaged due to local overheating, and the serious condition is that insulation breakdown causes grounding accidents. Therefore, controlling the corrosion of copper and preventing the deposition of copper corrosion products is an important measure to ensure safe operation of the generator.
The invention content is as follows:
the invention aims to provide a nuclear power generator inner cooling water treatment device which is simple in structure and low in cost, can achieve the advantages of lowest electrical conductivity, moderate pH value and lowest copper ion content of inner cooling water, improves the insulativity of a nuclear power generator set to the maximum extent and has long running period. The technical scheme of the invention is as follows: a nuclear power generator inner cooling water treatment device comprises a membrane component and an ion exchanger to form a deionization purification system, the membrane component is used for filtering and screening the nuclear power generator inner cooling water, an inlet isolation door (10) is connected with a generator inner cooling water bypass (1), and an outlet isolation door (22) is connected with the bottom of a nuclear power generator inner cooling water tank (8) through an outlet pipeline (25). The inlet pressure gauge (12) is arranged on an inlet pipeline (35), and the inlet pipeline (35) is connected with the inlet filter (11), the inlet turbine flowmeter (14) and the glass rotameter (15) and enters the membrane module (17) through the circulating pump (16). An inlet turbine flowmeter (14) and a glass rotameter (15) which are arranged on an inlet pipeline (35) display the inflow and inflow states, the inlet turbine flowmeter (14) transmits an electronic signal to a controller (26), cold water in the nuclear power generator is filtered by a membrane assembly (17) and then returns to a cold water tank (8) in the nuclear power generator through an outlet filter (21) and an outlet pipeline (25), an outlet pressure gauge (20) is arranged on the outlet pipeline (25) to display the running state, the cold water in the nuclear power generator intercepted by the membrane assembly (17) enters an ion exchanger (19) on the corresponding side through a circulating flowmeter (18) to carry out ion adsorption, the water outlet of the ion exchanger (19) enters the inlet of a circulating pump (16) again through a resin catcher (23) and then is filtered and circulated through the membrane assembly (17), the cold water in the nuclear power generator is sampled on line through an inlet sampling door (13) on an inlet pipeline (35), and the online monitoring data is transmitted to a controller (26) in real time through an online sampling flowmeter (33), a conductivity electrode and a pH electrode of an online two-in-one instrument (27) in sequence.
An online two-in-one instrument (27) in the alkalization control cabinet is in communication connection with a controller (26), cold water in the nuclear power generator passes through an inlet sampling door (13) on an inlet pipeline (35) and sequentially passes through an online sampling flowmeter (33), the conductivity electrode and the pH electrode of the on-line two-in-one instrument (27) are used for on-line data monitoring, the on-line monitoring data are transmitted to the controller (26) by the on-line two-in-one instrument (27), after the controller (26) compares the on-line monitoring data, the dosing pump (28) is intelligently regulated and controlled, the sodium hydroxide solution in the dissolving box (29) is diluted in the buffer pool (30) by the dosing pump (28) and then is added into the outlet pipeline (25) through the sampling backwater door (32), the outlet pipeline (25) returns to the bottom of the cold water tank (8) in the nuclear power generator through the nuclear power inner cooling water return pipeline (3).
The controller (26) can select different sampling water qualities by controlling the sampling switching valve (34) to switch the inlet sampling gate (13) and the outlet sampling gate (24).
The controller (26) controls the water replenishing electromagnetic valve (31) to replenish water to the medicine dissolving box (29), thereby simplifying the medicine dissolving operation steps.
The principle of the invention is as follows:
the nuclear power generator internal cooling water treatment device is used for filtering macromolecular particles in the nuclear power generator internal cooling water by utilizing the selective filtering principle of a membrane component (17), and then performing circulating adsorption through ion exchange resin. The alkalization control cabinet is used for adding a sodium hydroxide solution with a certain concentration to improve the pH value of a cold water system in the nuclear power generator so as to inhibit the copper corrosion phenomenon of the cold water system in the nuclear power generator. Therefore, the water quality of the cold water system in the nuclear power generator is kept in a qualified running state, and the safe, economic and stable running of the unit is guaranteed.
