CN220205704U - Nuclear power auxiliary electric boiler system - Google Patents
Nuclear power auxiliary electric boiler system Download PDFInfo
- Publication number
- CN220205704U CN220205704U CN202320681128.3U CN202320681128U CN220205704U CN 220205704 U CN220205704 U CN 220205704U CN 202320681128 U CN202320681128 U CN 202320681128U CN 220205704 U CN220205704 U CN 220205704U
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- Prior art keywords
- steam
- water separator
- electric boiler
- nuclear power
- water
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 89
- 238000000926 separation method Methods 0.000 claims abstract description 32
- 230000002209 hydrophobic effect Effects 0.000 claims abstract 4
- 238000005485 electric heating Methods 0.000 claims description 10
- 229920006395 saturated elastomer Polymers 0.000 claims description 10
- 229910001415 sodium ion Inorganic materials 0.000 abstract description 7
- FKNQFGJONOIPTF-UHFFFAOYSA-N Sodium cation Chemical compound [Na+] FKNQFGJONOIPTF-UHFFFAOYSA-N 0.000 description 3
- 230000017525 heat dissipation Effects 0.000 description 3
- 238000010438 heat treatment Methods 0.000 description 3
- 239000002699 waste material Substances 0.000 description 2
- 238000009825 accumulation Methods 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
Abstract
The utility model provides a nuclear power auxiliary electric boiler system which comprises an auxiliary electric boiler, a steam-water separator and a steam heater, wherein a low-pressure steam outlet of the auxiliary electric boiler is connected with the steam-water separator, a separation steam outlet of the steam-water separator is connected with the steam heater, steam separated by the steam-water separator is input into the steam heater, a superheated steam outlet of the steam heater is connected with a steam point for a nuclear power unit, a water outlet end of the steam-water separator is connected with the auxiliary electric boiler through a hydrophobic pipe, and water carried in the steam separated by the steam-water separator flows back to the auxiliary electric boiler through the hydrophobic pipe. The system can ensure that the content of sodium ions in the output steam is less than 10ppb, ensure that the dryness of the steam reaches 100%, and meet the requirement of nuclear power auxiliary steam.
Description
[ field of technology ]
The utility model relates to the technical field of steam generating devices, in particular to a nuclear power auxiliary electric boiler system.
[ background Art ]
The nuclear power auxiliary electric boiler is used as necessary equipment for starting and running of a nuclear power unit, and steam generated by the nuclear power auxiliary electric boiler mainly provides preheating, sealing and the like for the starting of the nuclear power unit, but the nuclear power unit has higher requirements on steam quality, in particular to steam dryness and sodium ion concentration. Wherein, the dryness of the steam is required to be more than 99.9 percent, and the concentration of sodium ions in the steam is required to be lower than 10ppb, etc.
Saturated steam generated by a conventional electric boiler has the humidity of 2% -4%, sodium ion groups contained in the steam can basically meet nuclear power requirements after being treated by a steam-water separator, but the dryness of the steam can generally only reach 99.5%, and the requirements of a nuclear power station can not be met, and a nuclear power auxiliary electric boiler system is provided.
[ utility model ]
The utility model aims to solve the problems in the prior art and provides a nuclear power auxiliary electric boiler system which can enable output steam to meet the requirements of a nuclear power station.
In order to achieve the above purpose, the utility model provides a nuclear power auxiliary electric boiler system, which comprises an auxiliary electric boiler, a steam-water separator and a steam heater, wherein a low-pressure steam outlet of the auxiliary electric boiler is connected with the steam-water separator, a separation steam outlet of the steam-water separator is connected with the steam heater, steam separated by the steam-water separator is input into the steam heater, a superheated steam outlet of the steam heater is connected with a steam point for a nuclear power unit, a water outlet end of the steam-water separator is connected with the auxiliary electric boiler through a drain pipe, and water carried in the steam separated by the steam-water separator flows back to the auxiliary electric boiler through the drain pipe.
Preferably, the inlet of the drain pipe is connected with the water outlet end at the bottom of the steam-water separator, the outlet of the drain pipe is connected with the auxiliary electric boiler, and the inlet end of the drain pipe is higher than the water outlet end of the drain pipe.
Preferably, a drain valve is disposed on the drain pipe.
Preferably, an electric heating pipe is arranged in the steam heater, and saturated steam output by the steam-water separator is changed into superheated steam after being heated by the electric heating pipe.
Preferably, a primary separation device and a secondary separation device are sequentially arranged in the steam-water separator along the conveying direction of steam, a primary steam outlet of the primary separation device is connected to the secondary separation device, a secondary steam outlet of the secondary separation device is communicated with the separation steam outlet, and water outlets of the primary separation device and the secondary separation device are connected to the drain pipe.
