CN107355260A - A kind of co-generation unit based on large commercial nuclear power generating sets - Google Patents
A kind of co-generation unit based on large commercial nuclear power generating sets Download PDFInfo
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- CN107355260A CN107355260A CN201610300797.6A CN201610300797A CN107355260A CN 107355260 A CN107355260 A CN 107355260A CN 201610300797 A CN201610300797 A CN 201610300797A CN 107355260 A CN107355260 A CN 107355260A
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 46
- 238000010438 heat treatment Methods 0.000 claims abstract description 22
- 238000010248 power generation Methods 0.000 claims abstract description 21
- 230000001105 regulatory effect Effects 0.000 claims description 22
- 239000002826 coolant Substances 0.000 claims description 20
- 230000003020 moisturizing effect Effects 0.000 claims description 14
- 238000012544 monitoring process Methods 0.000 claims description 9
- 230000005855 radiation Effects 0.000 claims description 9
- 238000006392 deoxygenation reaction Methods 0.000 claims description 4
- 230000002045 lasting effect Effects 0.000 claims description 3
- 230000001052 transient effect Effects 0.000 claims description 3
- 230000001960 triggered effect Effects 0.000 claims description 2
- 239000003795 chemical substances by application Substances 0.000 claims 1
- 230000005611 electricity Effects 0.000 abstract description 5
- 238000003912 environmental pollution Methods 0.000 abstract description 5
- 239000000567 combustion gas Substances 0.000 abstract description 4
- 238000000034 method Methods 0.000 abstract description 2
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 description 6
- 229910002092 carbon dioxide Inorganic materials 0.000 description 3
- 239000001569 carbon dioxide Substances 0.000 description 3
- MWUXSHHQAYIFBG-UHFFFAOYSA-N nitrogen oxide Inorganic materials O=[N] MWUXSHHQAYIFBG-UHFFFAOYSA-N 0.000 description 3
- 239000003245 coal Substances 0.000 description 2
- 230000006837 decompression Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- VNWKTOKETHGBQD-UHFFFAOYSA-N methane Chemical compound C VNWKTOKETHGBQD-UHFFFAOYSA-N 0.000 description 2
- 240000002853 Nelumbo nucifera Species 0.000 description 1
- 235000006508 Nelumbo nucifera Nutrition 0.000 description 1
- 235000006510 Nelumbo pentapetala Nutrition 0.000 description 1
- UCKMPCXJQFINFW-UHFFFAOYSA-N Sulphide Chemical compound [S-2] UCKMPCXJQFINFW-UHFFFAOYSA-N 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- CUZMQPZYCDIHQL-VCTVXEGHSA-L calcium;(2s)-1-[(2s)-3-[(2r)-2-(cyclohexanecarbonylamino)propanoyl]sulfanyl-2-methylpropanoyl]pyrrolidine-2-carboxylate Chemical compound [Ca+2].N([C@H](C)C(=O)SC[C@@H](C)C(=O)N1[C@@H](CCC1)C([O-])=O)C(=O)C1CCCCC1.N([C@H](C)C(=O)SC[C@@H](C)C(=O)N1[C@@H](CCC1)C([O-])=O)C(=O)C1CCCCC1 CUZMQPZYCDIHQL-VCTVXEGHSA-L 0.000 description 1
- 238000004140 cleaning Methods 0.000 description 1
- 239000003034 coal gas Substances 0.000 description 1
- 238000002485 combustion reaction Methods 0.000 description 1
- 238000009833 condensation Methods 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000000428 dust Substances 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 230000002209 hydrophobic effect Effects 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 239000003345 natural gas Substances 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 239000013589 supplement Substances 0.000 description 1
- 230000005619 thermoelectricity Effects 0.000 description 1
Classifications
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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
-
- 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
- F01K11/00—Plants characterised by the engines being structurally combined with boilers or condensers
- F01K11/02—Plants characterised by the engines being structurally combined with boilers or condensers the engines being turbines
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F24—HEATING; RANGES; VENTILATING
- F24D—DOMESTIC- OR SPACE-HEATING SYSTEMS, e.g. CENTRAL HEATING SYSTEMS; DOMESTIC HOT-WATER SUPPLY SYSTEMS; ELEMENTS OR COMPONENTS THEREFOR
- F24D3/00—Hot-water central heating systems
- F24D3/02—Hot-water central heating systems with forced circulation, e.g. by pumps
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F24—HEATING; RANGES; VENTILATING
- F24D—DOMESTIC- OR SPACE-HEATING SYSTEMS, e.g. CENTRAL HEATING SYSTEMS; DOMESTIC HOT-WATER SUPPLY SYSTEMS; ELEMENTS OR COMPONENTS THEREFOR
- F24D2200/00—Heat sources or energy sources
- F24D2200/32—Heat sources or energy sources involving multiple heat sources in combination or as alternative heat sources
-
- 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
- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P80/00—Climate change mitigation technologies for sector-wide applications
- Y02P80/10—Efficient use of energy, e.g. using compressed air or pressurized fluid as energy carrier
- Y02P80/15—On-site combined power, heat or cool generation or distribution, e.g. combined heat and power [CHP] supply
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- Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- General Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Combustion & Propulsion (AREA)
- Physics & Mathematics (AREA)
- Thermal Sciences (AREA)
- Engine Equipment That Uses Special Cycles (AREA)
Abstract
The invention belongs to nuclear power heat supply process field, and in particular to a kind of co-generation unit based on large commercial nuclear power generating sets.The co-generation unit of the present invention, including：Nuclear steam supply system, power generation circuit, exhaust steam supply loop and heat supply network circulating water loop, wherein, the nuclear steam supply system is used to provide steam, and the power generation circuit is used to utilize the part steam-electric power；The exhaust steam supply loop is used to extract another some vapor from power generation circuit and be exchanged heat with heat supply network circulating water loop；The heat supply network circulating water loop is used to exchange heat between exhaust steam supply loop and user's heat supply network, by the heat transfer in exhaust steam supply loop to user's heat supply network, realizes core steam heating.The present invention solves the technical problem that the warm factory of existing coal-fired and combustion gas can bring environmental pollution, and the weary steam to be generated electricity using nuclear power plant is heated, it is therefore prevented that the generation for the problem of environmental pollution that factory can bring is warmed up in coal-fired and combustion gas.
Description
Technical field
The invention belongs to nuclear power heat supply process field, and in particular to a kind of based on large commercial nuclear power generating sets
Co-generation unit.
Background technology
At present, the urban heat supplying factory overwhelming majority of the northern area of China is used as main combustion using coal and natural gas
Material.Coal heating factory can bring the row of dust, sulfide, nitrogen oxides and carbon dioxide because coal-fired
Put, these emissions can all cause the pollution of atmospheric environment, cause haze and greenhouse effects.Natural hot air heating
Although carbon dioxide only discharges in factory, carbon dioxide is also to cause one of main arch-criminal of greenhouse effects.
The northern area of China is completed and is being continuously increased building nuclear power generating sets quantity, and local government wishes
Nuclear power plant is hoped while power generation, can bear more local public services obligatioies, and large-scale core
Power plant realizes that cogeneration is wherein important option, large nuclear-power factory cogeneration can provide cleaning,
While efficient electric energy and thermal source, problem of environmental pollution caused by solving coal heating, is enhancement of environment
Very big help is played, and is increased economic efficiency, ensures and improve people's livelihood quality, improves nuclear power plant's heat energy
Comprehensive utilization；Meanwhile to ensure the security and economy of nuclear power, nuclear power generating sets typically require tape base lotus
Operation at full power, however, as nuclear power accounts for incrementally increasing for power network total installation of generating capacity proportion, nuclear power generating sets
It has been trend of the times to possess peak regulating function, and large nuclear-power factory configuration city heat supply function realizes cogeneration
It is the important means of nuclear power generating sets peak regulation.Large nuclear-power factory configuration city heat supply function realizes cogeneration,
It is the act achieved many things at one stroke, saves the energy, improve environment, improve heating quality, improve nuclear energy comprehensive utilization
It can be embodied conscientiously etc. benefit.The present invention using China the third generation nuclear reactor art built for support,
City heat supply is realized using extracted steam from turbine, proposes complete cogeneration system design side of large nuclear-power factory
Case.
The content of the invention
The technical problem to be solved in the invention is：Factory is warmed up in existing coal-fired and combustion gas can bring environmental pollution
The problem of.