The nuclear power generator internal cooling water treatment device comprises a membrane component and an ion exchanger to form a deionization purification system, the membrane component is used for filtering and screening the nuclear power generator internal cooling water, an inlet isolation door (10) is connected with a generator internal cooling water bypass (1), an outlet isolation door (22) is connected with a nuclear power internal cooling water return pipeline (3), and finally the nuclear power generator internal cooling water return pipeline returns to the bottom of a nuclear power generator internal cooling water tank (8). The inlet pressure gauge (12) is arranged on an inlet pipeline (35), and the inlet pipeline (35) is connected with the inlet filter (11), the inlet turbine flowmeter (14) and the glass rotameter (15) and enters the membrane module (17) through the circulating pump (16). The water inlet flow and the water inlet state are displayed by an inlet turbine flowmeter (14) and a glass rotameter (15) which are arranged on an inlet pipeline (35), the inlet turbine flowmeter (14) transmits an electronic signal to a controller (26), cold water in the nuclear power generator is filtered by a membrane assembly (17) and then returns to a cold water tank (8) in the nuclear power generator through an outlet pipeline (25) by an outlet filter (21), and an outlet pressure gauge (20) is arranged on the outlet pipeline (25) to display the running state of the device. The method comprises the following steps that cold water in the nuclear power generator intercepted by a membrane assembly (17) enters an ion exchanger (19) on the corresponding side through a circulating flow meter (18) to be subjected to ion adsorption, water discharged from the ion exchanger (19) reenters an inlet of a circulating pump (16) through a resin catcher (23), filtration and circulation are carried out through the membrane assembly (17) again, the cold water in the nuclear power generator is subjected to online sampling through an inlet sampling door (13) on an inlet pipeline (35), and online monitoring data are transmitted to a controller (26) in real time sequentially through an online sampling flow meter (33) and a conductivity electrode and a pH electrode of an online two-in-one instrument (27).
An online two-in-one instrument (27) in the alkalization control cabinet is in communication connection with the controller (26), online monitoring data are transmitted to the controller (26) by the online two-in-one instrument (27), the dosing pump (28) is controlled by the controller (26) according to the online monitoring data, and sodium hydroxide solution with certain concentration is added into the outlet pipeline (25) by the dosing pump (28) through the sampling backwater door (32).
Cold water in the nuclear power generator enters from an inlet sampling door (13), sequentially passes through an online sampling flowmeter (33), online data monitoring is carried out on a conductance electrode and a pH electrode of an online two-in-one instrument (27), the online monitoring data are transmitted to a controller (26) by the online two-in-one instrument (27), after the online monitoring data are compared by the controller (26), an intelligent regulation and control are carried out on a dosing pump (28), sodium hydroxide solution in a dissolving tank (29) is diluted by the dosing pump (28) in a buffer pool (30) and then is added into an outlet pipeline (25) through a sampling return water door (32), and finally the cold water enters into a cold water tank (8) in the nuclear power generator to complete the process of controlling the alkalization of the cold water in the nuclear power generator once.
And according to the actual running condition of the cold water in the nuclear power generator, when the external interference of the cold water in the nuclear power generator is overlarge, the running mode is switched, the external circulation flow is increased, the processing speed is increased, and the external interference factor is reduced. And meanwhile, two circulating pumps (16) are arranged for one standby, so that the standby circulating pump can be automatically switched when the main circulating pump is abnormal. And the safe and normal operation is ensured.
The invention has the technical effects that:
the device disclosed by the invention is used for filtering insoluble solid copper and other anions and cations existing in a cold water system in a generator of a nuclear power unit by using a selective filtering principle of a membrane component (17) and carrying out adsorption exchange on the copper ions and other ions by using an ion exchange mode of ion exchange resin, so that the aim of purifying the cold water in the nuclear power generator is fulfilled. And adding sodium hydroxide solution with certain concentration into an alkalization control system like a nuclear power generator cold water system for alkalization treatment. The controller (26) is used for carrying out automatic adjustment control, so that the pH value of online monitoring data of cold water in the nuclear power generator is controlled to be 7.00-9.00; the conductivity is within the range of 0-2.00 mu s/cm. The nuclear power generator internal cooling water treatment device can automatically operate according to on-line monitoring data, and adjust the operation state according to actual needs.
