CN216772824U - Electricity-heat-steam co-generation combined supply system utilizing nuclear energy - Google Patents
Electricity-heat-steam co-generation combined supply system utilizing nuclear energy Download PDFInfo
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- CN216772824U CN216772824U CN202123197394.9U CN202123197394U CN216772824U CN 216772824 U CN216772824 U CN 216772824U CN 202123197394 U CN202123197394 U CN 202123197394U CN 216772824 U CN216772824 U CN 216772824U
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- Y02E30/00—Energy generation of nuclear origin
Abstract
The utility model discloses an electric heating steam co-production combined supply system utilizing nuclear energy. The nuclear power generating unit comprises a nuclear steam supply device, a steam turbine with a high-pressure cylinder and a low-pressure cylinder, a steam-water separation reheater and a condenser, wherein a heat supply network heat exchanger is provided with a first pipe side inlet for supplying industrial water source, a first pipe side outlet communicated with a heat supply network water supply pipeline and a first shell side inlet connected with a high-pressure cylinder, a steam generator is provided with a second shell side inlet connected with the first pipe side outlet, a second pipe side inlet connected with the steam-water separation reheater and a second pipe side outlet connected with the shell side of the heat supply network heat exchanger, a superheater is provided with a third shell side inlet connected with the second shell side outlet, and heating steam is supplied to the pipe side of the superheater through at least one of the steam-water separation reheater and the nuclear steam supply device. The electric heating steam co-production combined supply system is reasonable in structural design and high in practicability.
Description
Technical Field
The utility model relates to the technical field of nuclear energy, in particular to a combined heat and steam generation system utilizing nuclear energy.
Background
Nuclear energy is one of the current mature alternative energy sources as a safe, clean and economical energy source. In recent years, the heating demand of urban residents becomes one of the main market fields in which the terminal heat consumption is rapidly increased, and on the other hand, the national energy-saving and emission-reduction policies are increasingly strict, and the market in various places requires to actively eliminate the backward capacity of the existing small heating boilers and the like; the heat load and the heat source are increased and decreased, and the urban heat source planning construction speed is delayed, so that the urban planning heat supply gap is increased day by day. Therefore, the development of nuclear energy for heating and heat supply has great significance for improving the energy structure of China, relieving the increasingly tense energy supply situation, meeting the increasing heating demand of urban residents, reducing the environmental protection pressure and the like.
The system for supplying steam, heat and electricity by utilizing nuclear power is provided in the related technology, wherein a heat source for supplying hot water is from main steam, a heat source for supplying steam is from middle steam extraction of a high-pressure cylinder, the heat supply and steam supply functions and the system are independent from each other, the structural design is unreasonable and complicated, the investment cost is high, the steam extraction energy level is not matched in utilization, the loss of available energy is large, and the practicability is poor.
Disclosure of Invention
The present invention is directed to solving, at least to some extent, one of the technical problems in the related art.
Therefore, the embodiment of the utility model provides the electricity, heat and steam cogeneration combined supply system which is reasonable in structural design and strong in practicability and utilizes nuclear energy.
The cogeneration system using nuclear power according to an embodiment of the present invention includes: the nuclear power plant comprises a nuclear steam supply device, a steam turbine with a high-pressure cylinder and a low-pressure cylinder, a steam-water separation reheater and a condenser, wherein an inlet of the high-pressure cylinder is connected with an outlet of the nuclear steam supply device, an inlet of the steam-water separation reheater is connected with an outlet of the high-pressure cylinder, an inlet of the low-pressure cylinder is connected with an outlet of the steam-water separation reheater, and an outlet of the low-pressure cylinder is connected with an inlet of the condenser; the heat supply network heat exchanger is provided with a first pipe side inlet connected with a heat supply network water return pipeline and a first industrial steam water supply source, a first pipe side outlet communicated with a heat supply network water supply pipeline, a first shell side inlet connected with an outlet of the high-pressure cylinder and a first shell side outlet connected with an inlet of the condenser; a steam generator having a second shell side inlet connected to the first tube side outlet and a second industrial steam supply, a second shell side outlet, a second tube side inlet connected to an outlet of the moisture separator reheater, and a second tube side outlet connected to a shell side of the heat grid heat exchanger; a superheater having a third shell side inlet connected to the second shell side outlet and a third shell side outlet for industrial steam, the superheater having a tube side supplied with heating steam by at least one of the moisture separator reheater and the nuclear steam supply.