Technical scheme is as described below：
A kind of co-generation unit based on large commercial nuclear power generating sets, including：Nuclear steam supply system,
Power generation circuit, exhaust steam supply loop and heat supply network circulating water loop, wherein, the nuclear steam supply system is used
In providing steam, the steam that nuclear steam supply system provides can circulate in the power generation circuit；It is described
Power generation circuit is used to utilize the part steam-electric power；The exhaust steam supply loop is used for from power generation circuit
Extract another some vapor and exchanged heat with heat supply network circulating water loop, heat and circulated in heat supply network circulating water loop
The water of flowing；The heat supply network circulating water loop is used to exchange heat between exhaust steam supply loop and user's heat supply network,
By the heat transfer in exhaust steam supply loop to user's heat supply network, core steam heating is realized.
Preferably, the nuclear steam supply system has nuclear reactor, the main pump being sequentially connected by pipeline
And steam generator, the nuclear reactor are used to add the cooling agent circulated in nuclear steam supply system
Heat.The main pump is used to provide power for the closed cycle in nuclear steam supply system.The steam generation
Device is used to produce steam using the cooling agent of high temperature.The high temperature coolant heated by nuclear reactor is anti-from core
Answer the coolant flow of heap to export outflow, the coolant entrance of steam generator is flowed into by pipeline, by changing
Flowed out after heat from the coolant outlet of steam generator, then the entrance of main pump is flowed into by pipeline, by master
After pump increase kinetic energy, flowed out from the outlet of main pump, the coolant flow of nuclear reactor is then flowed back to by pipeline
Entrance, form closed cycle.
Preferably, the power generation circuit has steam turbine, condenser, the first low-pressure heater, second low
Press heater, main feed pump, high-pressure heater and generator.The steam turbine is used for the heat energy of steam
It is converted into the rotation function of steam turbine.The condenser is used to the weary steam for finishing work(being condensed into water.The
One low-pressure heater and the second low-pressure heater are used to that working medium heating therein will to be flowed into.Main feed pump is used for
Kinetic energy is provided to the working medium circulation in power generation circuit.High-pressure heater is used to that working medium heating therein will to be flowed into,
The generator is used to generate electricity under the drive of steam turbine.
Preferably, the steam turbine has steam turbine high-pressure cylinder and turbine low pressure cylinder, from steam generator
The steam of steam (vapor) outlet outflow first flows into steam turbine high-pressure cylinder, then flows into turbine low pressure cylinder.Steam turbine is high
Cylinder pressure and turbine low pressure cylinder drive generator rotary electrification jointly.
Preferably, the exhaust steam supply loop has non-return valve, the first isolating valve, the first regulating valve,
One heat exchanger and the first drainage pump.The entrance of non-return valve is connected to steam turbine high-pressure cylinder and steam turbine low-pressure
Jet chimney between cylinder so that flow into steam turbine low-pressure from a steam part for steam turbine high-pressure cylinder outflow
Cylinder, another part flow into non-return valve.The outlet of non-return valve has been sequentially connected in series the first isolating valve, the first regulation
Valve.Non-return valve can prevent the steam for flowing into exhaust steam supply loop from flowing backwards, it is therefore prevented that flow backwards and drawn by steam
Major accident during the Turbo-generator Set transient state of hair.The outlet of first regulating valve is connected to by pipeline
The high temperature side entrance of one heat exchanger, the high temperature side outlet of first heat exchanger are connected to first by pipeline
The entrance of drainage pump, the outlet of the first drainage pump are connected to the entrance of the second low-pressure heater by pipeline.
Preferably, the heat supply network circulating water loop includes：Second heat exchanger, backwater booster pump, moisturizing remove
Oxygen device, small pump and the second drainage pump.The outlet of first heat exchanger low temperature side is connected to by pipeline
The entrance of two heat exchanger high temperature sides, the outlet of the second heat exchanger high temperature side have been sequentially connected in series backwater by pipeline
Booster pump and the second drainage pump, the outlet of the second drainage pump are connected to first heat exchanger low temperature by pipeline
The entrance of side.The admission port of moisturizing oxygen-eliminating device is connected to moisturizing source, and the deoxygenation water out of moisturizing oxygen-eliminating device connects
The entrance of small pump is connected to, the outlet of small pump is connected to backwater booster pump outlet and the second hydrophobic pump intake
Between pipeline on.The low temperature of second heat exchanger surveys the pipeline for being connected to user's heat supply network, for giving user's heat
Net provides thermal source.