And according to the actual running condition of the cold water in the nuclear power generator, when the external interference of the cold water in the nuclear power generator is overlarge, the running mode is switched, the external circulation flow is increased, the processing speed is increased, and the external interference factor is reduced. And meanwhile, two circulating pumps (16) are arranged for one standby, so that the standby circulating pump can be automatically switched when the main circulating pump is abnormal. And the safe and normal operation is ensured.
The device has the advantages of simple structure, low cost, lowest conductivity of the inner cooling water, moderate pH value and lowest copper ion content, improves the insulativity of the nuclear power generating set to the maximum extent and has long running period. The method has the advantages of simple process, convenient operation and certain degree of automation.
Description of the drawings:
FIG. 1 is a schematic diagram of the connection of the device of the invention in a cold water system in a nuclear power generator.
FIG. 2 is a schematic diagram of the connection of the deionization system according to the present invention.
FIG. 3 is a schematic view of the alkalization control system connection according to the present invention.
The specific implementation mode is as follows:
as shown in figure 2, the nuclear power generator internal cooling water treatment device comprises a membrane component and an ion exchanger which form a deionization purification system, the nuclear power generator internal cooling water is filtered and screened by the membrane component, an inlet isolation door 10 is connected with a generator internal cooling water bypass 1, an outlet isolation door 22 is connected with the bottom of a nuclear power generator internal cooling water tank 8 by an outlet pipeline 25, an inlet pressure gauge 12 is arranged on an inlet pipeline 35, the inlet pipeline 35 is connected with an inlet filter 11, an inlet turbine flowmeter 14 and a glass rotameter 15 and enters the membrane component 17 through a circulating pump 16, the inlet turbine flowmeter 14 and the glass rotameter 15 which are arranged on the inlet pipeline 35 display the water inlet flow and the water inlet state, the inlet turbine flowmeter 14 transmits an electronic signal to a controller 26, the nuclear power generator internal cooling water is filtered by the membrane component 17 and then returns to the nuclear power generator internal cooling water tank 8 through the outlet pipeline 25 by the outlet filter 21, an outlet pressure gauge 20 is arranged on an outlet pipeline 25 to display the running state of the device, cold water in the nuclear power generator intercepted by the membrane assembly 17 enters the ion exchanger 19 on the corresponding side through the circulating flow meter 18 to be subjected to ion adsorption, water discharged from the ion exchanger 19 reenters the inlet of the circulating pump 16 through the resin catcher 23, filtration and circulation are carried out through the membrane assembly 17 again, the cold water in the nuclear power generator is subjected to online sampling through the inlet sampling door 13 on the inlet pipeline 35, and online monitoring data are transmitted to the controller 26 in real time through the online sampling flow meter 33 and the conductivity electrode and the pH electrode of the online two-in-one instrument 27 in sequence.
As shown in fig. 3, the on-line two-in-one instrument 27 in the alkalization control cabinet is in communication connection with the controller 26, the cold water in the nuclear power generator passes through the inlet sampling gate 13 on the inlet pipeline 35, sequentially passes through the on-line sampling flow meter 33, the conductivity electrode and the pH electrode of the on-line two-in-one instrument 27 perform on-line data monitoring, the on-line monitoring data is transmitted to the controller 26 by the on-line two-in-one instrument 27, the controller 26 compares the on-line monitoring data, and then intelligently controls the dosing pump 28, the sodium hydroxide solution in the dissolving tank 29 is diluted by the dosing pump 28 in the buffer tank 30 and then is added into the outlet pipeline 25 through the sampling return water gate 32, and the outlet pipeline 25 returns to the bottom of the cold water tank 8 in the nuclear power generator through the cold water return pipeline 3.
As shown in fig. 2, the controller 26 may switch the inlet sample gate 13 and the outlet sample gate 24 by controlling the sample switching valve 34.
The controller 26 controls the water replenishing solenoid valve 31 to replenish water to the drug dissolving tank 29.