According to the nuclear-energy-utilizing combined heat and steam generation system, the nuclear power unit, the heat supply network heat exchanger, the steam generator and the superheater are communicated, so that the combined heat and steam generation system can be used for heating in winter and supplying industrial steam, and can be used simultaneously. In addition, the heat supply network heat exchanger, the steam generator and the superheater of the nuclear-energy-utilizing combined electric heating and steam generation system exchange heat in a tube side and shell side isolated heating mode, so that the heat supply network heat exchanger, the steam generator and the superheater only exchange heat, and do not exchange working media with liquid in a pipeline of a nuclear power unit, potential radioactive substances in the nuclear power unit cannot enter a heat supply network and industrial steam, and the safety of the combined electric heating and steam generation system in use is improved.
In some embodiments, the superheater has a third tube side inlet connected to the moisture separator reheater outlet and a third tube side outlet connected to the shell side of the heat network heat exchanger.
In some embodiments, the cogeneration system utilizing nuclear energy comprises an insulated heater, the superheater having a third tube-side inlet and a third tube-side outlet; the isolation heater has a fourth tube side inlet connected to the outlet of the nuclear steam supply and a fourth tube side outlet connected to the shell side of the heat grid heat exchanger, a fourth shell side inlet connected to the third tube side outlet, and a fourth shell side outlet connected to the third tube side inlet.
In some embodiments, an outlet of the condenser is connected to an inlet of the nuclear steam supply.
In some embodiments, the moisture separator reheater is supplied with heating steam by at least one of an extraction steam of the high pressure cylinder and the nuclear steam supply.
In some embodiments, the nuclear power generating unit further comprises a first air inlet regulating valve and a second air inlet regulating valve, the first air inlet regulating valve is disposed at the inlet of the high pressure cylinder for regulating the pressure of the hot steam entering the high pressure cylinder, and the second air inlet regulating valve is disposed at the inlet of the low pressure cylinder for regulating the pressure of the hot steam entering the low pressure cylinder.
In some embodiments, the cogeneration system using nuclear power further comprises an industrial steam supply line connected to the third shell-side outlet, the industrial steam supply line comprises a low-pressure steam line and a medium-pressure steam line, and the low-pressure steam line is provided with a pressure reducer.
In some embodiments, the cogeneration system using nuclear power further comprises a water replenishing device connected to the first pipe-side inlet.
In some embodiments, the steam generator has a second tube-side inlet connected to the first tube-side outlet by a first valve and to the second industrial steam supply source by a second valve, and a third valve is disposed between the heat network supply line and the first tube-side outlet.
In some embodiments, the cogeneration system utilizing nuclear energy comprises a radiation monitoring meter for monitoring a radiation level within at least one of the heat supply network water supply line and the line of industrial steam.
Drawings
Fig. 1 is a schematic diagram of an electricity, heat, and steam cogeneration system utilizing nuclear energy according to an embodiment of the present invention.
Fig. 2 is a schematic diagram of an electricity, heat, and steam cogeneration system using nuclear energy according to another embodiment of the present invention.
Reference numerals:
1. a nuclear power unit; 11. a nuclear steam supply device; 12. a high pressure cylinder; 13. a moisture separator reheater; 14. a low pressure cylinder; 15. a condenser; 16. a first intake air regulating valve; 17. a second intake air regulating valve;
2. a heat supply network heat exchanger; 21. a heat supply network water return pipeline; 22. a first industrial steam water supply source; 23. a heat supply network water supply line; 231. a third valve; 24. a water replenishing device;
3. a steam generator; 31. a first valve; 32. a second industrial steam water supply source; 321. a second valve;
4. a superheater; 41. an industrial steam supply line; 411. a low pressure steam line; 412. a medium pressure steam line; 42. a pressure reducer;
5. an isolation heater;
6. radiation monitoring meter.
