CN108800101B - A kind of high efficiency ultracritical nuclear power system and working method - Google Patents
A kind of high efficiency ultracritical nuclear power system and working method Download PDFInfo
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- CN108800101B CN108800101B CN201810651184.6A CN201810651184A CN108800101B CN 108800101 B CN108800101 B CN 108800101B CN 201810651184 A CN201810651184 A CN 201810651184A CN 108800101 B CN108800101 B CN 108800101B
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22D—PREHEATING, OR ACCUMULATING PREHEATED, FEED-WATER FOR STEAM GENERATION; FEED-WATER SUPPLY FOR STEAM GENERATION; CONTROLLING WATER LEVEL FOR STEAM GENERATION; AUXILIARY DEVICES FOR PROMOTING WATER CIRCULATION WITHIN STEAM BOILERS
- F22D1/00—Feed-water heaters, i.e. economisers or like preheaters
- F22D1/50—Feed-water heaters, i.e. economisers or like preheaters incorporating thermal de-aeration of feed-water
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Abstract
The invention discloses a kind of high efficiency ultracritical nuclear power system and working methods, comprising: the condensate system with low-temperature flue gas waste heat utilization apparatus, the water supply system with medium temperature flue gas waste heat utilization device, coupling steam turbine high-pressure cylinder, coupling turbine low pressure cylinder, non-nuclear fuel can discharge and reforming unit and nuclear island；The output of condensate system with low-temperature flue gas waste heat utilization apparatus is sequentially connected high pressure water pump, the first high-pressure heater and medium temperature flue gas waste heat utilization device；The output of medium temperature flue gas waste heat utilization device is divided into two-way, wherein can discharge with non-nuclear fuel all the way and reforming unit is connect, the feed-water intake pipeline connection of another way and nuclear island；The outlet vapor pipeline of nuclear island is divided into two-way, wherein can discharge with non-nuclear fuel all the way and reforming unit is connect, another way is connected with turbine low pressure cylinder with coupling.The present invention takes full advantage of the nuclear island of existing maturation and the technological parameter feature of non-core fuel boiler, solves the problems, such as that the device fabrication in previous scheme is difficult.
Description
Technical field
The present invention relates to energy technology fields, more particularly to a kind of high efficiency ultracritical nuclear power system and working method.
Background technique
The nuclear power plant of modern Commercial is mainly Subcritical Units, and the reactor-loop coolant of boiling-water reactor nuclear power plant is drawn
Enter steam turbine, radiation protection and waste processing are more complicated, therefore presurized water reactor is the mainstream of modern Commercial nuclear power technology.Conventional pressure
Water-water reactor is generally two circuit systems, and wherein the steam of secondary coolant circuit system drives steam turbine power generation.Due to reactor catalyst carrier temperature
Limitation (presurized water reactor mean outlet temperature is generally below 330 degrees Celsius), it is full that pressure lower (5.0~8.0MPa) can only be produced
Want that steam moisture is again high than enthalpy drop very little with steam or micro- overheat (degree of superheat is 20~30 degrees Celsius) steam, full mechanism, in order to
Increase single-machine capacity, steam flow is inevitable very big.At present the parameter of commercialization nuclear power plant secondary coolant circuit system be generally pressure about 6~
8MPa, about 230 DEG C~290 DEG C or so of temperature, generating efficiency about 34%.Supercritical-Pressure Light Water Cooled Reactor (SCWR) reactor core outlet ginseng
Number pressure about 25MPa, about 500 DEG C of temperature, compared with conventional presurized water reactor, a few circuit, the hot fluid of core exit directly into
Enter steam turbine, system thermal efficiency is close to 45%, much higher than the thermal efficiency of conventional water cooled reator 34%.But Supercritical-Pressure Light Water Cooled Reactor is located always
In research state, but since parameter greatly improves, lack heat transfer flow experiment and numeric data, and lack critical material in heap
The reasons such as chemical property and mechanical property under the conditions of Supercritical-Pressure Light Water Cooled Reactor, technically there is also bigger difficulty, there is optimism
Document is thought to need by 2028 to have commercial heap constructive ability.
Most of nuclear power plant all uses saturated vapor, and the work done of nuclear steam turbine 2/3 is completed in low pressure (LP) cylinder, but nuclear power
The exhaust steam moisture of turbine low pressure cylinder is larger, and generally up to 12%~14%, it is be easy to cause blade erosion, corrosion, therefore general
Using half speed turbine, and need after high pressure cylinder plus special separator dehumidified, reheating.And thermal power plant
Superheated steam is generallyd use, the degree of superheat is high, generallys use full speed steam turbine.Half speed turbine root diameter is big, weight weight, generally
For, the consumption of materials of half speed turbine than full speed steam turbine more than 2 times, for whole unit, half speed turbine
Weight be about 1.2~2.4 times of full speed unit.The support loading of corresponding Turbine Engine Foundation also increases, and construction investment increases；
Half speed turbine transport, lifting, in terms of investment it is also higher than full speed steam turbine.Equipment manufacturing cost and installation structural construction cost,
Half Speed machine is higher than full speed machine by 20%~30% (to be equivalent to high 7% or so) to entire conventional island.
