CN216346522U - Nuclear power unit cogeneration system utilizing condensate water waste heat - Google Patents
Nuclear power unit cogeneration system utilizing condensate water waste heat Download PDFInfo
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- CN216346522U CN216346522U CN202123027887.8U CN202123027887U CN216346522U CN 216346522 U CN216346522 U CN 216346522U CN 202123027887 U CN202123027887 U CN 202123027887U CN 216346522 U CN216346522 U CN 216346522U
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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Abstract
The utility model discloses a cogeneration system of a nuclear power unit by utilizing waste heat of condensed water, which comprises a reactor, a steam generator and an absorption heat pump, wherein the reactor is used for generating a steam; the gas outlet of the reactor is connected with the hot end inlet of the steam generator; the absorption heat pump comprises a generator, a condenser, an evaporator and an absorber; the hot end inlet of the generator is connected with the hot end outlet of the steam generator, the hot end outlet of the generator is connected with the gas inlet of the reactor, and the refrigerant outlet end of the generator is sequentially connected with the hot end of the condenser, the cold end of the evaporator and the solution inlet of the absorber; the solution outlet of the generator is connected with the solution inlet of the absorber, and the solution outlet of the absorber is connected with the solution inlet of the generator; the cold end inlet of the absorber is connected with a heat supply network water return pipeline, and the cold end outlet of the absorber is connected with a heat supply network water supply pipeline. The waste heat of the steam turbine exhaust of the nuclear power unit is fully utilized for heat supply, and the capacity utilization efficiency is effectively improved.
Description
Technical Field
The utility model belongs to the field of clean energy heat supply, and relates to a cogeneration system of a nuclear power unit by using waste heat of condensed water.
Background
Coal-fired heating is one of the most important factors causing haze in winter, and sulfur dioxide and dust particles in air are increased rapidly in northern central heating cities. The temperature is low, the wind power is small and other meteorological conditions enable haze to be accumulated and not scattered, long-time haze weather in northern areas is caused, and the problem of hot spots influencing the image of the nationality and the county is solved. In addition, harmful substances generated by coal-fired heating comprise carbon dioxide and sulfur dioxide, the carbon dioxide is a main substance of greenhouse effect, and the sulfur dioxide is easy to form acid rain. Therefore, coal-fired heating brings serious environmental pollution problems, and the promotion of clean energy heating is urgently needed.
Nuclear energy has been developed in recent years as an important clean energy source. At present, nuclear power heat supply is not applied on a large scale, mainly in a steam extraction form of a steam turbine, and the thermoelectric ratio is low.
SUMMERY OF THE UTILITY MODEL
The utility model aims to overcome the defects of the prior art and provide a cogeneration system of a nuclear power unit by using the waste heat of condensed water, so that the waste heat of the steam exhaust of a steam turbine of the nuclear power unit is fully used for supplying heat, and the capacity utilization efficiency is effectively improved.
In order to achieve the purpose, the utility model adopts the following technical scheme to realize the purpose:
a nuclear power unit cogeneration system utilizing the waste heat of condensed water comprises a reactor, a steam generator and an absorption heat pump;
the gas outlet of the reactor is connected with the hot end inlet of the steam generator;
the absorption heat pump comprises a generator, a condenser, an evaporator and an absorber; the hot end inlet of the generator is connected with the hot end outlet of the steam generator, the hot end outlet of the generator is connected with the gas inlet of the reactor, and the refrigerant outlet end of the generator is sequentially connected with the hot end of the condenser, the cold end of the evaporator and the solution inlet of the absorber; the solution outlet of the generator is connected with the solution inlet of the absorber, and the solution outlet of the absorber is connected with the solution inlet of the generator; the cold end inlet of the absorber is connected with a heat supply network water return pipeline, and the cold end outlet of the absorber is connected with a heat supply network water supply pipeline.
Preferably, steam is provided with in steam generator's the cold junction, and steam generator's cold junction exit linkage has the steam turbine entry, and the steam extraction export of steam turbine and steam generator's cold junction entry linkage.
Furthermore, the exhaust steam outlet of the steam turbine is connected with the hot end inlet of the evaporator, and the hot end outlet of the evaporator is connected with the cold end inlet of the steam generator.
And a feed water heater is arranged between the hot end outlet of the evaporator and the cold end inlet of the steam generator, the inlet and the outlet of the cold end of the feed water heater are respectively connected with the hot end outlet of the evaporator and the cold end inlet of the steam generator, and the steam extraction outlet of the steam turbine is connected with the hot end of the feed water heater.
Preferably, a cold end of a condenser is connected between a cold end outlet of the absorber and the heat supply network water supply pipeline, a cold end outlet of the absorber is connected with a cold end inlet of the condenser, and a cold end outlet of the condenser is connected with the heat supply network water supply pipeline.
Preferably, a throttle valve is arranged between the hot end of the condenser and the cold end of the evaporator.