Detailed Description
Reference will now be made in detail to embodiments of the present invention, examples of which are illustrated in the accompanying drawings. The embodiments described below with reference to the drawings are illustrative and intended to be illustrative of the utility model and are not to be construed as limiting the utility model.
A cogeneration system using nuclear power according to an embodiment of the present invention will be described with reference to fig. 1 and 2.
As shown in fig. 1 and 2, the cogeneration system using nuclear power according to the embodiment of the present invention includes a nuclear power plant 1, a heat grid heat exchanger 2, a steam generator 3, and a superheater 4.
As shown in fig. 1 and 2, the nuclear power plant 1 includes a nuclear steam supply device 11, a steam turbine having a high pressure cylinder 12 and a low pressure cylinder 14, a moisture separator reheater 13, and a condenser 15, an inlet of the high pressure cylinder 12 is connected to an outlet of the nuclear steam supply device 11, an inlet of the moisture separator reheater 13 is connected to an outlet of the high pressure cylinder 12, an inlet of the low pressure cylinder 14 is connected to an outlet of the moisture separator reheater 13, and an outlet of the low pressure cylinder 14 is connected to an inlet of the condenser 15. Optionally, the nuclear power generating unit 1 may be a pressurized water reactor nuclear power generating unit 1.
It can be understood that the steam provided by the nuclear steam supply device 11 enters the high pressure cylinder 12 to perform expansion work, the exhausted steam enters the moisture separator reheater 13 to separate most of moisture in the steam through the moisture separator reheater 13, then the steam is changed into superheated steam through the two-stage heater, the superheated steam enters the low pressure cylinder 14 to perform work to drive the generator to generate power, and the generated exhaust steam enters the condenser 15 through the outlet of the low pressure cylinder 14. In other words, the nuclear steam supply device 11 is connected to the high pressure cylinder 12, and after the high pressure cylinder 12 applies work, the pressure of the steam is reduced and the humidity thereof is increased, and after the steam is subjected to steam-water separation and two-stage reheating in the steam-water separation reheater 13, the steam enters the low pressure cylinder 14 to apply work, and the exhaust steam enters the condenser 15.
As shown in fig. 1 and 2, the heat supply network heat exchanger 2 has a first tube side inlet connected to the heat supply network return line 21 and the first industrial steam supply source 22, a first tube side outlet communicated to the heat supply network supply line 23, a first shell side inlet connected to the outlet of the high pressure cylinder 12, and a first shell side outlet connected to the inlet of the condenser 15. It can be understood that, when the cogeneration system of electric heat and steam needs heating, can get into the water source to the pipe side of heat supply network heat exchanger 2 through heat supply network return water pipeline 21, then heats the shell side of heat supply network heat exchanger 2 through the export of high-pressure cylinder 12, and the hydrophobic behind the heat supply network heat exchanger 2 condensation can be discharged into condenser 15 through the export of first shell side.
As shown in fig. 1 and 2, the steam generator 3 has a second shell-side inlet connected to the first tube-side outlet and the second industrial steam supply source 32, a second shell-side outlet, a second tube-side inlet connected to the outlet of the moisture separator reheater 13, and a second tube-side outlet connected to the shell side of the heat grid heat exchanger 2. The superheater 4 has a third shell side inlet connected to the second shell side outlet and a third shell side outlet for industrial steam, and the tube side of the superheater 4 is supplied with heating steam from at least one of a moisture separator reheater 13 and a nuclear steam supply 11. It will be appreciated that when the cogeneration system supplies industrial steam, water may be supplied to the steam generator 3 by the first and second industrial steam supply sources 22 and 32, and then the industrial steam output from the steam generator 3 is reheated by passing through the superheater 4 and then discharged through the second shell side outlet of the superheater 4. The heat sources of the steam generator 3 and the superheater 4 are from the nuclear power plant 1, specifically, the steam generator 3 may be heated by a moisture separator reheater 13, and the superheater 4 may be heated by the moisture separator reheater 13 and/or the nuclear steam supply device 11.
According to the embodiment of the utility model, the characteristics of clean nuclear energy are fully utilized by the combined electricity, heat and steam generation system utilizing nuclear energy, the problem of environmental pollution caused by traditional energy sources such as fire coal, fuel gas and the like is solved, the energy structure of China is improved, and the combined electricity, heat and steam generation system is an effective way for ensuring clean energy supply required by industrial development.