Preferably, the exhaust steam supply loop is additionally provided with back-up system, in nuclear steam supply system
Lasting heat supply is ensured during shutdown.Back-up system include the second regulating valve, pressure-reducing valve, the second isolating valve and
Reserve steam source.One end of second isolating valve is connected to reserve steam source, and the other end has been sequentially connected in series decompression
Valve and the second regulating valve, the other end of the second regulating valve are connected to the high temperature side entrance of first heat exchanger.
When nuclear steam supply system shutdown, the steam in reserve steam source can pass sequentially through the second isolating valve, subtract
Pressure valve and the second regulating valve flow into the high temperature side entrance of first heat exchanger.
Preferably, between the entrance of the outlet of first heat exchanger low temperature side and the second heat exchanger high temperature side
Pipeline on be additionally provided with Radiation monitoring instrument, for monitoring the water circulated in heat supply network circulating water loop
Containing radiation event.From the water of first heat exchanger low temperature side outlet outflow, Radiation monitoring instrument is firstly flowed through,
The entrance of the second heat exchanger high temperature side is flowed into again.
Beneficial effects of the present invention are：
(1) the weary steam that the present invention is generated electricity using nuclear power plant is heated, it is therefore prevented that factory is warmed up in coal-fired and combustion gas
The generation for the problem of environmental pollution that can be brought.
(2) by being returned for 4 to region heat supply network end user from active nuclear power plant's primary Ioops system
The setting on road, and the reasonable setting of radioactivity monitoring, prevent radioactive substance to be discharged into heat supply network and finally use
Family.
Brief description of the drawings
Fig. 1 is the composition schematic diagram of the co-generation unit of the present invention；
Wherein, 1- nuclear steam supply systems, 101- nuclear reactors, 102- main pumps, 103- steam generators,
2- power generation circuits, 201- steam turbines, 202- condensers, the low-pressure heaters of 203- first, the low pressure of 204- second
Heater, 205- main feed pumps, 206- high-pressure heaters, 207- steam turbine high-pressure cylinders, 208- steam turbines are low
Cylinder pressure, 209- generators, 3- exhaust steam supply loops, 301- non-return valves, the isolating valves of 302- first, 303-
One regulating valve, 304- first heat exchangers, the drainage pumps of 305- first, the regulating valves of 306- second, 307- decompressions
Valve, the isolating valves of 308- second, 309- reserve steams source, 4- heat supply network circulating water loops, the heat exchangers of 401- second,
402- backwater booster pumps, 403- moisturizing oxygen-eliminating devices, 404- small pumps, the drainage pumps of 405- second, 406- radiation
Measuring instrument.
Embodiment
A kind of thermoelectricity based on large commercial nuclear power generating sets of the present invention is joined with reference to the accompanying drawings and examples
Production system is described in detail.
The co-generation unit based on large commercial nuclear power generating sets of the present invention, including nuclear steam supply system
1, the nuclear steam supply system 1 has nuclear reactor 101, the main pump 102 being sequentially connected by pipeline
With steam generator 103, the nuclear reactor 101 is used to circulate in nuclear steam supply system 1
Coolant heating.The main pump 102, which is used to provide for the closed cycle in nuclear steam supply system 1, to be moved
Power.The steam generator 103 is used to produce steam using the cooling agent of high temperature.By nuclear reactor 101
The high temperature coolant of heating exports outflow from the coolant flow of nuclear reactor 101, and steam is flowed into by pipeline
The coolant entrance of generator 103, flowed out after heat exchange from the coolant outlet of steam generator 103,
The entrance of main pump 102 is flowed into by pipeline again, after main pump 102 increases kinetic energy, from main pump 102
Outlet outflow, the coolant flow inlet of nuclear reactor 101 is then flowed back to by pipeline, forms closed cycle.
The co-generation unit of the present invention, in addition to power generation circuit 2, power generation circuit 2 have steam turbine 201,
Condenser 202, the first low-pressure heater 203, the second low-pressure heater 204, main feed pump 205, height
Press heater 206 and generator 209.The steam turbine 201 is used to the heat energy of steam being converted into steamer
The rotation function of machine 201.The condenser 202 is used to the weary steam for finishing work(being condensed into water.First
The low-pressure heater 204 of low-pressure heater 203 and second is used to that working medium heating therein will to be flowed into.Main feedwater
Pump 205 is used to provide kinetic energy to the working medium circulation in power generation circuit 2.High-pressure heater 206 is used for will stream
Enter working medium heating therein, the generator 209 is used to generate electricity under the drive of steam turbine 201.