Preferably, a circulation pump is provided between the solution outlet of the absorber and the solution inlet of the generator.
Preferably, the solution in the absorption heat pump is a lithium bromide solution.
Compared with the prior art, the utility model has the following beneficial effects:
according to the utility model, the nuclear power unit and the absorption heat pump are combined, and helium gas at the outlet of the steam generator is used as a high-temperature heat source of the absorption heat pump, so that the heat supply capacity of the nuclear power unit is improved, the thermoelectricity is improved, and the capacity utilization efficiency is effectively improved.
Furthermore, the exhaust waste heat of the steam turbine is used as a low-temperature heat source of the absorption heat pump, so that the capacity utilization efficiency is effectively improved.
Drawings
FIG. 1 is a schematic diagram of the system of the present invention.
Wherein: 1-a reactor; 2-a steam generator; 3-a steam turbine; 4-a feedwater heater; 5-a generator; 6-a condenser; 7-an evaporator; 8-an absorber; 9-a throttle valve; 10-circulating pump.
Detailed Description
The utility model is described in further detail below with reference to the accompanying drawings:
as shown in fig. 1, the cogeneration system of a nuclear power generating unit using waste heat of condensed water according to the present invention includes a reactor 1, a steam generator 2, a steam turbine 3, a feedwater heater 4, a generator 5, a condenser 6, an evaporator 7, an absorber 8, a throttle valve 9, and a circulation pump 10.
The absorption heat pump comprises a generator 5, a condenser 6, an evaporator 7 and an absorber 8; a hot end inlet of the generator 5 is connected with a hot end outlet of the steam generator 2, a hot end outlet of the generator 5 is connected with a gas inlet of the reactor 1, and a refrigerant outlet end of the generator 5 is sequentially connected with a hot end of the condenser 6, a cold end of the evaporator 7 and a solution inlet of the absorber 8; a solution outlet of the generator 5 is connected with a solution inlet of the absorber 8, and a solution outlet of the absorber 8 is connected with a solution inlet of the generator 5; the cold end inlet of the absorber 8 is connected with a heat supply network water return pipeline, and the cold end outlet of the absorber 8 is connected with a heat supply network water supply pipeline.
The cold end of the condenser 6 is connected between the cold end outlet of the absorber 8 and the heat supply network water supply pipeline, the cold end outlet of the absorber 8 is connected with the cold end inlet of the condenser 6, and the cold end outlet of the condenser 6 is connected with the heat supply network water supply pipeline.
The gas outlet of the reactor 1 is connected with the hot end inlet of the steam generator 2; be provided with steam in steam generator 2's the cold junction, steam generator 2's cold junction exit linkage has 3 entrances of steam turbine, and steam turbine 3's steam extraction export is connected with steam generator 2's cold junction entry.
The hot end outlet of the condenser 6 is connected with the cold end inlet of the evaporator 7 through a throttle valve 9, and the solution outlet of the absorber 8 is connected with the solution inlet of the generator 5 through a circulating pump 10.
Be provided with steam in steam generator 2's the cold junction, steam generator 2's cold junction exit linkage has 3 entrances of steam turbine, and steam turbine 3's steam extraction export is connected with steam generator 2's cold junction entry.
The exhaust steam outlet of the steam turbine 3 is connected with the hot end inlet of the evaporator 7, and the hot end outlet of the evaporator 7 is connected with the cold end inlet of the steam generator 2.
A feed water heater 4 is arranged between the hot end outlet of the evaporator 7 and the cold end inlet of the steam generator 2, the inlet and the outlet of the cold end of the feed water heater 4 are respectively connected with the hot end outlet of the evaporator 7 and the cold end inlet of the steam generator 2, and the steam extraction outlet of the steam turbine 3 is connected with the hot end of the feed water heater 4.
High-temperature helium gas from the reactor 1 enters a steam generator 2 to heat steam, and the generated high-temperature steam is used for driving a steam turbine 3 to do work and generate power. Steam at the outlet of the steam generator 2 enters the generator 5 to be used as a high-temperature heat source of the absorption heat pump, and the steam at the outlet of the generator 5 returns to the reactor 1 to absorb heat. The exhausted steam of the steam turbine 3 enters an evaporator 7 for condensation and serves as a low-temperature heat source of the absorption heat pump, and the feed water at the outlet of the evaporator 7 enters a feed water heater to be preheated by the extracted steam of the steam turbine 3 and then enters a steam generator 2 for heating.
