CN113153466A - Nuclear power heating heat source system - Google Patents
Nuclear power heating heat source system Download PDFInfo
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- CN113153466A CN113153466A CN202110274934.4A CN202110274934A CN113153466A CN 113153466 A CN113153466 A CN 113153466A CN 202110274934 A CN202110274934 A CN 202110274934A CN 113153466 A CN113153466 A CN 113153466A
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- source system
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- 238000010438 heat treatment Methods 0.000 title claims abstract description 68
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 49
- 230000001105 regulatory effect Effects 0.000 claims description 7
- 238000012544 monitoring process Methods 0.000 claims description 6
- 238000012806 monitoring device Methods 0.000 claims description 3
- 239000011148 porous material Substances 0.000 claims description 3
- 230000009467 reduction Effects 0.000 claims description 3
- 238000003912 environmental pollution Methods 0.000 abstract description 6
- 230000006872 improvement Effects 0.000 description 9
- RAHZWNYVWXNFOC-UHFFFAOYSA-N Sulphur dioxide Chemical compound O=S=O RAHZWNYVWXNFOC-UHFFFAOYSA-N 0.000 description 6
- 238000003303 reheating Methods 0.000 description 6
- 229920006395 saturated elastomer Polymers 0.000 description 6
- 238000000926 separation method Methods 0.000 description 5
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 description 4
- 230000000694 effects Effects 0.000 description 4
- 238000000605 extraction Methods 0.000 description 4
- 239000008236 heating water Substances 0.000 description 4
- 229910002092 carbon dioxide Inorganic materials 0.000 description 2
- 239000001569 carbon dioxide Substances 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000005484 gravity Effects 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 230000004044 response Effects 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 238000003916 acid precipitation Methods 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 238000009833 condensation Methods 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 239000000428 dust Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000013486 operation strategy Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 230000002265 prevention Effects 0.000 description 1
- 238000011160 research Methods 0.000 description 1
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Classifications
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K13/00—General layout or general methods of operation of complete plants
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
- F01D15/00—Adaptations of machines or engines for special use; Combinations of engines with devices driven thereby
- F01D15/10—Adaptations for driving, or combinations with, electric generators
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
- F01D17/00—Regulating or controlling by varying flow
- F01D17/10—Final actuators
- F01D17/12—Final actuators arranged in stator parts
- F01D17/14—Final actuators arranged in stator parts varying effective cross-sectional area of nozzles or guide conduits
- F01D17/141—Final actuators arranged in stator parts varying effective cross-sectional area of nozzles or guide conduits by means of shiftable members or valves obturating part of the flow path
- F01D17/145—Final actuators arranged in stator parts varying effective cross-sectional area of nozzles or guide conduits by means of shiftable members or valves obturating part of the flow path by means of valves, e.g. for steam turbines
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
- F01D21/00—Shutting-down of machines or engines, e.g. in emergency; Regulating, controlling, or safety means not otherwise provided for
- F01D21/003—Arrangements for testing or measuring
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K17/00—Using steam or condensate extracted or exhausted from steam engine plant
- F01K17/02—Using steam or condensate extracted or exhausted from steam engine plant for heating purposes, e.g. industrial, domestic
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- Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- General Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Combustion & Propulsion (AREA)
- Engine Equipment That Uses Special Cycles (AREA)
Abstract
The invention discloses a nuclear power heating heat source system, which comprises: the high-pressure steam turbine cylinder, the heat exchanger that is connected with the high-pressure steam turbine cylinder through high-pressure cylinder exhaust pipe and valve to and heat supply pipe network, wherein, the heat supply pipe network circulating water in the heat supply pipe network flows through the heat exchanger and is heated by high-pressure cylinder exhaust steam. Compared with the prior art, the nuclear power heating heat source system uses the exhaust steam of the high-pressure cylinder of the steam turbine as a heating heat source, and the steam does work in the high-pressure cylinder of the steam turbine, so that the heat efficiency of a nuclear power plant can be effectively improved, and the problem of environmental pollution caused by thermal power heating is avoided. In addition, the temperature of condensed water can be increased by the aid of drainage from the heat exchanger to the condenser, efficiency of a nuclear power plant is improved, and heating of the nuclear power plant and participation of the nuclear power plant in peak regulation operation are achieved.
