CN105788688A - Thermodynamic system of pressurized water reactor nuclear power plant - Google Patents
Thermodynamic system of pressurized water reactor nuclear power plant Download PDFInfo
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- CN105788688A CN105788688A CN201410822867.5A CN201410822867A CN105788688A CN 105788688 A CN105788688 A CN 105788688A CN 201410822867 A CN201410822867 A CN 201410822867A CN 105788688 A CN105788688 A CN 105788688A
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- pressure
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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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- 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 invention discloses a thermodynamic system of a pressurized water reactor nuclear power plant. The thermodynamic system is characterized in that a pressure vessel (1) is provided, and a reactor (2) is disposed in the pressure vessel; the pressure vessel is connected with a pressure stabilizer (3), a vapor generator (4), and a main circulating pump (5); the pressure stabilizer is respectively connected with the vapor generator and the main circulating pump; the vapor generator is respectively connected with a steam turbine high pressure cylinder (6) and a high pressure heater (17); the steam turbine high pressure cylinder is connected with a steam-water separator reheater (7), which is connected with a shunting type low pressure cylinder (8) of a steam turbine, and the shunting type low pressure cylinder of the steam turbine is respectively connected with a generator (9) and a condenser (10). The thermodynamic system is used for the pressurized water reactor nuclear power plant.
Description
Technical field:
The present invention relates to the therrmodynamic system of a kind of pressurized-water reactor nuclear power plant.
Background technology:
The inefficiency of the therrmodynamic system of currently used nuclear power station.
Summary of the invention:
It is an object of the invention to provide the therrmodynamic system of a kind of pressurized-water reactor nuclear power plant.
Above-mentioned purpose is realized by following technical scheme:
A kind of therrmodynamic system of pressurized-water reactor nuclear power plant, its composition includes: pressure vessel, in described pressure vessel, reactor is installed, described pressure vessel and manostat, steam generator, main circulation pump connects, described manostat respectively with described steam generator, described main circulation pump connects, described steam generator respectively with steam turbine high-pressure cylinder, high-pressure heater connects, described steam turbine high-pressure cylinder is connected with separator, described separator is connected with the shunting low pressure (LP) cylinder of steam turbine, the shunting low pressure (LP) cylinder of described steam turbine respectively with electromotor, condenser connects.
The therrmodynamic system of described pressurized-water reactor nuclear power plant, described condenser is connected with solidifying air water pump, described solidifying air water pump is connected with deep desalting device, described deep desalting device is connected with main solidifying booster, the solidifying booster of described master and one group of low-pressure heater connect, low-pressure heater described in one group is connected with the shunting low pressure (LP) cylinder of described steam turbine, oxygen-eliminating device respectively, described oxygen-eliminating device is connected with feed pump, steam turbine high-pressure cylinder respectively, and described feed pump is connected with described steam turbine high-pressure cylinder.
Beneficial effect:
The present invention ensures the safe operation of reactor, and presurized water reactor does not allow cooling water boiling.Therefore, main circulation pump the pressure of coolant of reactor is sent into up to 12 ~ 16MPa.In the case, even if the temperature of coolant reaches 320 DEG C without vaporization.The heat energy that nuclear fuel released by coolant takes reactor out of, and enters steam generator, by thousands of heat-transfer pipes, imparts heat to the secondary circuit water (pressure is generally lower 8 ~ 11MPa than primary Ioops) outside pipe, makes water boiling produce steam；Entering steam turbine high-pressure cylinder expansion working from steam generator saturated vapor out or micro-superheated steam, high pressure cylinder steam discharge enters separator, and the saturated vapor separated is continued work done by the low pressure (LP) cylinder day being sent into symmetrical flow division after reheating.The exhaust steam making merit condenses into water in condenser, after condensate pump, precision processing device of condensation water, solidifying liter pump, low pressure bleeder heater, oxygen-eliminating device, feed pump and the heating of high-pressure extraction device, again sends steam generator back to.After coolant flows through steam generator, then sent into reactor by main pump and form circulation, constantly the heat in reactor is taken and change out of generation steam.
