CN211650406U - Steam heating system for preventing nuclear power secondary medium from leaking outwards - Google Patents
Steam heating system for preventing nuclear power secondary medium from leaking outwards Download PDFInfo
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- CN211650406U CN211650406U CN202020320695.2U CN202020320695U CN211650406U CN 211650406 U CN211650406 U CN 211650406U CN 202020320695 U CN202020320695 U CN 202020320695U CN 211650406 U CN211650406 U CN 211650406U
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Abstract
The utility model discloses a steam heating system for preventing nuclear power secondary medium leaks outward, including secondary medium return circuit, high pressure circulating water return circuit and low pressure medium return circuit, between secondary medium and the high pressure circulating water and through heat exchanger transmission heat between high pressure circulating water and the low pressure medium, during the system operation, keep the pressure in high pressure circulating water return circuit to be higher than the pressure in secondary medium return circuit, the pressure in low pressure medium return circuit is less than the pressure in secondary medium return circuit. The utility model discloses owing to established high-pressure circulating water return circuit between secondary medium return circuit and low pressure medium return circuit to no matter make high-pressure circulating water return circuit's pressure all be higher than the secondary medium return circuit at normal operating, start-up stop or accident situation, can effectively prevent secondary medium's outer hourglass from this, ensured the security of the external heat supply of low pressure medium, make to utilize the nuclear energy to become possible to the external heat supply. The utility model also provides a similar solution for other energy utilization systems which need to prevent the medium from leaking.
Description
Technical Field
The utility model relates to a steam heating system for preventing nuclear power secondary medium leaks outward belongs to the industrial heating and resident heating field that utilize special method.
Background
In recent years, with the increase of industrial heat and resident heating demand and the upgrade and replacement of the traditional coal-fired and gas-fired distributed heating mode, the centralized heating technology using low-pressure steam as a heat source gradually becomes an important aspect in the field of energy utilization.
The flexibility modification of the thermal power generating unit is suitable for the requirement of a power grid on peak regulation and is also a positive response of a conventional coal burner group on the market heat supply requirement. Under the large background that the electric power auxiliary market is continuously perfected, the flexible modification not only increases the peak regulation capacity of the unit, but also brings considerable economic benefits to the power plant due to participation in deep peak regulation and external centralized heat supply.
The nuclear power unit is an important component of non-fossil fuel installation in China, and the installed capacity of the nuclear power unit reaches 4860 ten thousand kilowatts in China by 06 months in 2019. The nuclear power unit bears a basic load type in a national power grid, which is determined by the characteristics of nuclear power. If the external heat supply can be realized by utilizing nuclear power, the heat supply benefit of a power station can be increased, and a certain peak regulation effect can be achieved. However, nuclear power heating must be performed on the premise of sufficiently ensuring safety.
At present, the technology is mature, the operation is reliable, and the commercialization rate is the highest in the nuclear power field, and the secondary medium of the power station is saturated steam with a certain pressure grade, is generated by a steam generation system in a nuclear island, and is then conveyed to a steam power system to do work for power generation. The nuclear power supplies heat to the outside, namely, a secondary medium is used as a heat source to generate steam or hot water with low pressure grade, so that the external heat supply requirement is met. Because steam or hot water with low pressure grade is an open system for conveying to an industrial area or a residential area, the problem of possible leakage of a secondary medium must be fundamentally eliminated, and the safety of nuclear power external heat supply is ensured.
If the heat supply medium (steam or hot water) of a low pressure level is directly generated using the secondary medium, there is a risk that the secondary medium leaks into the heat supply medium because the pressure of the secondary medium is higher than the pressure of the steam or hot water for heat supply. Based on the circumstances, the utility model provides a novel heat transfer system eliminates the possibility of secondary medium to leaking outward from technical angle, makes the external heat supply of nuclear power possible.
SUMMERY OF THE UTILITY MODEL
In order to solve the technical problem, the utility model discloses a steam heating system for preventing nuclear power secondary medium leaks outward guarantees that secondary medium can not appear leaking outward, and the low pressure medium (steam or hot water) that produces simultaneously and need the parameter is used for the external heat supply.
The utility model adopts the following technical scheme:
a steam heating system for preventing nuclear power secondary medium from leaking outwards comprises a secondary medium loop, a high-pressure circulating water loop and a low-pressure medium loop, wherein heat is transferred between the secondary medium loop and the high-pressure circulating water loop and between the high-pressure circulating water loop and the low-pressure medium loop through heat exchangers, when the system operates, the pressure of the high-pressure circulating water loop is kept higher than that of the secondary medium loop, and the pressure of the low-pressure medium loop is lower than that of the secondary medium loop.
Preferably, the secondary medium loop comprises a secondary medium inlet, a steam condenser and a secondary medium outlet which are communicated in sequence.
Preferably, the high-pressure circulating water loop comprises a high-pressure circulating water pump, a steam condenser, a pressure stabilizer and a low-pressure evaporator which are sequentially and circularly communicated.
