CN213986129U - Nuclear island equipment cooling water system material corrodes analogue means - Google Patents
Nuclear island equipment cooling water system material corrodes analogue means Download PDFInfo
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- CN213986129U CN213986129U CN202022767607.6U CN202022767607U CN213986129U CN 213986129 U CN213986129 U CN 213986129U CN 202022767607 U CN202022767607 U CN 202022767607U CN 213986129 U CN213986129 U CN 213986129U
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- circulating water
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- cooling water
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- 239000000498 cooling water Substances 0.000 title claims abstract description 32
- 239000000463 material Substances 0.000 title claims abstract description 30
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 148
- 230000007797 corrosion Effects 0.000 claims abstract description 49
- 238000005260 corrosion Methods 0.000 claims abstract description 49
- 230000001105 regulatory effect Effects 0.000 claims abstract description 47
- 238000004088 simulation Methods 0.000 claims abstract description 17
- 229910000975 Carbon steel Inorganic materials 0.000 claims abstract description 13
- 239000010962 carbon steel Substances 0.000 claims abstract description 13
- 238000012806 monitoring device Methods 0.000 claims abstract description 10
- 239000010935 stainless steel Substances 0.000 claims description 20
- 229910001220 stainless steel Inorganic materials 0.000 claims description 20
- 238000001514 detection method Methods 0.000 claims description 18
- 239000007788 liquid Substances 0.000 claims description 10
- 238000009423 ventilation Methods 0.000 claims description 9
- 239000010963 304 stainless steel Substances 0.000 claims description 6
- 229910000589 SAE 304 stainless steel Inorganic materials 0.000 claims description 6
- 230000001276 controlling effect Effects 0.000 claims description 5
- 238000005485 electric heating Methods 0.000 claims description 5
- -1 polytetrafluoroethylene Polymers 0.000 claims description 4
- 229920001343 polytetrafluoroethylene Polymers 0.000 claims description 4
- 239000004810 polytetrafluoroethylene Substances 0.000 claims description 4
- 238000003466 welding Methods 0.000 claims description 2
- 238000011160 research Methods 0.000 abstract description 8
- 230000008859 change Effects 0.000 abstract description 5
- 230000007246 mechanism Effects 0.000 abstract description 3
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 6
- 238000000034 method Methods 0.000 description 6
- 229910052760 oxygen Inorganic materials 0.000 description 6
- 239000001301 oxygen Substances 0.000 description 6
- 238000012360 testing method Methods 0.000 description 6
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 4
- 230000008569 process Effects 0.000 description 4
- 238000000746 purification Methods 0.000 description 4
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 description 3
- 229910052802 copper Inorganic materials 0.000 description 3
- 239000010949 copper Substances 0.000 description 3
- 238000002347 injection Methods 0.000 description 3
- 239000007924 injection Substances 0.000 description 3
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 2
- 150000001450 anions Chemical class 0.000 description 2
- 230000004888 barrier function Effects 0.000 description 2
- 150000001768 cations Chemical class 0.000 description 2
- 239000012535 impurity Substances 0.000 description 2
- 229910052757 nitrogen Inorganic materials 0.000 description 2
- 239000004809 Teflon Substances 0.000 description 1
- 229920006362 Teflon® Polymers 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 229910052742 iron Inorganic materials 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
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- Preventing Corrosion Or Incrustation Of Metals (AREA)
Abstract
A material corrosion simulation device for a cooling water system of nuclear island equipment comprises a circulating water tank, wherein a circulating water outlet is formed in the bottom of the circulating water tank, the circulating water outlet is connected with a carbon steel pipeline through a pipeline and flows back to the top of the circulating water tank, a booster pump, a first hanging piece bypass flow regulating valve, a first hanging piece bypass rotor flowmeter, a pipeline inner wall corrosion condition monitoring device, a first bypass corrosion hanging piece device and the carbon steel pipeline are sequentially arranged on the pipeline, and a hanging piece bypass water return valve is arranged on the carbon steel pipeline; the utility model discloses can simulate equipment cooling water system operation condition simultaneously to the accurate regulation and control of quality of water parameter more truthfully for the water quality change law and the material corrosion mechanism of the different operation stages of this system of research.