Steam turbine is flowed into by pipeline from the high temperature and high pressure steam of the steam (vapor) outlet of steam generator 103 outflow
201 steam inlet, the associated components rotation of pushing turbine 201, and drive and connect with steam turbine 201
The generator 207 connect generates electricity.The weary steam for finishing work(flows out from the steam (vapor) outlet of steam turbine 201, passes through
Pipeline flows into the steam inlet of condenser 202, it is condensed after weary steam be changed into condensed water and from condenser
202 condensation water out outflow, condensed water pass through the first low-pressure heater 203 and the second low pressure successively again
Main feed pump 205 is flowed into after the heating of heater 204, is flowed into after main feed pump 205 increases kinetic energy
In high-pressure heater 206, the condensate return after the heating of high-pressure heater 206 returns steam generator
103 feed-water intake, form circulation.
Steam turbine 201 has steam turbine high-pressure cylinder 207 and turbine low pressure cylinder 208, from steam generator
The steam of 103 steam (vapor) outlets outflow first flows into steam turbine high-pressure cylinder 207, then flows into turbine low pressure cylinder 208.
Steam turbine high-pressure cylinder 207 and turbine low pressure cylinder 208 drive the rotary electrification of generator 209 jointly.
The co-generation unit of the present invention, in addition to exhaust steam supply loop 3.Exhaust steam supply loop 3 has
Non-return valve 301, the first isolating valve 302, the first regulating valve 303, first heat exchanger 304 and first are dredged
Water pump 305.
The entrance of non-return valve 301 is connected between steam turbine high-pressure cylinder 207 and turbine low pressure cylinder 208
Jet chimney so that the steam part flowed out from steam turbine high-pressure cylinder 207 flows into turbine low pressure cylinder
208, another part flows into non-return valve 301.The outlet of non-return valve 301 be sequentially connected in series the first isolating valve 302,
First regulating valve 303.Non-return valve 301 can prevent the steam for flowing into exhaust steam supply loop 3 from flowing backwards, and prevent
Major accident when triggered Turbo-generator Set transient state is flow backwards by steam is stopped.First regulating valve 303
Outlet the high temperature side entrance of first heat exchanger 304, first heat exchanger 304 are connected to by pipeline
High temperature side outlet the entrance of the first drainage pump 305 is connected to by pipeline, the first drainage pump 305 goes out
Mouth is connected to the entrance of the second low-pressure heater 204 by pipeline.
Steam turbine high-pressure cylinder 207 flows out steam and flows through non-return valve 301, the first isolating valve 302 and the successively
After one regulating valve 303, the high temperature side entrance of first heat exchanger 304 is flowed into, from first after heat exchange
The high temperature side outlet outflow of heat exchanger 304, then flow into the after the first drainage pump 305 supplements kinetic energy
Two low-pressure heaters 204 heat again.
Power generation circuit 2 and exhaust steam supply loop 3 collectively form a closed circulation system.
Exhaust steam supply loop 3 is additionally provided with back-up system, for being protected in 1 shutdown of nuclear steam supply system
Hinder lasting heat supply.Back-up system includes the second regulating valve 306, pressure-reducing valve 307, the second isolating valve 308
With reserve steam source 309.One end of second isolating valve 308 is connected to reserve steam source, and the other end is successively
The regulating valve 306 of pressure-reducing valve 307 and second is in series with, the other end of the second regulating valve 306 is connected to first
The high temperature side entrance of heat exchanger 304.When 1 shutdown of nuclear steam supply system, reserve steam source 309
Steam can pass sequentially through the second isolating valve 308, the regulating valve 306 of pressure-reducing valve 307 and second flows into the
The high temperature side entrance of one heat exchanger 304.
The co-generation unit of the present invention, in addition to heat supply network circulating water loop 4.Heat supply network circulating water loop 4
Including：Second heat exchanger 401, backwater booster pump 402, moisturizing oxygen-eliminating device 403, small pump 404 and
Two drainage pumps 405.