According to the nuclear-energy-utilizing combined heat and steam generation system, the nuclear power unit 1, the heat supply network heat exchanger 2, the steam generator 3 and the superheater 4 are communicated with one another, so that the combined heat and steam generation system can be used for heating in winter and supplying industrial steam, and can be used for heating in winter and supplying industrial steam at the same time.
In addition, the heat supply network heat exchanger 2, the steam generator 3 and the superheater 4 of the nuclear power-utilizing cogeneration combined system in the embodiment of the utility model exchange heat in a tube-side and shell-side isolated heating manner, so that the heat supply network heat exchanger 2, the steam generator 3 and the superheater 4 only exchange heat, and do not exchange working media with liquid in a pipeline of the nuclear power unit 1, and therefore, potential radioactive substances in the nuclear power unit 1 cannot enter a heat supply network and industrial steam, and the safety of the nuclear power cogeneration combined system in use is improved.
In addition, the nuclear-energy-utilizing cogeneration combined system of the embodiment of the utility model can match the energy levels of the nuclear power generating unit 1 by adopting a multi-point steam extraction, step-by-step heating and hydrophobic self-flow heat regeneration mode when heating and supplying industrial steam, thereby reducing the loss of steam extraction and heat supply on the heat efficiency of the unit and ensuring higher economic benefit of the cogeneration combined system.
In some embodiments, as shown in fig. 1, the third tube side inlet of the superheater 4 is connected to the outlet of the moisture separator reheater 13, and the third tube side outlet of the superheater 4 is connected to the shell side of the heat network heat exchanger 2. It is understood that the heat source of the superheater 4 comes from the outlet of the moisture separator reheater 13, and after heat exchange is performed on the superheater 4, the drain water can enter the shell side of the heat network heat exchanger 2 in a gravity flow manner.
In other embodiments, as shown in fig. 2, the cogeneration system using nuclear power comprises an insulated heater 5, and the superheater 4 has a third tube side inlet and a third tube side outlet. The isolation heater 5 has a fourth tube side inlet connected to the outlet of the nuclear steam supply device 11 and a fourth tube side outlet connected to the shell side of the heat grid heat exchanger 2, a fourth shell side inlet connected to the third tube side outlet, and a fourth shell side outlet connected to the third tube side inlet. The electric heat and steam cogeneration combined supply system of the embodiment of the utility model can reduce the pressure and the temperature of the steam at the outlet of the nuclear steam supply device 11 by arranging the isolation heater 5, and the water in the isolation heater 5 can circulate under the action of the circulating pump, so that the heat in the isolation heater 5 can be transferred to the superheater 4.
Further, as shown in fig. 1 and 2, an outlet of the condenser 15 is connected to an inlet of the nuclear steam supply device 11, so that water in the condenser 15 can flow into the nuclear steam supply device 11 to reheat the water, and the rationality of the cogeneration system is improved when the cogeneration system is used.
Further, the moisture separator reheater 13 is supplied with heating steam from at least one of the extraction steam of the high pressure cylinder 12 and the nuclear steam supply device 11. It can be understood that the moisture separator reheater 13 may be supplied with heating steam from the high pressure cylinder 12, or may be supplied with heating steam from the nuclear steam supply device 11, so as to improve flexibility of the cogeneration system in use.
In some embodiments, as shown in fig. 1 and 2, the nuclear power plant 1 further includes a first air intake regulating valve 16 and a second air intake regulating valve 17, the first air intake regulating valve 16 being provided at an inlet of the high pressure cylinder 12 for regulating the pressure of the hot steam entering the high pressure cylinder 12, and the second air intake regulating valve 17 being provided at an inlet of the low pressure cylinder 14 for regulating the pressure of the hot steam entering the low pressure cylinder 14. It can be understood that the first inlet regulating valve 16 can regulate the pressure of the steam entering the high pressure cylinder 12, and the second inlet regulating valve 17 can regulate the pressure of the steam entering the low pressure cylinder 14, so as to ensure that the first stage pressure of the steam turbine can still meet the requirement of the average temperature control mode, and reduce the influence of the pressure reduction of the steam turbine inlet caused by steam extraction on the steam turbine.