Description
Technical Field
The utility model relates to a material corrodes protection research technical field, in particular to nuclear island equipment cooling water system material corrodes analogue means.
Background
The nuclear island equipment cooling water system of the nuclear power station provides cooling water for various safety-related and non-safety-related systems of the nuclear island, and the system provides an intermediate barrier which can be monitored between equipment containing radioactive fluid and a final hot trap, and is a necessary system for normal operation of the nuclear power station. Once fouling or plugging of various heat exchangers in the system occurs, the heat exchange efficiency is seriously reduced, and material corrosion can cause equipment leakage to damage the barrier and even cause shutdown.
At present, the problem that the content of iron in equipment cooling water exceeds the standard is solved, which shows that the problems of carbon steel corrosion and corrosion product shedding are not solved; the content of copper in the cooling water of the equipment exceeds the standard, the copper in the system has corrosion phenomenon, and the corrosion leakage condition can occur, and the problem of copper corrosion in the system needs to be emphasized. When researching the water quality change rule and the material corrosion mechanism, the water quality parameters of the circulating water need to be accurately controlled, and parameters such as the conductivity of the circulating water, the content of impurities, anions and cations, the dissolved oxygen, the turbidity and the like are adjusted according to research requirements; in addition, the water flow speed on the surface of the material in the system is in the range of 1-4m/s, the water flow state of different parts in the system is different, and simulation equipment used in the experiment needs to simulate the parameters according to the field working conditions.
Disclosure of Invention
In order to overcome the defects of the prior art, the utility model aims to provide a nuclear island equipment cooling water system material corrodes analogue means can simulate equipment cooling water system operation condition more really and simultaneously to the accurate regulation and control of quality of water parameter for the water quality change law and the material corrosion mechanism of the different operation stages of this system of research.
In order to realize the purpose, the utility model discloses a technical scheme is:
a material corrosion simulation device for a cooling water system of nuclear island equipment comprises a circulating water tank 1, wherein a circulating water outlet is formed in the bottom of the circulating water tank 1, the circulating water outlet is connected with a carbon steel pipeline 28 through a pipeline and flows back to the top of the circulating water tank 1, a booster pump 25, a first coupon bypass flow regulating valve 8, a first coupon bypass rotor flowmeter 10, a pipeline inner wall corrosion condition monitoring device 15, a first bypass corrosion coupon device 14 and a carbon steel pipeline 28 are sequentially arranged on the pipeline, and a coupon bypass return water valve 17 is arranged on the carbon steel pipeline 28;
a second coupon bypass is led out from a pipeline between the first coupon bypass flow regulating valve 8 and the first coupon bypass rotor flowmeter 10, and the second coupon bypass is sequentially provided with a second coupon bypass flow regulating valve 9, a second coupon bypass rotor flowmeter 11, a second bypass corrosion coupon device 12 and a second coupon bypass return water valve 16 and then is converged with a carbon steel pipeline 28. 29
The circulating water circulation system is characterized in that a water filling port valve 29, a thermometer 4, a cooling water ring pipe inlet valve 5 and a cooling water ring pipe outlet valve 6 are arranged at the top of the circulating water tank 1, a magnetic turning plate liquid level meter 7 used for observing the liquid level of the circulating water tank 1 is arranged on one side of the circulating water tank 1, a constant-temperature electric heating device 3 used for controlling the temperature of circulating water is arranged in the circulating water tank 1, a ventilation ring pipe 27 is arranged at the bottom of the water tank, and the ventilation ring pipe 27 is connected with a ventilation valve 26 arranged on the outer side of the circulating water tank 1.