Preferably, the low-pressure medium loop comprises a low-pressure evaporator, a steam drum, a low-pressure medium inlet and a low-pressure medium outlet, and the low-pressure evaporator, the low-pressure medium inlet and the low-pressure medium outlet are respectively communicated with the steam drum.
Preferably, the secondary medium circuit in the steam condenser passes through the shell side of the steam condenser, and the high-pressure circulating water circuit passes through the tube side of the steam condenser.
Preferably, the high-pressure circulating water circuit in the low-pressure evaporator passes through the tube side of the low-pressure evaporator, and the low-pressure medium circuit passes through the shell side of the low-pressure evaporator.
Preferably, the high-pressure circulating water circuit, the secondary medium circuit and the low-pressure medium circuit are all provided with safety valves.
The steam condenser releases the heat of the secondary medium to high-pressure circulating water, the low-pressure evaporator releases the heat of the high-pressure circulating water to a heat supply medium, the high-pressure circulating water pump is a power device for pushing the high-pressure circulating water, the pressure stabilizing device ensures that a high-pressure circulating water loop operates within a required parameter range, the steam pocket is a steam-water separation device of the low-pressure medium loop, and the generated saturated steam is delivered to an external heat user.
The secondary medium loop can be saturated steam generated by nuclear power, and can also be other mediums with special properties, such as corrosive, toxic or polluting mediums and the like. The scheme or the derivative scheme can be used for system protection to avoid medium leakage.
The pressure stabilizer is an important component of a high-pressure circulating water loop, and can be saturated steam with a certain pressure generated at the top of the pressure stabilizer by electric heating or steam heating or other gases with adjustable pressure directly filled at the top according to different energy sources.
If the system finally generates steam, a steam pocket is matched with the low-pressure evaporator. The low-pressure medium can also be hot water, depending on the requirements of the user. If hot water is supplied externally, the steam drum is omitted from the system, and the low-pressure evaporator is replaced by a water-water heat exchanger.
The utility model has the advantages that: for utilizing secondary medium direct heating heat supply medium (water or steam), the utility model discloses innovatively set up high-pressure circulating water return circuit between two kinds of medium return circuits to at the system operation, open and stop or under the fault condition, all maintain high-pressure circulating water return circuit's pressure and be higher than the pressure in secondary medium return circuit, eliminated the possibility that secondary medium leaks outward from this, guaranteed the security of system. Meanwhile, steam or hot water generated by high-pressure circulating water is used for supplying heat. The utility model discloses make the industry heat supply or resident's heating that utilize nuclear power to go on possible, also provide the solution for the energy utilization system that similar needs prevent the medium and leak outward simultaneously.
Drawings
Fig. 1 is a schematic structural view of the present invention;
in the figure: 1. the system comprises a high-pressure circulating water pump, a steam condenser, a pressure stabilizer, a steam drum and a low-pressure evaporator, wherein the high-pressure circulating water pump 2 is connected with the steam condenser 3 is connected with the pressure stabilizer 4.
Detailed Description
The technical solution of the present invention is further described in detail by the following specific embodiments in combination with the accompanying drawings:
example (b): as shown in the attached figure 1, the steam heating system for preventing the nuclear power secondary medium from leaking outwards comprises a secondary medium loop, a high-pressure circulating water loop and a low-pressure medium loop, heat is transferred between the secondary medium loop and the high-pressure circulating water loop and between the high-pressure circulating water loop and the low-pressure medium loop through heat exchangers, when the system operates, the pressure of the high-pressure circulating water loop is kept higher than that of the secondary medium loop, and the pressure of the low-pressure medium loop is lower than that of the secondary medium loop. The secondary medium loop comprises a secondary medium inlet, a steam condenser 2 and a secondary medium outlet which are communicated in sequence. The high-pressure circulating water loop comprises a high-pressure circulating water pump 1, a steam condenser 2, a pressure stabilizer 3 and a low-pressure evaporator 5 which are sequentially and circularly communicated. The low-pressure medium loop comprises a low-pressure evaporator 5, a steam drum 4, a low-pressure medium inlet and a low-pressure medium outlet, and the low-pressure evaporator 5, the low-pressure medium inlet and the low-pressure medium outlet are respectively communicated with the steam drum 4.
The utility model discloses during the use to the secondary medium that the saturated steam state exists enters into steam condenser 2's casing side, gives the high-pressure circulating water that the pipe side flowed through to the heat transfer, and saturated steam becomes the condensate water and gets back to again and accomplishes the heat absorption evaporation process in the nuclear island. In the low-pressure evaporator 5, the low-pressure medium absorbs the heat released by the high-pressure circulating water, completes the processes of temperature rise and evaporation, completes the steam-water separation in the steam drum 4, and then outputs the steam-water separation to the outside of the system for heat supply.