As shown in figure 1, the deionization purification system consists of a membrane component and an ion exchanger, the membrane component is used for filtering and screening cold water in the nuclear power generator, an inlet isolation door 10 is connected with a cold water bypass 1 in the nuclear power generator, and an outlet isolation door 22 is connected with the bottom of a cold water tank 8 in the nuclear power generator through an outlet pipeline 3. The nuclear power generator inner cooling water bypass 1 connected with the nuclear power generator inner cooling water treatment device is positioned between a nuclear power generator inner cooling water system cooler 5 and a nuclear power generator inner cooling water system filter 6. The cold water in the nuclear power generator passes through the cold water pump 4, and then the cold water in the cold water tank 8 in the nuclear power generator passes through the cold water system cooler 5 in the nuclear power generator and the filter 6 in the cold water system in the nuclear power generator in turn to enter the magnet exciting coil 7, and finally returns to the cold water tank 8 in the nuclear power generator. And supplementing demineralized water into the cold water system in the nuclear power generator through the demineralized water supplementing water 9 along with the consumption of the cold water system in the nuclear power generator.
As shown in fig. 2, the inlet pressure gauge 12 is mounted on an inlet line 35, and the inlet line 35 connects the inlet filter 11, the inlet turbine flow meter 14, the glass rotameter 15, and the circulating pump 16 into the membrane module 17. The inlet turbine flowmeter 14 and the glass rotameter 15 which are arranged on an inlet pipeline 35 display the water inlet flow and the water inlet state, the inlet turbine flowmeter 14 transmits an electronic signal to a controller 26, cold water in the nuclear power generator is filtered by a membrane assembly 17 and then returns to a cold water tank 8 in the nuclear power generator through an outlet filter 21 and an outlet pipeline 25, the outlet pipeline 25 is provided with an outlet pressure gauge 20 to display the running state of the device, the cold water in the nuclear power generator, which is intercepted by the membrane assembly 17, enters an ion exchanger 19 on the corresponding side through a circulating flowmeter 18 to carry out ion adsorption, the water discharged from the ion exchanger 19 reenters the inlet of a circulating pump 16 through a resin catcher 23, is filtered and circulated through the membrane assembly 17 again, the cold water in the nuclear power generator is sampled on line through an inlet sampling door 13 on the inlet pipeline 35 and sequentially passes through an on, The conductivity electrode and the pH electrode of the online two-in-one meter 27 transmit online monitoring data to the controller 26 in real time.
As shown in fig. 3, the on-line two-in-one instrument 27 in the alkalization control cabinet is in communication connection with the controller 26, the cold water in the nuclear power generator passes through the inlet sampling gate 13 on the inlet pipeline 35, sequentially passes through the on-line sampling flow meter 33, the conductivity electrode and the pH electrode of the on-line two-in-one instrument 27 perform on-line data monitoring, the on-line monitoring data is transmitted to the controller 26 by the on-line two-in-one instrument 27, the controller 26 compares the on-line monitoring data, and then intelligently controls the dosing pump 28, the sodium hydroxide solution in the dissolving tank 29 is diluted by the dosing pump 28 in the buffer tank 30 and then is added into the outlet pipeline 25 through the sampling return water gate 32, and the outlet pipeline 25 returns to the bottom of the cold water tank 8 in the nuclear power generator through the cold water return pipeline 3.
Cold water in the nuclear power generator enters from the inlet sampling door 13 and sequentially passes through the online sampling flowmeter 33, online data monitoring is carried out on a conductance electrode and a pH electrode of the online two-in-one instrument 27, the online monitoring data are transmitted to the controller 26 by the online two-in-one instrument 27, after the controller 26 compares the online monitoring data, intelligent regulation and control are carried out on the dosing pump 28, the sodium hydroxide solution in the dissolving tank 29 is added into the outlet pipeline 25 by the dosing pump 28 through the sampling return water door 32, and finally the sodium hydroxide solution enters the cold water tank 8 in the nuclear power generator to complete the process of primary cold water alkalization control in the nuclear power generator.
After the cold water in the nuclear power generator is circulated for many times, the controller 26 enables the conductivity of the cold water in the nuclear power generator to reach a set range under the controllable condition, and ensures that the conductivity and the pH value of the cold water in the nuclear power generator fluctuate within a reasonable range, so that the cold water in the nuclear power generator is always in an optimal state, and the consumption of a whole set of medicines and the loss of resin reach the lowest.