The outlet of the low temperature side of first heat exchanger 304 is connected to the high temperature side of the second heat exchanger 401 by pipeline
Entrance, the outlet of the high temperature side of the second heat exchanger 401 has been sequentially connected in series backwater booster pump 402 by pipeline
With the second drainage pump 405, the outlet of the second drainage pump 405 is connected to first heat exchanger 304 by pipeline
The entrance of low temperature side.The admission port of moisturizing oxygen-eliminating device 403 is connected to moisturizing source, moisturizing oxygen-eliminating device 403
Deoxygenation water out is connected to the entrance of small pump 404, and the outlet of small pump 404 is connected to backwater booster pump
On pipeline between 402 outlets and the entrance of the second drainage pump 405.
The second heat exchanger is flowed into from the water by heating of the low temperature side outlet of first heat exchanger 304 outflow
401 high temperature side entrance, after heat exchange, flowed out from the high temperature side outlet of the second heat exchanger 401, warp
The second drainage pump 405 is flowed into after crossing the increase hydraulic pressure of backwater booster pump 402, is increased by the second drainage pump 405
The low temperature side entrance of first heat exchanger 304 is flowed back to after adding kinetic energy, forms closed cycle.When heat supply network recirculated water
When quantity of circulating water in loop 4 is reduced, moisturizing oxygen-eliminating device 403 is in the future at the water progress deoxygenation at self-complementary water source
Reason, then be pumped to by small pump 404 in circulating water loop.
Between the entrance of the outlet of the low temperature side of first heat exchanger 304 and the high temperature side of the second heat exchanger 401
Pipeline on Radiation monitoring instrument 406 can also be set, followed for monitoring in heat supply network circulating water loop 4
The water of ring contains radiation event.From the water of the low temperature side outlet of first heat exchanger 304 outflow, spoke is firstly flowed through
Measuring instrument 406 is penetrated, then flows into the entrance of the high temperature side of the second heat exchanger 401.
The low temperature of second heat exchanger 401 surveys the pipeline for being connected to user's heat supply network, for being provided to user's heat supply network
Thermal source.
Claims (8)
1. a kind of co-generation unit based on large commercial nuclear power generating sets, including：Nuclear steam supply system
(1), power generation circuit (2), exhaust steam supply loop (3) and heat supply network circulating water loop (4), its feature exist
In：The nuclear steam supply system (1) is used to provide steam, what nuclear steam supply system (1) provided
Steam can circulate in the power generation circuit (2)；The power generation circuit (2) is used to utilize part institute
State steam-electric power；The exhaust steam supply loop (3), which is used to extract from power generation circuit (2), separately partly steams
Vapour is simultaneously exchanged heat with heat supply network circulating water loop (4), recycle stream in heating heat supply network circulating water loop (4)
Dynamic water；The heat supply network circulating water loop (4) be used for exhaust steam supply loop (3) and user's heat supply network it
Between exchange heat, by the heat transfer in exhaust steam supply loop (3) to user's heat supply network, realize core steam heating.
2. the co-generation unit as claimed in claim 1 based on large commercial nuclear power generating sets, its feature
It is：The nuclear steam supply system (1) have be sequentially connected by pipeline nuclear reactor (101),
Main pump (102) and steam generator (103), the nuclear reactor (101) are used to supply core steam
The coolant heating circulated in system (1)；The main pump (102) is used for for core steam supply system
Closed cycle in system (1) provides power；The steam generator (103) is used to utilize the cold of high temperature
But agent produces steam；High temperature coolant by nuclear reactor (101) heating is from nuclear reactor (101)
Coolant flow outlet outflow, pass through pipeline flow into steam generator (103) coolant entrance, pass through
Flowed out after heat exchange from the coolant outlet of steam generator (103), then main pump (102) is flowed into by pipeline
Entrance, after main pump (102) increases kinetic energy, flowed out from the outlet of main pump (102), Ran Houtong
Piping flows back to the coolant flow inlet of nuclear reactor (101), forms closed cycle.
3. the co-generation unit as claimed in claim 2 based on large commercial nuclear power generating sets, its feature
It is：The power generation circuit (2) has steam turbine (201), condenser (202), the first low-pressure heating
Device (203), the second low-pressure heater (204), main feed pump (205), high-pressure heater (206) and
Generator (209)；The steam turbine (201) is used to the heat energy of steam being converted into steam turbine (201)
Rotation function；The condenser (202) is used to the weary steam for finishing work(being condensed into water；First low pressure
Heater (203) and the second low-pressure heater (204) are used to that working medium heating therein will to be flowed into；Master gives
Water pump (205) is used to provide kinetic energy to the working medium circulation in power generation circuit (2)；High-pressure heater (206)
For that will flow into working medium heating therein, the generator (209) is used for the band in steam turbine (201)
Dynamic lower generating.