Further, as shown in fig. 1 and fig. 2, the cogeneration system further includes an industrial steam supply pipeline 41 connected to the outlet of the third shell side, the industrial steam supply pipeline 41 includes a low-pressure steam pipeline 411 and a medium-pressure steam pipeline 412, and a pressure reducer 42 is disposed on the low-pressure steam pipeline 411.
Specifically, as shown in fig. 1 and 2, the cogeneration system further includes a water replenishing device 24, and the water replenishing device 24 is connected to the first pipe side inlet. It can be understood that the water replenishing device 24 comprises a water replenishing pipeline and a deaerator, and when the water amount in the heat supply network water supply system is reduced, water can be supplied into the heat supply network water returning pipeline 21 through the water replenishing pipeline and oxygen in water can be removed through the deaerator, so that the reliability of the combined heat and steam generation system is high when the combined heat and steam generation system is used.
Further, as shown in fig. 1 and 2, a second tube side inlet of the steam generator 3 is connected to a first tube side outlet through a first valve 31 and to a second industrial steam water supply source 32 through a second valve 321, and a third valve 231 is provided between the heat network water supply line 23 and the first tube side outlet. It is understood that, when the cogeneration system only heats and supplies heat, the third valve 231 may be opened and the first and second valves 31 and 321 may be closed, so that the water path is discharged from the grid water supply pipe after heat exchange by the grid heat supplier. When the cogeneration system supplies only industrial steam, the first valve 31 and the second valve 321 may be opened and the third valve 231 may be closed, so that the industrial water source is discharged from the industrial steam supply line 41 after passing through the steam generator 3 and the superheater 4. When the cogeneration system simultaneously heats and supplies industrial steam, the first valve 31, the second valve 321, and the third valve 231 may be opened.
Specifically, as shown in fig. 1 and 2, the cogeneration system further includes a radiation monitoring table 6 for monitoring a radiation level in at least one of the heat supply network water supply line 23 and the line of the industrial steam. For example, the radiation monitoring tables 6 may be provided on both the heat supply network water supply line 23 and the industrial steam supply line 41. The electric heating steam co-generation combined supply system provided by the embodiment of the utility model can detect whether the water supply pipeline 23 of the heat supply network and the industrial steam supply pipeline 41 contain radioactive substances or not by arranging the radiation monitoring meter 6, so that the safety of the electric heating steam co-generation combined supply system in use can be improved.
In the description of the present invention, it is to be understood that the terms "central," "longitudinal," "lateral," "length," "width," "thickness," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," "clockwise," "counterclockwise," "axial," "radial," "circumferential," and the like are used in the orientations and positional relationships indicated in the drawings for convenience in describing the utility model and to simplify the description, and are not intended to indicate or imply that the referenced devices or elements must have a particular orientation, be constructed and operated in a particular orientation, and are therefore not to be considered limiting of the utility model.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one such feature. In the description of the present invention, "a plurality" means at least two, e.g., two, three, etc., unless specifically limited otherwise.
In the present invention, unless otherwise expressly stated or limited, the terms "mounted," "connected," "secured," and the like are to be construed broadly and can, for example, be fixedly connected, detachably connected, or integrally formed; may be mechanically coupled, may be electrically coupled or may be in communication with each other; they may be directly connected or indirectly connected through intervening media, or they may be connected internally or in any other suitable relationship, unless expressly stated otherwise. The specific meanings of the above terms in the present invention can be understood by those skilled in the art according to specific situations.
In the present invention, unless otherwise expressly stated or limited, the first feature "on" or "under" the second feature may be directly contacting the first and second features or indirectly contacting the first and second features through an intermediate. Also, a first feature "on," "over," and "above" a second feature may be directly or diagonally above the second feature, or may simply indicate that the first feature is at a higher level than the second feature. A first feature being "under," "below," and "beneath" a second feature may be directly under or obliquely under the first feature, or may simply mean that the first feature is at a lesser elevation than the second feature.