The ion removal system comprises: an inlet filter 11, a flow sensor 14, a glass rotameter 15, a circulating pump 16, a membrane assembly 17, a circulating flow meter 18, an ion exchanger 19, an outlet pressure gauge 20 and an outlet filter 21.
Alkalization control system: an online two-in-one meter 27, a controller 26, a dosing pump 28 and an online sampling flow meter 33.
Claims (4)
1. A nuclear power generator inner cooling water treatment device is characterized in that: the deionization purification system comprises a membrane component and an ion exchanger, cold water in the nuclear power generator is filtered and sieved through the membrane component, an inlet isolation door (10) is connected with a cold water bypass (1) in the generator, an outlet isolation door (22) is connected with the bottom of a cold water tank (8) in the nuclear power generator through an outlet pipeline (25), an inlet pressure gauge (12) is installed on an inlet pipeline (35), the inlet pipeline (35) is connected with an inlet filter (11), an inlet turbine flowmeter (14) and a glass rotameter (15) and enters the membrane component (17) through a circulating pump (16), the inlet turbine flowmeter (14) and the glass rotameter (15) which are installed on the inlet pipeline (35) display the inflow and the inflow states, the inlet turbine flowmeter (14) transmits electronic signals to a controller (26), the cold water in the nuclear power generator is filtered by the membrane component (17) and then passes through the outlet filter (21) and passes through the outlet pipeline (25) ) Returning to a cold water tank (8) in the nuclear power generator, installing an outlet pressure gauge (20) on an outlet pipeline (25) to display the running state of a device, entering cold water in the nuclear power generator intercepted by a membrane assembly (17) into an ion exchanger (19) on the corresponding side through a circulating flow meter (18) for ion adsorption, re-entering the outlet water of the ion exchanger (19) into an inlet of a circulating pump (16) through a resin catcher (23), performing filtration circulation again through the membrane assembly (17), performing online sampling on the cold water in the nuclear power generator through an inlet sampling door (13) on an inlet pipeline (35), and transmitting online monitoring data to a controller (26) in real time through an online sampling flow meter (33), a conductivity electrode and a pH electrode of an online two-in-one instrument (27).
2. The internal cooling water treatment device of the nuclear power generator as claimed in claim 1, which is characterized in that: an online two-in-one instrument (27) in the alkalization control cabinet is in communication connection with a controller (26), cold water in the nuclear power generator passes through an inlet sampling door (13) on an inlet pipeline (35) and sequentially passes through an online sampling flowmeter (33), the conductivity electrode and the pH electrode of the on-line two-in-one instrument (27) are used for on-line data monitoring, the on-line monitoring data are transmitted to the controller (26) by the on-line two-in-one instrument (27), after the controller (26) compares the on-line monitoring data, the dosing pump (28) is intelligently regulated and controlled, the sodium hydroxide solution in the dissolving box (29) is diluted in the buffer pool (30) by the dosing pump (28) and then is added into the outlet pipeline (25) through the sampling backwater door (32), the outlet pipeline (25) returns to the bottom of the cold water tank (8) in the nuclear power generator through the nuclear power inner cooling water return pipeline (3).
3. The internal cooling water treatment device of the nuclear power generator as claimed in claim 1, which is characterized in that: the controller (26) can switch the inlet sample gate (13) and the outlet sample gate (24) by controlling the sample switching valve (34).
4. The internal cooling water treatment device of the nuclear power generator as claimed in claim 1, which is characterized in that: the controller (26) controls the water replenishing electromagnetic valve (31) to replenish water to the dissolved medicine box (29).
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| CN202010861412.XA CN111977851A (en) | 2020-09-11 | 2020-09-11 | Nuclear power generator inner cooling water treatment facilities |
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| CN202010861412.XA CN111977851A (en) | 2020-09-11 | 2020-09-11 | Nuclear power generator inner cooling water treatment facilities |
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| CN111977851A true CN111977851A (en) | 2020-11-24 |
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| EP2429956A1 (en) * | 2009-04-16 | 2012-03-21 | Swedish Metallurgy and Mining AB | Scaling, deposition and general copper corrosion elimination in closed cooling water systems |
| CN102432133A (en) * | 2011-12-15 | 2012-05-02 | 宁夏电力公司电力科学研究院 | Automatic alkalization treatment device for inner cooling water of power plant |
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