4. the co-generation unit as claimed in claim 3 based on large commercial nuclear power generating sets, its feature
It is：The steam turbine (201) has steam turbine high-pressure cylinder (207) and turbine low pressure cylinder (208),
Steam turbine high-pressure cylinder (207) is first flowed into from the steam of steam generator (103) steam (vapor) outlet outflow, then is flowed
Enter turbine low pressure cylinder (208)；Steam turbine high-pressure cylinder (207) and turbine low pressure cylinder (208) are common
Drive generator (209) rotary electrification.
5. the co-generation unit as claimed in claim 4 based on large commercial nuclear power generating sets, its feature
It is：The exhaust steam supply loop (3) has non-return valve (301), the first isolating valve (302), first
Regulating valve (303), first heat exchanger (304) and the first drainage pump (305)；Non-return valve (301)
Entrance be connected to jet chimney between steam turbine high-pressure cylinder (207) and turbine low pressure cylinder (208),
So that turbine low pressure cylinder (208) is flowed into from a steam part for steam turbine high-pressure cylinder (207) outflow, separately
A part flows into non-return valve (301)；The outlet of non-return valve (301) be sequentially connected in series the first isolating valve (302),
First regulating valve (303)；Non-return valve (301) can prevent to flow into the steam of exhaust steam supply loop (3)
Flow backwards, it is therefore prevented that major accident during triggered Turbo-generator Set transient state is flow backwards by steam；First adjusts
The outlet of section valve (303) is connected to the high temperature side entrance of first heat exchanger (304) by pipeline, the
The high temperature side outlet of one heat exchanger (304) is connected to the entrance of the first drainage pump (305) by pipeline,
The outlet of first drainage pump (305) is connected to the entrance of the second low-pressure heater (204) by pipeline.
6. the co-generation unit as claimed in claim 5 based on large commercial nuclear power generating sets, its feature
It is：The heat supply network circulating water loop (4) includes：Second heat exchanger (401), backwater booster pump (402),
Moisturizing oxygen-eliminating device (403), small pump (404) and the second drainage pump (405)；First heat exchanger (304)
The outlet of low temperature side is connected to the entrance of the second heat exchanger (401) high temperature side, the second heat exchanger by pipeline
(401) outlet of high temperature side has been sequentially connected in series backwater booster pump (402) and the second drainage pump by pipeline
(405), it is low by pipeline to be connected to first heat exchanger (304) for the outlet of the second drainage pump (405)
The entrance of warm side；The admission port of moisturizing oxygen-eliminating device (403) is connected to moisturizing source, moisturizing oxygen-eliminating device (403)
Deoxygenation water out be connected to the entrances of small pump (404), the outlet of small pump (404) is connected to back
Water booster pump (402) is exported on the pipeline between the second drainage pump (405) entrance；Second heat exchanger
(401) low temperature surveys the pipeline for being connected to user's heat supply network, for providing thermal source to user's heat supply network.
7. the co-generation unit as claimed in claim 6 based on large commercial nuclear power generating sets, its feature
It is：The exhaust steam supply loop (3) is additionally provided with back-up system, in nuclear steam supply system (1)
Lasting heat supply is ensured during shutdown；Back-up system include the second regulating valve (306), pressure-reducing valve (307),
Second isolating valve (308) and reserve steam source (309)；One end of second isolating valve (308) is connected to
Reserve steam source, the other end have been sequentially connected in series pressure-reducing valve (307) and the second regulating valve (306), and second adjusts
The other end of section valve (306) is connected to the high temperature side entrance of first heat exchanger (304)；When core steam
During supply system (1) shutdown, the steam of reserve steam source (309) can pass sequentially through the second isolating valve
(308), pressure-reducing valve (307) and the second regulating valve (306) flow into the height of first heat exchanger (304)
Warm side entrance.
8. the co-generation unit as claimed in claim 7 based on large commercial nuclear power generating sets, its feature
It is：In the outlet of first heat exchanger (304) low temperature side and the second heat exchanger (401) high temperature side
Radiation monitoring instrument (406) is additionally provided with pipeline between entrance, for monitoring heat supply network circulating water loop
(4) water circulated in contains radiation event；Flowed out from first heat exchanger (304) low temperature side outlet
Water, firstly flow through Radiation monitoring instrument (406), then flow into the entrance of the second heat exchanger (401) high temperature side.