A flow regulating bypass, a water quality purifying bypass and a water quality detecting bypass are led out from a pipeline between the pipeline booster pump 25 and the first hanging piece bypass flow regulating valve 8, and all three bypass pipelines are provided, and part of circulating water returns to the circulating water tank 1 after being converged by the three bypass pipelines;
the flow regulating bypass pipeline is provided with a flow regulating bypass flow regulating valve 18, and the water quality purifying bypass pipeline is provided with a purifying device inlet valve 19, a water quality purifying device 21 and a purifying device outlet valve 20; and the water quality detection bypass pipeline is provided with a water quality detection device inlet valve 22, a water quality detection device 24 and a water quality detection device outlet valve 23.
Pipeline inner wall corrosion conditions monitoring devices 15 includes first stainless steel flange 34, second stainless steel flange 36, and the stainless steel connecting pipe phase-match of flange size and system use, welded connection between flange and the pipeline, be provided with polytetrafluoroethylene between first stainless steel flange 34 and the second stainless steel flange 36 and make the connecting piece.
The polytetrafluoroethylene connecting piece comprises a bottom connecting flange 30, a first middle connecting part 31, a second connecting part 32 and a top connecting flange 33, wherein a hole is formed in the middle of the connecting piece, and the size of the hole is matched with the size of a pipe section for observing the corrosion condition of the inner wall of the pipeline.
The first stainless steel connecting flange 34 and the second stainless steel connecting flange 36 are pressed tightly by 4 bolts 35.
The pipeline is a 304 stainless steel pipe, and the circulating water tank 1 is made of 304 stainless steel.
A use method of a material corrosion simulation device of a cooling water system of nuclear island equipment comprises the following steps;
opening a water filling port valve 29 at the top of a circulating water tank 1, filling demineralized water into a system, observing the liquid level of the water tank according to a magnetic turning plate liquid level meter 7 on the water tank, opening a power supply of a constant-temperature electric heating device 3, heating the circulating water to a target temperature, hanging a test piece of a research material in a first bypass corrosion hanging piece device 14, opening a first hanging piece bypass flow regulating valve 8, a flow regulating bypass flow regulating valve 18 and a hanging piece bypass return water valve 17, starting a booster pump 25, regulating the opening degrees of the first hanging piece bypass flow regulating valve 8, the flow regulating bypass flow regulating valve 18 and the hanging piece bypass return water valve 17, and regulating a first hanging piece bypass rotameter 10 to a set value;
when the material corrosion behavior research under two flow speed conditions needs to be carried out simultaneously, a test piece is hung in the second bypass corrosion coupon device 12, the second coupon bypass flow regulating valve 9 and the second coupon bypass return water valve 16 are opened, and the flow of the second coupon bypass rotameter 11 is regulated to a target value by controlling the opening of the valve;
when the water quality of the circulating water needs to be purified in the operation process of the device, an inlet valve 19 of the purifying device and an outlet valve 20 of the purifying device are opened, so that part of the circulating water flows through a water quality purifying device 21 and returns to the circulating water tank 1; when the water quality needs to be measured in the operation process of the device, opening an inlet valve 22 of the water quality detection device and an outlet valve 20 of the water quality detection device, so that a small part of circulating water flows through the water quality detection device 24;
during the test, when the dissolved oxygen content in the circulating water needs to be adjusted, the vent valve 26 and the water injection valve 29 are opened, and nitrogen or oxygen is injected into the circulating water through the vent loop 27.
The utility model has the advantages that:
the experimental device can truly simulate the actual operation condition of the cooling water system of the nuclear island equipment.
2 the experimental device can accurately control various parameters in the circulating water, including circulating water flow rate, circulating water conductivity, dissolved oxygen, impurity anion and cation content and the like, and further research the influence of the parameters on material corrosion in the system.