Description
Technical Field
The invention belongs to the technical field of nuclear power, and particularly relates to a nuclear power heating heat source system.
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 power has been developed greatly in recent years as an important clean energy source. With the increasing load peak-valley difference of the power grid, the peak regulation situation of the power system is more and more severe. Due to the increase of the proportion of nuclear power in a power grid, the demand of a power system for a nuclear power unit to participate in power grid peak shaving is increasingly enhanced, and the nuclear power unit is potentially required to participate in peak shaving operation.
In view of this, it is necessary to provide a nuclear power heating heat source system, which can solve the problem of thermal power heating environmental pollution and achieve the purpose of heating in a nuclear power plant and participating in peak shaving in the nuclear power plant.
Disclosure of Invention
The invention aims to: the defects of the prior art are overcome, and the nuclear power heating heat source system is provided, so that the problem of thermal power heating environmental pollution can be solved, and the purposes of heating of a nuclear power plant and participating in peak regulation of the nuclear power plant are achieved.
In order to achieve the above object, the present invention provides a nuclear power heating heat source system, which includes: the high-pressure steam turbine cylinder, the heat exchanger that is connected with the high-pressure steam turbine cylinder through high-pressure cylinder exhaust pipe and valve to and heat supply pipe network, wherein, the heat supply pipe network circulating water in the heat supply pipe network flows through the heat exchanger and is heated by high-pressure cylinder exhaust steam.
As an improvement of the nuclear power heating heat source system, the steam turbine high-pressure cylinder is provided with a tee joint, and the steam turbine high-pressure cylinder is led out of the high-pressure cylinder through the tee joint to exhaust steam to a heat exchanger.
As an improvement of the nuclear power heating heat source system, the nuclear power heating heat source system further comprises a condenser, and drain water generated by heat exchange of exhaust steam of the high-pressure cylinder through the heat exchanger is discharged to the condenser.
As an improvement of the nuclear power heating heat source system, a drainage device is arranged on the high-pressure cylinder exhaust pipe, and drainage generated by heat exchange of high-pressure cylinder exhaust through the heat exchanger is discharged to a condenser through a pore plate for pressure reduction.
As an improvement of the nuclear power heating heat source system, a flow regulating valve and a quick closing valve are arranged on a high-pressure cylinder exhaust pipe between a high-pressure cylinder of the steam turbine and a heat exchanger.
As an improvement of the nuclear power heating heat source system, the quick closing valve is close to the high-pressure cylinder of the steam turbine.
As an improvement of the nuclear power heating heat source system, a radioactivity monitoring device is arranged on the side of the heating pipeline network heated by the heat exchanger.
As an improvement of the nuclear power heating heat source system, a temperature monitoring and alarming device is arranged on a heat supply network water return pipeline of the heat supply network.
As an improvement of the nuclear power heating heat source system, the circulating water of the heat supply network flows through the heat exchanger and is heated by the exhaust steam of the high-pressure cylinder to the temperature of 130-140 ℃, for example, 130 ℃.
As an improvement of the nuclear power heating heat source system, the temperature of the exhaust steam of the high-pressure cylinder is 160-180 ℃, for example 178 ℃.
Compared with the prior art, the nuclear power heating heat source system uses a nuclear power plant for heating, so that the problem of environmental pollution caused by heating of the thermal power plant is solved; the exhaust steam of the high-pressure cylinder of the steam turbine is used as a heating source, and the steam works in the high-pressure cylinder, so that the heat efficiency of the nuclear power plant can be effectively improved; the temperature of condensed water can be increased by the drainage from the heat exchanger to the condenser, so that the efficiency of the nuclear power plant is improved, and the heating of the nuclear power plant and the participation of the nuclear power plant in peak regulation operation are realized.