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| CN201610300797.6A CN107355260B (en) | 2016-05-09 | 2016-05-09 | Cogeneration system based on large commercial nuclear power unit |
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| CN201610300797.6A CN107355260B (en) | 2016-05-09 | 2016-05-09 | Cogeneration system based on large commercial nuclear power unit |
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| CN107355260B CN107355260B (en) | 2024-03-19 |
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Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN107420878A (en) * | 2017-03-28 | 2017-12-01 | 中国核电工程有限公司 | It is a kind of to carry out vapour, heat, the system of CCHP using nuclear energy |
| CN108331628A (en) * | 2018-04-24 | 2018-07-27 | 贵州电网有限责任公司 | A kind of power supply system of Anti-icing of Transmission Lines mitigation on-Line Monitor Device |
| CN108988739A (en) * | 2018-08-22 | 2018-12-11 | 中国科学院合肥物质科学研究院 | A kind of nuclear reactor joint wind-force and solar energy grid-connected photovoltaic system |
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| CN109058767A (en) * | 2018-10-08 | 2018-12-21 | 江苏金合能源科技有限公司 | A kind of storage of nuclear reactor steam and heating system |
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| CN107420878A (en) * | 2017-03-28 | 2017-12-01 | 中国核电工程有限公司 | It is a kind of to carry out vapour, heat, the system of CCHP using nuclear energy |
| CN108331628A (en) * | 2018-04-24 | 2018-07-27 | 贵州电网有限责任公司 | A kind of power supply system of Anti-icing of Transmission Lines mitigation on-Line Monitor Device |
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| CN109065193A (en) * | 2018-07-27 | 2018-12-21 | 中国核动力研究设计院 | A kind of double cooling irradiation test system and methods |
| CN108988739A (en) * | 2018-08-22 | 2018-12-11 | 中国科学院合肥物质科学研究院 | A kind of nuclear reactor joint wind-force and solar energy grid-connected photovoltaic system |
| CN108988739B (en) * | 2018-08-22 | 2020-12-11 | 中国科学院合肥物质科学研究院 | Nuclear reactor combined wind power and solar photovoltaic grid-connected power generation system |
| CN109058767A (en) * | 2018-10-08 | 2018-12-21 | 江苏金合能源科技有限公司 | A kind of storage of nuclear reactor steam and heating system |
| CN109058767B (en) * | 2018-10-08 | 2023-10-03 | 江苏金合能源科技有限公司 | Nuclear reactor steam storage and heating system |
| CN113906523A (en) * | 2019-04-12 | 2022-01-07 | 泰拉能源公司 | Nuclear heating plant with load tracking power generation |
| CN111322789A (en) * | 2020-03-16 | 2020-06-23 | 明阳智慧能源集团股份公司 | Nuclear power and wind power combined hydrogen production and heat supply system |
| CN111834026B (en) * | 2020-06-12 | 2023-03-14 | 中国核电工程有限公司 | Industrial steam production system for pressurized water reactor nuclear power unit |
| CN111834026A (en) * | 2020-06-12 | 2020-10-27 | 中国核电工程有限公司 | Industrial steam production system for pressurized water reactor nuclear power unit |
| CN113091030A (en) * | 2021-04-06 | 2021-07-09 | 上海核工程研究设计院有限公司 | Nuclear power and thermal power coupling steam supply system |
| CN113113161A (en) * | 2021-04-06 | 2021-07-13 | 上海核工程研究设计院有限公司 | Nuclear energy steam supply system |
| CN113389606A (en) * | 2021-06-30 | 2021-09-14 | 国核电力规划设计研究院有限公司 | Direct heat supply system and method for steam exhaust and extraction of steam of intermediate pressure cylinder of steam turbine of nuclear power unit |
| CN113389606B (en) * | 2021-06-30 | 2024-02-09 | 国核电力规划设计研究院有限公司 | Direct heat supply system and method for exhaust steam and extraction steam of medium-pressure cylinder of steam turbine of nuclear power unit |
| CN114198794A (en) * | 2021-12-17 | 2022-03-18 | 中国核电工程有限公司 | Heat supply system and heat supply method |
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