Preferably, the saturated steam output from the steam-water separator is changed into superheated steam through the steam heater, and the degree of superheat is controlled to be 3-10 ℃.
The utility model has the beneficial effects that:
1. the low pressure steam itself is free of sodium ions, which are mainly from the water carried in the steam. The utility model adopts a high-efficiency steam-water separator, the separation efficiency can reach 99.5 percent, and the sodium ion content in the steam can be less than 10ppb by removing water in the steam.
2. In the utility model, the steam-water separator is positioned at a high position, and the separated water can be directly returned to the auxiliary electric boiler, so that the waste is avoided.
3. The saturated steam is heated by the steam heater to become superheated steam, and the superheated steam can still keep the superheat degree of more than 1 ℃ even after long-distance transportation, so that the dryness of the steam can reach 100%, and the requirement of nuclear power auxiliary steam is met.
The features and advantages of the present utility model will be described in detail by way of example with reference to the accompanying drawings.
[ description of the drawings ]
FIG. 1 is a schematic diagram of a nuclear power assisted electric boiler system according to the present utility model.
[ detailed description ] of the utility model
Referring to fig. 1, the nuclear power auxiliary electric boiler system comprises an auxiliary electric boiler 1, a steam-water separator 2 and a steam heater 3, wherein a low-pressure steam outlet 11 of the auxiliary electric boiler 1 is connected with the steam-water separator 2, a separation steam outlet 21 of the steam-water separator 2 is connected with the steam heater 3, steam separated by the steam-water separator 2 is input into the steam heater 3, a superheated steam outlet 31 of the steam heater 3 is connected with a steam point for a nuclear power unit, a water outlet end of the steam-water separator 2 is connected with the auxiliary electric boiler 1 through a water drain pipe 22, and water carried in steam separated by the steam-water separator 2 flows back to the auxiliary electric boiler 1 through the water drain pipe 22. In the present embodiment, the superheated steam outlet 31 of the steam heater 3 is provided with an electrically operated valve. The top of the auxiliary electric boiler 1 is also provided with a safety valve, an electric exhaust valve, a blow-down valve and other instrument valves which are necessary for controlling the operation of the boiler
Wherein, the steam generated by the auxiliary electric boiler 1 is input from the side of the steam-water separator 2, water carried in the steam is separated by the steam-water separator 2, the water flows back to the auxiliary electric boiler 1 through a drain pipe 22 at the bottom of the steam-water separator 2, and the steam is output from the top of the steam-water separator 2. After the steam-water separator 2 is used for treatment, along with the removal of water in the steam, sodium ions in the steam can meet the requirements, but the dryness of the steam still cannot meet the requirements. Meanwhile, as the steam point connecting pipeline for the auxiliary electric boiler 1 and the nuclear power unit is longer, certain heat dissipation loss exists in the pipeline, a small amount of water can be condensed in the pipeline, and the dryness of the steam can be reduced. Therefore, a steam heater 3 is arranged in a steam pipeline, steam output from the top of the steam-water separator 2 enters the steam heater 3, an electric heating pipe with a certain heating power is arranged in the steam heater 3, residual water in the steam is completely evaporated into steam after being heated by the electric heating pipe, meanwhile, the temperature of the steam can be continuously increased, the saturated state is changed into the overheat state, and the superheat degree is controlled to be 3-10 ℃. The steam is conveyed to a steam point for the nuclear power unit in a long distance, and even if the heat dissipation loss of the pipeline occurs, the steam still has the superheat degree of more than 1 ℃, so that the dryness of the steam can be ensured to reach 100%.
Further, the inlet of the drain pipe 22 is connected to the water outlet end of the bottom of the steam-water separator 2, the outlet is connected to the auxiliary electric boiler 1, the inlet end of the drain pipe 22 is higher than the water outlet end thereof, and the separated water can be directly returned to the auxiliary electric boiler 1, so that waste is avoided.
Further, a drain valve 4 is disposed on the drain pipe 22 for controlling water at the bottom of the steam-water separator 2 to smoothly return to the boiler, so as to avoid water accumulation at the bottom of the separator
Further, an electric heating pipe is arranged in the steam heater 3, and saturated steam output by the steam-water separator 2 is changed into superheated steam after being heated by the electric heating pipe.
Further, a primary separation device and a secondary separation device are sequentially arranged in the steam-water separator 2 along the steam conveying direction, a primary steam outlet of the primary separation device is connected to the secondary separation device, a secondary steam outlet of the secondary separation device is communicated with the separation steam outlet 21, and water outlets of the primary separation device and the secondary separation device are connected to the drain pipe 22.
Further, the saturated steam output by the steam-water separator 2 is changed into superheated steam through the steam heater 3, and the superheat degree is controlled to be 3-10 ℃, so that the dryness of the steam reaching the steam utilization point is ensured to be 100%, and the heating power consumption of the steam can be ensured not to be too large.