Accompanying drawing illustrates:
Accompanying drawing 1 is the structural representation of the present invention；
Detailed description of the invention:
Embodiment 1:
A kind of therrmodynamic system of pressurized-water reactor nuclear power plant, its composition includes: pressure vessel 1, reactor 2 is installed in described pressure vessel, described pressure vessel and manostat 3, steam generator 4, main circulation pump 5 connects, described manostat respectively with described steam generator, described main circulation pump connects, described steam generator respectively with steam turbine high-pressure cylinder 6, high-pressure heater 17 connects, described steam turbine high-pressure cylinder is connected with separator 7, described separator is connected with the shunting low pressure (LP) cylinder 8 of steam turbine, the shunting low pressure (LP) cylinder of described steam turbine respectively with electromotor 9, condenser 10 connects.
Embodiment 2:
The therrmodynamic system of the pressurized-water reactor nuclear power plant according to embodiment 1, described condenser is connected with solidifying air water pump 11, described solidifying air water pump is connected with deep desalting device 12, described deep desalting device is connected with main solidifying booster 13, the solidifying booster of described master and one group of low-pressure heater 14 connect, low-pressure heater described in one group is connected with the shunting low pressure (LP) cylinder of described steam turbine, oxygen-eliminating device 15 respectively, described oxygen-eliminating device is connected with feed pump 16, steam turbine high-pressure cylinder 6 respectively, and described feed pump is connected with described steam turbine high-pressure cylinder.
Claims (2)
1. the therrmodynamic system of a pressurized-water reactor nuclear power plant, its composition includes: pressure vessel, it is characterized in that: in described pressure vessel, reactor is installed, described pressure vessel and manostat, steam generator, main circulation pump connects, described manostat respectively with described steam generator, described main circulation pump connects, described steam generator respectively with steam turbine high-pressure cylinder, high-pressure heater connects, described steam turbine high-pressure cylinder is connected with separator, described separator is connected with the shunting low pressure (LP) cylinder of steam turbine, the shunting low pressure (LP) cylinder of described steam turbine respectively with electromotor, condenser connects.
2. the therrmodynamic system of pressurized-water reactor nuclear power plant according to claim 1, it is characterized in that: described condenser is connected with solidifying air water pump, described solidifying air water pump is connected with deep desalting device, described deep desalting device is connected with main solidifying booster, the solidifying booster of described master and one group of low-pressure heater connect, low-pressure heater described in one group is connected with the shunting low pressure (LP) cylinder of described steam turbine, oxygen-eliminating device respectively, described oxygen-eliminating device is connected with feed pump, steam turbine high-pressure cylinder respectively, and described feed pump is connected with described steam turbine high-pressure cylinder.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410822867.5A CN105788688A (en) | 2014-12-26 | 2014-12-26 | Thermodynamic system of pressurized water reactor nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410822867.5A CN105788688A (en) | 2014-12-26 | 2014-12-26 | Thermodynamic system of pressurized water reactor nuclear power plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN105788688A true CN105788688A (en) | 2016-07-20 |
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ID=56389279
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201410822867.5A Withdrawn CN105788688A (en) | 2014-12-26 | 2014-12-26 | Thermodynamic system of pressurized water reactor nuclear power plant |
Country Status (1)
| Country | Link |
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| CN (1) | CN105788688A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109185853A (en) * | 2018-10-17 | 2019-01-11 | 中国船舶重工集团公司第七0三研究所 | A kind of list tank heat-accumulation type hot energy-accumulating power station system |
-
2014
- 2014-12-26 CN CN201410822867.5A patent/CN105788688A/en not_active Withdrawn
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109185853A (en) * | 2018-10-17 | 2019-01-11 | 中国船舶重工集团公司第七0三研究所 | A kind of list tank heat-accumulation type hot energy-accumulating power station system |
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Legal Events
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| C06 | Publication | ||
| PB01 | Publication | ||
| WW01 | Invention patent application withdrawn after publication | ||
| WW01 | Invention patent application withdrawn after publication |
Application publication date: 20160720 |