3 the utility model discloses in be provided with pipeline inner wall corrosion conditions monitoring devices, the device conveniently assembles and observes, can be used for studying the pipeline inner wall corrosion products and form or the condition of droing.
Drawings
Fig. 1 is an overall schematic view of the present invention.
FIG. 2 is a front view of the corrosion monitoring device for the inner wall of the pipeline.
FIG. 3 is a top view of the corrosion monitoring device for the inner wall of the pipeline.
Detailed Description
The present invention will be described in further detail with reference to examples.
As shown in fig. 1: a laboratory simulation device for researching the corrosion behavior of a material of a cooling water system of nuclear island equipment is used for researching the water quality change rule of the cooling water system of the nuclear island equipment and the influence of the water quality change on the corrosion of the material. The simulation device comprises a circulating water tank 1, circulating water is led out from the circulating water tank 1, is pressurized by a pipeline booster pump 25, flows through a first coupon bypass flow regulating valve 8, a first coupon bypass rotor flow meter 10, a pipeline inner wall corrosion condition monitoring device 15, a first bypass corrosion coupon device 14, a carbon steel pipeline 28 and a coupon bypass water return valve 17, and then flows back to the circulating water tank 1. A second coupon bypass is led out between the first coupon bypass flow regulating valve 8 and the first coupon bypass rotor flowmeter 10, and the second coupon bypass is sequentially provided with a second coupon bypass flow regulating valve 9, a second coupon bypass rotor flowmeter 11, a second bypass corrosion coupon device 12 and a second coupon bypass return water valve 16. The parts are connected by 304 stainless steel pipes.
The whole circulating water tank 1 is made of 304 stainless steel, a water filling port valve 29, a thermometer 4, a cooling water ring pipe inlet valve 5 and a cooling water ring pipe outlet valve 6 are arranged at the top of the circulating water tank 1, and a magnetic turning plate liquid level meter 7 for observing the liquid level of the water tank is arranged on one side of the water tank. A constant temperature electric heating device 3 is arranged in the water tank and used for controlling the temperature of the circulating water. The bottom of the water tank is provided with a ventilation ring pipe 27, and a ventilation valve 26 is connected outside the ventilation ring pipe.
A flow regulating bypass, a water quality purifying bypass and a water quality detecting bypass are led out from a pipeline between a pipeline booster pump 25 and a first hanging piece bypass flow regulating valve 8 of the simulation device, and part of circulating water returns to a circulating water tank 1 after flowing through the three bypasses. The flow regulating bypass introduces water from between the pipeline booster pump 25 and the first hanging piece bypass flow regulating valve 8 of the simulation device, and returns to the circulating water tank 1 after passing through the flow regulating bypass flow regulating valve 18. The water quality purification bypass introduces water from between a pipeline booster pump 25 and a first hanging piece bypass flow regulating valve 8 of the simulation device, and returns to the circulating water tank 1 after flowing through a purification device inlet valve 19, a water quality purification device 21 and a purification device outlet valve 20; the water quality detection bypass introduces water from between a pipeline booster pump 25 and the first hanging piece bypass flow regulating valve 8 of the simulation device, and returns to the circulating water tank 1 after flowing through a water quality detection device inlet valve 22, a water quality detection device 24 and a water quality detection device outlet valve 23.
As shown in fig. 2 and 3: the pipeline inner wall corrosion condition monitoring device 15 comprises a first stainless steel connecting flange 34 and a second stainless steel connecting flange 36, the size of the flange is matched with that of a stainless steel connecting pipeline used by a system, and the flange is connected with the pipeline in a welding mode. A teflon connector is provided between the first 34 and second 36 stainless steel attachment flanges, comprising a bottom attachment flange 30, a first intermediate attachment member 31, a second attachment member 32 and a top attachment flange 33. The middle of the connecting piece is provided with a hole, and the size of the hole is matched with the size of a pipe section for observing the corrosion condition of the inner wall of the pipeline. After the components are assembled in sequence, all parts between the first stainless steel connecting flange 34 and the second stainless steel connecting flange 36 are pressed tightly through 4 bolts 35, and water leakage is avoided.