Further, the separated steam outlet 21 is arranged at the top of the steam-water separator 2, and the low-pressure steam outlet 11 is connected to the side of the steam-water separator 2.
The working process of the utility model comprises the following steps:
according to the nuclear power auxiliary electric boiler system, after low-pressure steam is separated by the steam-water separator 2 and heated by the steam heater 3, the concentration of sodium ions in the steam is lower than 10ppb, the dryness is 100%, the parameter requirement of the nuclear power auxiliary steam is completely met, the system is simple in structure, and the parameter can meet the use requirement of a nuclear power station. When in operation, the low-pressure steam generated by the auxiliary electric boiler 1 is output from the low-pressure steam outlet 11 at the upper part of the auxiliary electric boiler, and the dryness of the steam is 96-98%. The steam is input through the side face of the steam-water separator 2, water carried in the steam is separated through a primary separation device and a secondary separation device in the steam-water separator 2, the water flows back to the auxiliary electric boiler 1 through a drain pipe 22 at the bottom of the steam-water separator 2, and the steam is output through a separation steam outlet 21 at the top of the steam-water separator 2. The dryness of the steam reaches about 99.5% after the steam passes through the steam-water separator 2. The steam output from the top of the steam-water separator 2 enters the steam heater 3, an electric heating pipe with certain heating power is arranged in the steam heater 3, the residual water in the steam is completely evaporated into steam after being heated by the electric heating pipe, and meanwhile, the whole temperature of the steam can be continuously increased, the saturated state is changed into the overheat state, and the superheat degree is controlled at 3-10 ℃. The steam is conveyed to a steam point for the nuclear power unit in a long distance, and even if the heat dissipation loss of the pipeline occurs, the steam still has the superheat degree of more than 1 ℃, so that the dryness of the steam can be ensured to reach 100%.
The above embodiments are illustrative of the present utility model, and not limiting, and any simple modifications of the present utility model fall within the scope of the present utility model.
Claims (6)
1. A nuclear power auxiliary electric boiler system, characterized in that: including auxiliary electric boiler (1), steam-water separator (2) and steam heater (3), the low pressure steam outlet (11) of auxiliary electric boiler (1) inserts steam-water separator (2), the separation steam outlet (21) of steam-water separator (2) inserts steam heater (3), the steam input that separates out via steam-water separator (2) steam heater (3), the superheated steam outlet (31) of steam heater (3) inserts nuclear power unit and uses the vapour point, the play water end of steam-water separator (2) inserts through hydrophobic pipe (22) auxiliary electric boiler (1), the water that carries in the steam that separates out via steam-water separator (2) is through hydrophobic pipe (22) backward flow extremely auxiliary electric boiler (1).
2. A nuclear power assisted electric boiler system according to claim 1, wherein: the inlet of the drain pipe (22) is connected with the water outlet end of the bottom of the steam-water separator (2), the outlet of the drain pipe is connected with the auxiliary electric boiler (1), and the inlet end of the drain pipe (22) is higher than the water outlet end of the drain pipe.
3. A nuclear power assisted electric boiler system according to claim 1 or 2, wherein: the drain pipe (22) is provided with a drain valve (4).
4. A nuclear power assisted electric boiler system according to claim 1, wherein: an electric heating pipe is arranged in the steam heater (3), and saturated steam output by the steam-water separator (2) is changed into superheated steam after being heated by the electric heating pipe.
5. A nuclear power assisted electric boiler system according to claim 1, wherein: the steam-water separator is characterized in that a primary separation device and a secondary separation device are sequentially arranged in the steam-water separator (2) along the steam conveying direction, a primary steam outlet of the primary separation device is connected into the secondary separation device, a secondary steam outlet of the secondary separation device is communicated with the separation steam outlet (21), and water outlets of the primary separation device and the secondary separation device are connected into the drain pipe (22).
6. A nuclear power assisted electric boiler system according to claim 1, wherein: the saturated steam output by the steam-water separator (2) is changed into superheated steam through the steam heater (3), and the superheat degree is controlled at 3-10 ℃.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202320681128.3U CN220205704U (en) | 2023-03-31 | 2023-03-31 | Nuclear power auxiliary electric boiler system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202320681128.3U CN220205704U (en) | 2023-03-31 | 2023-03-31 | Nuclear power auxiliary electric boiler system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN220205704U true CN220205704U (en) | 2023-12-19 |
Family
ID=89148698
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202320681128.3U Active CN220205704U (en) | 2023-03-31 | 2023-03-31 | Nuclear power auxiliary electric boiler system |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN220205704U (en) |
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2023
- 2023-03-31 CN CN202320681128.3U patent/CN220205704U/en active Active
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