It is well known that the investment of nuclear power plant is much larger than thermal power plant, and the thermal efficiency of thermal power plant generally higher than nuclear power plant.Such as
Fruit uses suitable method, builds suitable system, the therrmodynamic system of thermal power plant can be coupled into nuclear power plant, then can be big
Width reduces initial cost, and can greatly improve operating thermal efficiency, and economy will be substantially improved.
Due to the inherent safety of high temperature gas cooled reactor, the design allowable temperature of fuel element is up to 1600 DEG C, therefore 10MW
High-temperature gas-solid two-phase flow is completed.The prior art proposes a kind of by Modular high-temperature air cooled reactor technology and current maturation
The scheme of supercritical steam power cycle technology coupling matches the scheme of a machine using more heaps, and primary Ioops use helium closed circulation,
Helium flows through pebble bed core from top to bottom and is heated to 750 DEG C or so, and secondary circuit uses water and water steam, and vapor is by helium
Gas is heated to temperature required for supercritical steam power cycle, such as 565 DEG C, and generating efficiency is up to 45% or more, so
And be also due to the nuclear island part commercialized Some Key Technologies of enlargement and do not make a breakthrough yet, therefore high temperature gas cooled reactor is still in generally
Read the design phase.
The technological difficulties for needing to solve are broken through due to nuclear island and are much higher than conventional thermal power generating equipment, therefore nuclear power and supercritical steam are dynamic
The key point of power circulation coupling, which is cannot to place hope on, breaks through Nuclear island equipment to adapt to thermoelectricity parameter, however this thinking but one
It is straight to pay attention to without studied personnel.
The series-parallel coupled electricity-generation system and nuclear energy and conventional energy resource for disclosing nuclear energy and conventional energy resource in the prior art are straight
Take over thermal coupling electricity generation system, but the specific embodiment all without proposing conventional energy resource boiler.In particular, the prior art discloses
Nuclear energy and conventional energy resource coupled system, be all based on from nuclear reactor export steam be directly entered it is so-called " heating dress
Set " such as coal-burning boiler.But when specific to boiler design, this system, which is designed, brings huge challenge to the design of boiler, because
Liquid water is not heated to for this special boiler the process of saturated vapor, that is to say, that the process not vaporized, with biography
System boiler is compared, and the Steam Temperature Characteristics of this boiler will appear subversive variation, and caused by the variation of this Steam Temperature Characteristics
The innovative design of heating surface arrangement be it is huge, be difficult to obtain experimental verification at present, or perhaps it is very jejune.
In conclusion the key point that nuclear power is coupled with supercritical steam power cycle is that breakthrough core can neither be placed hope on
Island equipment adapts to thermoelectricity parameter, and equipment manufactures and designs in immature reliable situation in a short time, and cannot place hope on
Break through apparatus of thermo-electric power boiler significantly to adapt to the requirement not vaporized in the boiler.It is most worth to post for industrial application of being more convenient for
Give desired thinking be using existing maturation nuclear island design and manufacturing technology and existing maturation by liquid water to superheated steam
Apparatus of thermo-electric power boiler design and manufacturing technology gives full play to nuclear fuel and mature experience that non-core fuel heat utilizes, ingehious design nuclear island and
Non-core fuel bound electrification technique system realizes high efficiency ultracritical nuclear energy power generation.However, this thinking does not obtain but sufficiently
It was found that.
In conclusion in the prior art for high efficiency ultracritical nuclear power generating system, still lack effective, innovation and mature
Solution.
The heat exchanger tube of steam-line blowing, especially boiler internal is usually carried out before conventional thermal power plant starting to pipeline as overheated
Device, economizer etc..It needs to put into a large amount of fuel when conventional thermal power plant blowpipe, boiler load is lower when due to blowpipe, usually needs
Surely to fire, therefore for coal-burning boiler, when blowpipe a large amount of fuel oil that needs to burn surely fire.For nuclear power and conventional energy resource coupling
Collaboration is united, and the fossil fuel expense during these blowpipes is provided with the possibility of saving, but its technical solution is not reported.
Summary of the invention
In order to solve the deficiencies in the prior art, there is provided a kind of high efficiency ultracritical nuclear power systems for an object of the present invention
System, solves the problems, such as the immature of the prior art, enhances the key equipment in the system design that nuclear energy is coupled with conventional energy resource
Availability.