The use method of the laboratory simulation device for the material corrosion behavior of the cooling water system of the nuclear island equipment comprises the following steps: and opening a water injection port valve 29 at the top of the circulating water tank 1, injecting demineralized water into the system, and observing the liquid level of the water tank according to a magnetic turning plate liquid level meter 7 on the water tank. And (4) turning on a power supply of the constant-temperature electric heating device 3 to heat the circulating water to the target temperature. Hanging a test piece for researching material in the first side-road corrosion hanging piece device 14, opening the first hanging piece bypass flow regulating valve 8, the flow regulating bypass flow regulating valve 18 and the hanging piece bypass return water valve 17, starting the booster pump 25, regulating the opening degrees of the first hanging piece bypass flow regulating valve 8, the flow regulating bypass flow regulating valve 18 and the hanging piece bypass return water valve 17, and regulating the first hanging piece bypass rotameter 10 to a set value. When the material corrosion behavior research under two flow speed conditions needs to be carried out simultaneously, a test piece can be hung in the second bypass corrosion coupon device 12, the second coupon bypass flow regulating valve 9 and the second coupon bypass return water valve 16 are opened, and the flow of the second coupon bypass rotameter 11 is regulated to a target value by controlling the opening of the valve.
When the water quality of the circulating water needs to be purified in the operation process of the device, an inlet valve 19 of the purifying device and an outlet valve 20 of the purifying device are opened, so that part of the circulating water flows through a water quality purifying device 21 and returns to the circulating water tank 1; when the water quality needs to be measured in the operation process of the device, the inlet valve 22 of the water quality detection device and the outlet valve 23 of the water quality detection device are opened, so that a small part of circulating water flows through the water quality detection device 24. During the test, when the dissolved oxygen content in the circulating water needs to be adjusted, the vent valve 26 and the water injection valve 29 are opened, and nitrogen or oxygen is injected into the circulating water through the vent loop 27.
The above is a preferred embodiment of the present invention, but the protection of the present invention is not limited to the above embodiment, and variations and advantages which can be conceived by those skilled in the art are included in the present invention without departing from the spirit and scope of the inventive concept.
Claims (9)
1. The utility model provides a nuclear island equipment cooling water system material corrodes analogue means, a serial communication port, including circulating water tank (1), circulating water tank ()1 bottom is provided with the circulating water export, the circulating water export is through pipe connection carbon steel pipeline (28), flows back to circulating water tank (1) top, booster pump (25), first lacing film bypass flow control valve (8), first lacing film bypass rotor flow meter (10), pipeline inner wall corruption condition monitoring devices (15), first bypass corruption lacing film device (14), carbon steel pipeline (28) have set gradually on the pipeline, set up lacing film bypass return water valve (17) on carbon steel pipeline (28).
2. The material corrosion simulation device for the cooling water system of the nuclear island equipment according to claim 1, wherein a second hanger bypass is led out from a pipeline between the first hanger bypass flow regulating valve (8) and the first hanger bypass rotor flow meter (10), and the second hanger bypass is sequentially provided with a second hanger bypass flow regulating valve (9), a second hanger bypass rotor flow meter (11), a second bypass corrosion hanger device (12) and a second hanger bypass return water valve (16) and then is merged with the carbon steel pipeline (28).
3. The material corrosion simulation device for the cooling water system of the nuclear island equipment according to claim 1, wherein a water filling port valve (29), a thermometer (4), a cooling water loop inlet valve (5) and a cooling water loop outlet valve (6) are arranged at the top of the circulating water tank (1), a magnetic turning plate liquid level meter (7) for observing the liquid level of the circulating water tank (1) is arranged on one side of the circulating water tank (1), a constant temperature electric heating device (3) for controlling the temperature of circulating water is arranged in the circulating water tank (1), a ventilation loop (27) is arranged at the bottom of the tank, and the ventilation loop (27) is connected with a ventilation valve (26) arranged outside the circulating water tank (1).