Drawings
The nuclear power heating heat source system and the technical effects thereof of the present invention will be described in detail with reference to the accompanying drawings and the detailed description, wherein:
FIG. 1 is a schematic diagram of a secondary loop steam-water flow of a nuclear power plant.
FIG. 2 is a schematic diagram of the exhaust steam heating process of the high-pressure cylinder of the nuclear power plant of the nuclear power heating heat source system of the invention.
In the figure:
10-high pressure cylinder of steam turbine; 20- -a heat exchanger; 30-heat supply pipe network; 40- -flow control valve; 50- -quick closing valve; 60- -temperature monitoring and warning device.
Detailed Description
In order to make the objects, technical solutions and technical effects of the present invention more clear, the present invention will be described in further detail below with reference to the accompanying drawings and specific embodiments. It should be understood that the detailed description and specific examples, while indicating the preferred embodiment of the invention, are intended for purposes of illustration only and are not intended to limit the scope of the invention.
Referring to the steam-water flow chart of the secondary loop of the nuclear power plant shown in fig. 1, condensed water generated by condensation of the condenser sequentially passes through the shaft seal heater, the heater 1, the heater 2, the heater 3, the heater 4, the deaerator, the heater 6 and the heater 7 and enters the steam generator. As a heat exchange device, the steam generator heats the condensed water to saturated steam (this partially saturated steam is hereinafter referred to as main steam). The steam turbine includes a high pressure cylinder, an intermediate pressure cylinder, and two or three low pressure cylinders. Main steam enters the high-pressure cylinder through four high-pressure steam inlet pipelines, and each pipeline is provided with a main steam valve and a regulating valve. After expansion work is performed in the high-pressure cylinder, steam is sent to two steam-water separation reheaters (located on two sides of the high-intermediate pressure cylinder) which operate in parallel, and a part of main steam does not enter the high-pressure cylinder but enters the steam-water separation reheater through a steam pipeline to serve as a heating steam source of a secondary reheater in the steam-water separation reheater.
Along with the expansion work in the high-pressure cylinder, the steam humidity is continuously increased, and the exhaust steam humidity of the high-pressure cylinder is as high as 14.2%. If the high-pressure cylinder exhaust directly enters the low-pressure cylinder to do work, the blade of the low-pressure cylinder is seriously scoured and corroded, and the moisture loss is increased. Therefore, a moisture separator reheater is arranged between the high-pressure cylinder and the low-pressure cylinder, and the specific functions of the moisture separator reheater are as follows: 1. removing about 98% of water in the high-pressure cylinder exhaust steam; 2. the temperature of the steam entering the low pressure cylinder is increased to make the steam become superheated steam.
The moisture separator reheater includes a dehumidifier, a primary reheater and a secondary reheater. The steam is firstly dehumidified in a steam-water separator, then is sequentially heated in two stages of reheaters (steam is extracted from a steam turbine No. 7 and is supplied to the first stage of the steam-water separator reheater for reheating, and main steam is supplied to the second stage of the steam-water separator reheater for reheating), and then enters an intermediate pressure cylinder through four reheating steam pipelines, and each reheating steam pipeline is provided with a reheating main steam valve and a regulating valve.
The water drainage system of the moisture separator reheater consists of 3 independent systems, namely a moisture removal device water drainage system, a 1 st-stage reheater water drainage system and a 2 nd-stage reheater water drainage system. The condensed water separated from the shell of the moisture separator reheater is drained to a drain tank by gravity at first, and then enters a deaerator with a higher arrangement position through a drain pump, an electric valve and a regulating valve. Condensate from the 1 st and 2 nd reheaters of the moisture separator reheater is drained by gravity into respective reheater drain tanks. Generally, condensed water collected by a reheater steam trap tank is drained to a No. 6 heater (corresponding to a No. 1 reheater) or a No. 7 heater (corresponding to a No. 2 reheater), an electric valve and a regulating valve are arranged on a steam trap pipeline, and the opening degree of the regulating valve is automatically adjusted according to the liquid level of the steam trap tank. Every drain trap sets up alone and arranges to the urgent drain line of condenser, and the high condition of liquid level appears in heater or the oxygen-eliminating device that corresponds, and the condensate water is arranged to the condenser through urgent drain line.