In the present disclosure, the terms "one embodiment," "some embodiments," "an example," "a specific example," or "some examples" and the like mean that a specific feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the present disclosure. In this specification, the schematic representations of the terms used above are not necessarily intended to refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Furthermore, various embodiments or examples and features of different embodiments or examples described in this specification can be combined and combined by one skilled in the art without contradiction.
Although embodiments of the present invention have been shown and described above, it is understood that the above embodiments are exemplary and should not be construed as limiting the present invention, and that variations, modifications, substitutions and alterations can be made to the above embodiments by those of ordinary skill in the art within the scope of the present invention.
Claims (10)
1. An electric heat and steam cogeneration combined supply system using nuclear energy, comprising:
the nuclear power plant comprises a nuclear steam supply device, a steam turbine with a high-pressure cylinder and a low-pressure cylinder, a steam-water separation reheater and a condenser, wherein an inlet of the high-pressure cylinder is connected with an outlet of the nuclear steam supply device, an inlet of the steam-water separation reheater is connected with an outlet of the high-pressure cylinder, an inlet of the low-pressure cylinder is connected with an outlet of the steam-water separation reheater, and an outlet of the low-pressure cylinder is connected with an inlet of the condenser;
the heat supply network heat exchanger is provided with a first pipe side inlet connected with a heat supply network water return pipeline and a first industrial steam water supply source, a first pipe side outlet communicated with a heat supply network water supply pipeline, a first shell side inlet connected with an outlet of the high-pressure cylinder and a first shell side outlet connected with an inlet of the condenser;
a steam generator having a second shell side inlet connected to the first tube side outlet and a second industrial steam supply, a second shell side outlet, a second tube side inlet connected to an outlet of the moisture separator reheater, and a second tube side outlet connected to a shell side of the heat grid heat exchanger;
a superheater having a third shell side inlet connected to the second shell side outlet and a third shell side outlet for industrial steam, the superheater having a tube side supplied with heating steam by at least one of the moisture separator reheater and the nuclear steam supply.
2. An cogeneration system utilizing nuclear energy as in claim 1, wherein said superheater has a third tube side inlet connected to said moisture separator reheater outlet and a third tube side outlet connected to said heat network heat exchanger shell side.
3. A cogeneration system utilizing nuclear power according to claim 1, comprising an insulated heater, said superheater having a third tube side inlet and a third tube side outlet;
the isolation heater has a fourth tube side inlet connected to the outlet of the nuclear steam supply and a fourth tube side outlet connected to the shell side of the heat grid heat exchanger, a fourth shell side inlet connected to the third tube side outlet, and a fourth shell side outlet connected to the third tube side inlet.
4. An cogeneration system using nuclear power according to claim 1, wherein an outlet of said condenser is connected to an inlet of said nuclear steam supply device.
5. An cogeneration system using nuclear energy according to any one of claims 1 to 4, wherein said moisture separator reheater is supplied with heating steam by at least one of an extraction steam of said high pressure cylinder and said nuclear steam supply device.
6. An electric heat and steam cogeneration system using nuclear power as in claim 5, wherein said nuclear power plant further comprises a first air inlet regulating valve and a second air inlet regulating valve, said first air inlet regulating valve being provided at an inlet of said high pressure cylinder for regulating the pressure of the hot steam entering said high pressure cylinder, said second air inlet regulating valve being provided at an inlet of said low pressure cylinder for regulating the pressure of the hot steam entering said low pressure cylinder.
7. An cogeneration system using nuclear energy according to claim 1, further comprising an industrial steam supply line connected to said third shell side outlet, said industrial steam supply line including a low pressure steam line and a medium pressure steam line, said low pressure steam line being provided with a pressure reducer.
8. A cogeneration system utilizing nuclear power according to claim 1, further comprising a water replenishing device connected to said first pipe side inlet.
9. An cogeneration system using nuclear power according to claim 1, wherein said steam generator has a second tube-side inlet connected to said first tube-side outlet through a first valve and to said second industrial steam supply source through a second valve, and a third valve is provided between said heat-network supply line and said first tube-side outlet.
10. An cogeneration system utilizing nuclear power according to any one of claims 1 to 9, further comprising a radiation monitoring meter for monitoring a radiation level in at least one of said heat supply network water supply line and said line of industrial steam.
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