The working medium in the absorption heat pump comprises a refrigerant for preparing cold and an absorbent solution for absorbing and desorbing the refrigerant, the refrigerant and the absorbent solution form a working medium pair, and the absorbent solution in the embodiment adopts a lithium bromide solution; heating dilute solution with certain concentration conveyed from the absorber 8 by a circulating pump 10 in the generator 5 by using high-temperature helium gas, and evaporating most of low-boiling point refrigerant in the solution; the refrigerant vapor enters the hot end of the condenser 6 and is condensed into refrigerant liquid in the condenser 6; the refrigerant liquid enters the cold end of the evaporator 7, absorbs the heat in the hot end of the evaporator 7 and is excited into refrigerant vapor under the evaporation pressure; the residual concentrated solution in the generator 5 enters the absorber 8, is mixed with the low-pressure refrigerant vapor from the evaporator 7, absorbs the low-pressure refrigerant vapor and recovers the original concentration, and the solution with the recovered concentration in the absorber 8 is sent to the generator 5 for continuous circulation; the absorption process is exothermic and requires cooling of the mixed solution in the absorber 8 with mains water.
Finally, it should be noted that: the above embodiments are only for illustrating the technical solutions of the present invention and not for limiting the same, and although the present invention is described in detail with reference to the above embodiments, those of ordinary skill in the art should understand that: modifications and equivalents may be made to the embodiments of the utility model without departing from the spirit and scope of the utility model, which is to be covered by the claims.
Claims (8)
1. A nuclear power unit cogeneration system utilizing the waste heat of condensed water is characterized by comprising a reactor (1), a steam generator (2) and an absorption heat pump;
a gas outlet of the reactor (1) is connected with a hot end inlet of the steam generator (2);
the absorption heat pump comprises a generator (5), a condenser (6), an evaporator (7) and an absorber (8); a hot end inlet of the generator (5) is connected with a hot end outlet of the steam generator (2), a hot end outlet of the generator (5) is connected with a gas inlet of the reactor (1), and a refrigerant outlet end of the generator (5) is sequentially connected with a hot end of the condenser (6), a cold end of the evaporator (7) and a solution inlet of the absorber (8); a solution outlet of the generator (5) is connected with a solution inlet of the absorber (8), and a solution outlet of the absorber (8) is connected with a solution inlet of the generator (5); the cold end inlet of the absorber (8) is connected with a heat supply network water return pipeline, and the cold end outlet of the absorber (8) is connected with a heat supply network water supply pipeline.
2. The cogeneration system of nuclear power generating units utilizing the waste heat of condensed water of claim 1, characterized in that steam is provided in the cold end of the steam generator (2), the outlet of the cold end of the steam generator (2) is connected with the inlet of the steam turbine (3), and the exhaust outlet of the steam turbine (3) is connected with the inlet of the cold end of the steam generator (2).
3. The cogeneration system of nuclear power generating units utilizing the waste heat of condensed water according to claim 2, wherein the exhaust outlet of the steam turbine (3) is connected with the hot end inlet of the evaporator (7), and the hot end outlet of the evaporator (7) is connected with the cold end inlet of the steam generator (2).
4. The cogeneration system of nuclear power generating units using the waste heat of condensed water according to claim 3, characterized in that a water supply heater (4) is arranged between the hot end outlet of the evaporator (7) and the cold end inlet of the steam generator (2), the inlet and outlet of the cold end of the water supply heater (4) are respectively connected with the hot end outlet of the evaporator (7) and the cold end inlet of the steam generator (2), and the extraction outlet of the steam turbine (3) is connected with the hot end of the water supply heater (4).
5. The nuclear power generating unit cogeneration system using condensate water waste heat according to claim 1, wherein a cold end of the condenser (6) is connected between a cold end outlet of the absorber (8) and the heat supply network water supply pipeline, a cold end outlet of the absorber (8) is connected with a cold end inlet of the condenser (6), and a cold end outlet of the condenser (6) is connected with the heat supply network water supply pipeline.
6. The cogeneration system of nuclear power generating units utilizing the waste heat of condensed water according to claim 1, characterized in that a throttle valve (9) is arranged between the hot end of the condenser (6) and the cold end of the evaporator (7).
7. The cogeneration system of nuclear power generating units utilizing the waste heat of condensed water according to claim 1, characterized in that a circulation pump (10) is arranged between the solution outlet of the absorber (8) and the solution inlet of the generator (5).
8. The cogeneration system of nuclear power generating units utilizing the waste heat of condensed water of claim 1, wherein the solution in the absorption heat pump is lithium bromide solution.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202123027887.8U CN216346522U (en) | 2021-12-03 | 2021-12-03 | Nuclear power unit cogeneration system utilizing condensate water waste heat |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202123027887.8U CN216346522U (en) | 2021-12-03 | 2021-12-03 | Nuclear power unit cogeneration system utilizing condensate water waste heat |
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| Publication Number | Publication Date |
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| CN216346522U true CN216346522U (en) | 2022-04-19 |
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| CN202123027887.8U Active CN216346522U (en) | 2021-12-03 | 2021-12-03 | Nuclear power unit cogeneration system utilizing condensate water waste heat |
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2021
- 2021-12-03 CN CN202123027887.8U patent/CN216346522U/en active Active
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