After the steam entering the intermediate pressure cylinder expands and works in the intermediate pressure cylinder, the steam enters the low pressure cylinder to expand and work, and finally the exhaust steam enters the condenser and is condensed into condensed water. The reheating steam pipelines at the outlets of the two steam generators are also provided with a heating pipeline with an adjusting valve, the steam enters the surface heater according to actual needs, after the heating water is heated, the heating water is supplied to users, the steam is drained to enter the drainage flash tank, and finally enters the steam condenser through the drainage pump, and then is sent into the nuclear island steam generator through the shaft seal heater and the heaters at different levels.
In order to ensure the requirements of the side flow and the temperature of the condensed water under the rated working condition of the nuclear island, the high-pressure cylinder is provided with No. 6 and No. 7 steam extraction ports for heating the condensed water of the No. 6 and No. 7 heaters, wherein a part of No. 7 steam extraction enters a steam-water separation reheater to be used as a heating steam source of a primary reheater, and a part of high-pressure cylinder steam exhaust enters a deaerator to heat the condensed water. The intermediate pressure cylinder is provided with No. 3 and No. 4 steam extraction ports for condensed water of No. 3 and No. 4 heaters. The low pressure cylinder is provided with No. 1 and No. 2 steam extraction ports for condensed water of No. 1 and No. 2 heaters.
Referring to fig. 2, in terms of heat source selection for external heating in a nuclear power plant, high-pressure cylinder exhaust steam which applies work through a high-pressure cylinder may be adopted, and the high-pressure cylinder exhaust steam of a steam turbine is saturated steam with large moisture content, the pressure of the saturated steam is about 9.65bar.a, the humidity of the saturated steam is 14.3%, and the temperature of the saturated steam is about 178 ℃. According to the actual heating load, the exhaust steam amount of a high-pressure cylinder entering a steam-water separation reheater is adjusted, an adjusting valve on a heating pipeline is properly opened, after heating water is heated, the heating water is supplied to a user, steam is drained, enters a drain flash tank, and finally enters a condenser through a drain pump.
Referring to fig. 2, the nuclear heating heat source system of the present invention includes: the system comprises a high-pressure turbine cylinder 10, a heat exchanger 20 connected with the high-pressure turbine cylinder 10 through a high-pressure cylinder exhaust pipe and a valve, and a heat supply pipe network 30, wherein heat supply pipe circulating water in the heat supply pipe network 30 flows through the heat exchanger 20 and is heated by the high-pressure cylinder exhaust.
The tee joint is added on the high-pressure cylinder exhaust pipeline to lead out exhaust steam to the heat exchanger 20, the heat exchanger 20 heats the circulating water of the heat supply network to 140 ℃ by utilizing the high-pressure cylinder exhaust steam at 178 ℃, for example, the temperature is about 130 ℃, the parameter requirement of the long-distance heat supply network 30 is met, the sparse water generated by the exhaust steam is discharged to a condenser (not shown), and the water quantity balance of the two loops is ensured.
The nuclear power heating heat source system further comprises a condenser (not shown), and a drainage device (not shown) is arranged on the high-pressure cylinder exhaust pipeline aiming at the characteristics of high steam humidity and large pipeline drainage quantity. The drainage quantity of starting and normal operation is comprehensively considered, water hammer caused by drainage difficulty is avoided, and generated pipeline drainage is discharged to a condenser through a pore plate in a pressure reduction mode.