4. The material corrosion simulation device for the cooling water system of the nuclear island equipment according to claim 1, wherein three bypass pipelines including a flow regulating bypass, a water quality purifying bypass and a water quality detecting bypass are led out from a pipeline between the booster pump (25) and the first hanger bypass flow regulating valve (8), and part of circulating water flows through the three bypass pipelines and returns to the circulating water tank (1) after being converged.
5. The material corrosion simulation device for the cooling water system of the nuclear island equipment according to claim 4, wherein a flow regulating bypass flow regulating valve (18) is arranged on the flow regulating bypass pipeline, and a water quality purifying bypass pipeline is provided with an inlet valve (19) of a purifying device, a water quality purifying device (21) and an outlet valve (20) of the purifying device; and the water quality detection bypass pipeline is provided with a water quality detection device inlet valve (22), a water quality detection device (24) and a water quality detection device outlet valve (23).
6. The material corrosion simulation device for the cooling water system of the nuclear island equipment, according to claim 1, is characterized in that the pipeline inner wall corrosion condition monitoring device (15) comprises a first stainless steel connecting flange (34) and a second stainless steel connecting flange (36), the size of the flange is matched with that of a stainless steel connecting pipeline used by the system, the flange is connected with the pipeline in a welding mode, and a connecting piece made of polytetrafluoroethylene is arranged between the first stainless steel connecting flange (34) and the second stainless steel connecting flange (36).
7. The material corrosion simulator of nuclear island equipment cooling water system according to claim 6, characterized in that the connecting piece made of polytetrafluoroethylene comprises a bottom connecting flange (30), a first middle connecting part (31), a second connecting part (32) and a top connecting flange (33), and the middle of the connecting piece is provided with an opening, and the size of the opening is matched with the size of a pipe section for observing the corrosion condition of the inner wall of the pipeline.
8. The material corrosion simulation device for the cooling water system of the nuclear island equipment as claimed in claim 6, wherein the first stainless steel connecting flange (34) and the second stainless steel connecting flange (36) are compressed by 4 bolts (35).
9. The material corrosion simulator of nuclear island equipment cooling water system according to claim 1, characterized in that the pipeline is 304 stainless steel pipe, and the circulating water tank (1) is made of 304 stainless steel.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202022767607.6U CN213986129U (en) | 2020-11-25 | 2020-11-25 | Nuclear island equipment cooling water system material corrodes analogue means |
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| CN202022767607.6U CN213986129U (en) | 2020-11-25 | 2020-11-25 | Nuclear island equipment cooling water system material corrodes analogue means |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112394023A (en) * | 2020-11-25 | 2021-02-23 | 华能山东石岛湾核电有限公司 | Nuclear island equipment cooling water system material corrosion simulation device and use method thereof |
| CN114577502A (en) * | 2022-03-16 | 2022-06-03 | 国能宁夏供热有限公司 | High-temperature heat supply pipe network heat exchanger scaling simulation test device and use method thereof |
-
2020
- 2020-11-25 CN CN202022767607.6U patent/CN213986129U/en active Active
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112394023A (en) * | 2020-11-25 | 2021-02-23 | 华能山东石岛湾核电有限公司 | Nuclear island equipment cooling water system material corrosion simulation device and use method thereof |
| CN112394023B (en) * | 2020-11-25 | 2024-08-23 | 华能山东石岛湾核电有限公司 | Nuclear island equipment cooling water system material corrosion simulation device and application method thereof |
| CN114577502A (en) * | 2022-03-16 | 2022-06-03 | 国能宁夏供热有限公司 | High-temperature heat supply pipe network heat exchanger scaling simulation test device and use method thereof |
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