The high-pressure circulating water pump 1 pushes circulating water to flow through the steam condenser 2 and the low-pressure evaporator 5 in sequence, and the high-pressure circulating water loop further comprises a pressure stabilizing device 3 which can enable the high-pressure circulating water to stably run under required pressure.
When the system is operated, the pressure of the high-pressure circulating water loop is kept in a state of being higher than the pressure of the secondary medium loop, and meanwhile, the low-pressure medium loop generates hot water or steam with relatively low pressure grade according to the requirement of a user. If the steam condenser 2 leaks in the operation process, firstly, a channel for the secondary medium to enter and exit the steam condenser 2 is cut off, the residual secondary medium in the steam condenser 2 is discharged in time, then, the pressure of the high-pressure circulating water loop is released, the stored water in the loop is discharged completely, and the steam condenser 2 is maintained.
When the system is put into operation, the pressure in the high-pressure circulating water loop needs to be established first, and then the high-pressure circulating water loop is put into a secondary medium loop; when the system stops running, the secondary medium loop is cut off, and after the pressure of the secondary medium loop is reduced, the pressure of the high-pressure circulating water side is reduced.
In the processes (under the working conditions of operation, input, shutdown and failure), because the pressure of the high-pressure circulating water loop is always kept higher than the pressure of the secondary medium side, the risk of secondary medium leakage can be eliminated, hot water or steam in the low-pressure medium loop is ensured not to be polluted, the reliability of heat supply is ensured, and the external heat supply by utilizing nuclear energy becomes possible. The utility model also provides a similar solution for other energy utilization systems which need to prevent the medium from leaking.
The above-described embodiments are only preferred embodiments of the present invention, and are not intended to limit the present invention in any way, and other variations and modifications may be made without departing from the scope of the claims.
Claims (7)
1. A steam heating system for preventing nuclear power secondary medium from leaking outside is characterized by comprising a secondary medium loop, a high-pressure circulating water loop and a low-pressure medium loop, wherein heat is transferred between the secondary medium loop and the high-pressure circulating water loop and between the high-pressure circulating water loop and the low-pressure medium loop through heat exchangers, when the system operates, the pressure of the high-pressure circulating water loop is kept higher than that of the secondary medium loop, and the pressure of the low-pressure medium loop is lower than that of the secondary medium loop.
2. The steam heating system for preventing the nuclear power secondary medium from leaking outside as claimed in claim 1, wherein the secondary medium loop comprises a secondary medium inlet, a steam condenser and a secondary medium outlet which are communicated in sequence.
3. The steam heating system for preventing the leakage of the nuclear power secondary medium as recited in claim 1, wherein the high-pressure circulating water loop comprises a high-pressure circulating water pump, a steam condenser, a pressure stabilizer and a low-pressure evaporator which are sequentially and circularly communicated.
4. The steam heating system for preventing the leakage of the nuclear power secondary medium as recited in claim 1, wherein the low-pressure medium loop comprises a low-pressure evaporator, a steam drum, a low-pressure medium inlet and a low-pressure medium outlet, and the low-pressure evaporator, the low-pressure medium inlet and the low-pressure medium outlet are respectively communicated with the steam drum.
5. A steam heating system for preventing leakage of nuclear power secondary medium as defined in claim 2 or 3, wherein the secondary medium circuit in the steam condenser passes through a shell side of the steam condenser, and the high-pressure circulating water circuit passes through a tube side of the steam condenser.
6. The steam heating system for preventing the leakage of the nuclear power secondary medium as recited in claim 3 or 4, wherein the high-pressure circulating water loop in the low-pressure evaporator passes through a tube side of the low-pressure evaporator, and the low-pressure medium loop passes through a shell side of the low-pressure evaporator.
7. The steam heating system for preventing the leakage of the nuclear power secondary medium as recited in claim 1, wherein safety valves are disposed on the high-pressure circulating water loop, the secondary medium loop and the low-pressure medium loop.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202020320695.2U CN211650406U (en) | 2020-03-16 | 2020-03-16 | Steam heating system for preventing nuclear power secondary medium from leaking outwards |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202020320695.2U CN211650406U (en) | 2020-03-16 | 2020-03-16 | Steam heating system for preventing nuclear power secondary medium from leaking outwards |
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| Publication Number | Publication Date |
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| CN211650406U true CN211650406U (en) | 2020-10-09 |
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| CN202020320695.2U Active CN211650406U (en) | 2020-03-16 | 2020-03-16 | Steam heating system for preventing nuclear power secondary medium from leaking outwards |
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Address after: 1216, danionggang Road, Jianggan District, Hangzhou City, Zhejiang Province, 310021 Patentee after: Xizi clean energy equipment manufacturing Co.,Ltd. Address before: 1216, danionggang Road, Jianggan District, Hangzhou City, Zhejiang Province, 310021 Patentee before: HANGZHOU BOILER GROUP Co.,Ltd. |
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