According to one embodiment of the invention, a quick closing valve 50 with sensitive response is arranged at a position, close to a main pipe, of a newly led high-pressure cylinder steam exhaust pipeline, and the response time of the quick closing valve 50 meets the requirement of water inflow prevention of the steam turbine so as to ensure the safety of the steam turbine.
Except that the setting through the heater guarantees the containing of the potential radioactivity of two return circuits of nuclear power plant, set up radioactivity monitoring devices (KRT monitoring) in heating pipe network side heater export, judge the condition of revealing through the radioactivity activity of monitoring heat supply network circulating water to combine the operation strategy in time to take measures, prevent the possibility influence that the heat exchanger damage brought. The temperature monitoring and alarming device 60 is arranged on the return water pipeline of the heat supply network, the change condition of the heating load is calculated according to the measured return water temperature value, the load of the generator is adjusted timely through heat balance calculation, the load matching of the machine pile is realized, and the safe and stable operation of the power plant is ensured.
In the illustrated embodiment, the circulating water of the heat supply network flows through the heat exchanger and is heated by the high-pressure cylinder exhaust steam to the water temperature of about 130-. According to the invention, through the analysis and research of the system, a whole set of design scheme for utilizing the exhaust steam of the high-pressure cylinder of the steam turbine as an external heating heat source of the nuclear power plant is formed, the external clean heating of the nuclear power plant can be realized, and meanwhile, the safe and stable operation of equipment, a system and even the whole power plant in the power plant is ensured through a series of measures.
In combination with the detailed description of the embodiment of the invention, compared with the prior art, the nuclear power heating heat source system of the invention uses a nuclear power plant for heating, thereby avoiding the problem of environmental pollution caused by heating of a thermal power plant; the exhaust steam of the high-pressure cylinder of the steam turbine is used as a heating source, and the steam works in the high-pressure cylinder, so that the heat efficiency of the nuclear power plant can be effectively improved; the temperature of condensed water can be increased by the drainage from the heat exchanger to the condenser, so that the efficiency of the nuclear power plant is improved, and the heating of the nuclear power plant and the participation of the nuclear power plant in peak regulation operation are realized.
The present invention can be modified and adapted appropriately from the above-described embodiments, according to the principles described above. Therefore, the present invention is not limited to the specific embodiments disclosed and described above, and some modifications and variations of the present invention should fall within the scope of the claims of the present invention. Furthermore, although specific terms are employed herein, they are used in a generic and descriptive sense only and not for purposes of limitation.
Claims (10)
1. A nuclear power heating heat source system is characterized by comprising: the high-pressure steam turbine cylinder, the heat exchanger that is connected with the high-pressure steam turbine cylinder through high-pressure cylinder exhaust pipe and valve to and heat supply pipe network, wherein, the heat supply pipe network circulating water in the heat supply pipe network flows through the heat exchanger and is heated by high-pressure cylinder exhaust steam.
2. The nuclear power heating heat source system according to claim 1, wherein the steam turbine high-pressure cylinder is provided with a tee joint, and the steam turbine high-pressure cylinder leads out high-pressure cylinder exhaust steam through the tee joint to be communicated with the heat exchanger.
3. The nuclear heating heat source system according to claim 1, further comprising a condenser, and the high-pressure cylinder exhaust steam is discharged to the condenser through a drain produced by heat exchange of the heat exchanger.
4. The nuclear power heating heat source system according to claim 3, wherein a drain device is arranged on the high-pressure cylinder exhaust pipe, and drain water generated by heat exchange of the high-pressure cylinder exhaust through the heat exchanger is discharged to the condenser through a pore plate for pressure reduction.
5. The nuclear power heating heat source system according to claim 1, wherein a flow regulating valve and a quick closing valve are arranged on a high-pressure cylinder exhaust pipe between a high-pressure cylinder of the steam turbine and the heat exchanger.
6. The nuclear heating heat source system of claim 5, wherein the quick-closing valve is proximate to the turbine high pressure cylinder.
7. The nuclear heating heat source system according to claim 1, wherein a radioactivity monitoring device is provided on a side of the heating pipe network heated by the heat exchanger.
8. The nuclear power heating heat source system according to claim 1, wherein a temperature monitoring and alarming device is arranged on a return water pipe of the heat supply network.
9. The nuclear power heating heat source system as claimed in claim 1, wherein the circulating water of the heat supply network flows through the heat exchanger and is heated by the exhaust steam of the high-pressure cylinder to a temperature of 130-140 ℃.
10. The nuclear power heating heat source system as claimed in claim 1, wherein the temperature of the high-pressure cylinder exhaust steam is 160-180 ℃.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110274934.4A CN113153466A (en) | 2021-03-15 | 2021-03-15 | Nuclear power heating heat source system |
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| Application Number | Priority Date | Filing Date | Title |
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| CN202110274934.4A CN113153466A (en) | 2021-03-15 | 2021-03-15 | Nuclear power heating heat source system |
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| CN113153466A true CN113153466A (en) | 2021-07-23 |
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| CN202110274934.4A Pending CN113153466A (en) | 2021-03-15 | 2021-03-15 | Nuclear power heating heat source system |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114635766A (en) * | 2022-01-06 | 2022-06-17 | 国核电力规划设计研究院有限公司 | Valve setting and control system and method for heat supply steam extraction pipeline of pressurized water reactor nuclear power unit |
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| CN102797523A (en) * | 2012-08-16 | 2012-11-28 | 中国核电工程有限公司 | Bleeder steam and exhaust steam comprehensive utilization method for nuclear turbine |
| CN105156161A (en) * | 2015-09-22 | 2015-12-16 | 湖南创元铝业有限公司 | Main reheat steam and main reheat steam bypass system |
| CN107355261A (en) * | 2016-05-09 | 2017-11-17 | 中核辽宁核电有限公司 | A kind of cogeneration method based on large commercial nuclear power generating sets |
| US20190170020A1 (en) * | 2016-06-23 | 2019-06-06 | Lidao ZHANG | Gas turbine and pressurized water reactor steam turbine combined circulation system |
| US20200149433A1 (en) * | 2018-04-19 | 2020-05-14 | Uni-Rising(Beijing) Technology Co., Ltd. | Exhaust steam waste heat recovering and supplying system of air-cooling units in large thermal power plants |
-
2021
- 2021-03-15 CN CN202110274934.4A patent/CN113153466A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102797523A (en) * | 2012-08-16 | 2012-11-28 | 中国核电工程有限公司 | Bleeder steam and exhaust steam comprehensive utilization method for nuclear turbine |
| CN105156161A (en) * | 2015-09-22 | 2015-12-16 | 湖南创元铝业有限公司 | Main reheat steam and main reheat steam bypass system |
| CN107355261A (en) * | 2016-05-09 | 2017-11-17 | 中核辽宁核电有限公司 | A kind of cogeneration method based on large commercial nuclear power generating sets |
| US20190170020A1 (en) * | 2016-06-23 | 2019-06-06 | Lidao ZHANG | Gas turbine and pressurized water reactor steam turbine combined circulation system |
| US20200149433A1 (en) * | 2018-04-19 | 2020-05-14 | Uni-Rising(Beijing) Technology Co., Ltd. | Exhaust steam waste heat recovering and supplying system of air-cooling units in large thermal power plants |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114635766A (en) * | 2022-01-06 | 2022-06-17 | 国核电力规划设计研究院有限公司 | Valve setting and control system and method for heat supply steam extraction pipeline of pressurized water reactor nuclear power unit |
| CN114635766B (en) * | 2022-01-06 | 2024-02-09 | 国核电力规划设计研究院有限公司 | Valve setting and controlling system and method for heat supply steam extraction pipeline of pressurized water reactor nuclear power unit |
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Application publication date: 20210723 |