To achieve the goals above, the present invention adopts the following technical scheme:
A kind of high efficiency ultracritical nuclear power system, comprising:
Condensate system with low-temperature flue gas waste heat utilization apparatus, the water supply system with medium temperature flue gas waste heat utilization device,
Coupling steam turbine high-pressure cylinder, coupling turbine low pressure cylinder, non-nuclear fuel can discharge and reforming unit and nuclear island；In the band
The water supply system of warm flue gas waste heat utilization device includes: that oxygen-eliminating device, feed pump, high-pressure heater and medium temperature fume afterheat utilize dress
It sets；Oxygen-eliminating device, feed pump and high-pressure heater are sequentially connected in series, the high-pressure heater and medium temperature flue gas waste heat utilization device
It is connected in parallel；
The output end of the condensate system with low-temperature flue gas waste heat utilization apparatus is connect with oxygen-eliminating device, normal coupling fortune
When row, the water supply of oxygen-eliminating device output, which enters in medium temperature flue gas waste heat utilization device, to be heated；When medium temperature flue gas waste heat utilization device
When deactivating, the water supply of oxygen-eliminating device output is heated in high-pressure heater；
When normal coupling operation, the water supply after heating is divided into two-way, and first via water supply is connected to the feed-water intake of nuclear island, and second
Road water supply, which is connected to non-nuclear fuel, can discharge and reforming unit；When starting or decoupling operation, the water supply after heating is only connected to nuclear island
Feed-water intake；
The first via water supply enters nuclear island by the feed-water intake pipeline of nuclear island, and heated, vaporization becomes micro- overheat and steams
Vapour, micro- superheated steam are exported by nuclear island outlet vapor pipeline；
The outlet vapor pipeline of nuclear island is divided into two-way, wherein can discharge with non-nuclear fuel all the way and reforming unit is connect, separately
It is connect all the way with coupling with turbine low pressure cylinder.
Further, the non-nuclear fuel can discharge and reforming unit includes sequentially connected economizer, water-cooling wall entrance
Header, water-cooling wall and the first superheater；Second superheater is connect with super-heater exit case respectively with the first superheater；
Second tunnel water supply can be discharged by non-nuclear fuel and the economizer entrance of reforming unit, heated into economizer
And enter water-cooling wall entrance header；Become again through the first superheater is heated after the water cooled wall vaporization of the water supply of water-cooling wall entrance header
The superheated steam of height overheat, referred to as the first superheated steam；
Nuclear island outlet vapor enter non-nuclear fuel can discharge and the second superheater of reforming unit it is heated after spent as height
The superheated steam of heat, referred to as the second superheated steam；
When normal coupling operation, first superheated steam and the second superheated steam claim after super-heater exit case converges
For main superheated steam, main superheat steam pipeline is connected with steam turbine high-pressure cylinder with coupling, and main superheated steam pushes high pressure cylinder acting
And drive the first electrical power generators；When starting or decoupling operation, non-nuclear fuel can discharge and reforming unit is not run, and coupling is used
Steam turbine high-pressure cylinder is not also run, and the steam that nuclear island generates only enters the acting power generation of coupling turbine low pressure cylinder；
Further, it can be discharged and the steam flow of reforming unit, be realized to the second mistake by adjusting into non-nuclear fuel
The adjusting of hot steam temperature, and then realize the adjusting to main superheat steam temperature.
Further, on startup, first start nuclear island and low pressure (LP) cylinder, therefore nuclear island can be passed through using the steam that nuclear island generates
Outlet vapor coupling pipeline is gone to fossil-fuel boiler blowpipe, and nuclear fuel cost is far below fossil fuel, to save fossil
The expense of fuel.When blowpipe, valve 1-1 is opened, and 1-20 is closed, and 1-22 is closed, and 1-21 is opened, and steam flow: nuclear island outlet vapor passes through core
Island outlet vapor couples pipeline and enters the second superheater, enters back into super-heater exit case, enters back into the first superheater, enter back into
Water-cooling wall enters back into water-cooling wall entrance header, enters back into economizer, arranges finally by the blowpipe diffuse channel where valve 1-21
To atmosphere.
Further, the condensate system with low-temperature flue gas waste heat utilization apparatus includes: condenser, axle envelope heating
Device, low-pressure heater and low-temperature flue gas waste heat utilization apparatus；The condenser is connect with gland heater, gland heater with it is low
Pressure heater and low-temperature flue gas waste heat utilization apparatus are separately connected；When normal coupling operation, condensed water is in low-temperature flue gas waste heat benefit
It is heated in device；When low-temperature flue gas waste heat utilization apparatus deactivates, condensed water is heated in low-pressure heater.
Further, non-nuclear fuel can discharge and the flue gas of reforming unit discharge adds in medium temperature flue gas waste heat utilization device
Hot water supply, the flue gas come out from medium temperature flue gas waste heat utilization device successively pass through denitrification apparatus, air preheater, deduster and draw
Entering low-temperature flue gas waste heat utilization apparatus after blower, the flue gas come out from low-temperature flue gas waste heat utilization apparatus passes through desulfurizer,
Finally it is discharged from chimney.
Further, the nuclear island outlet vapor pipeline is divided into two-way pipeline, couples pipeline all the way for nuclear island outlet vapor,
Being connected to non-nuclear fuel by the first valve can discharge and reforming unit, and another way is nuclear island outlet vapor direct-furnish pipeline, by the
Two valves are connected to coupling turbine low pressure cylinder.
Further, the non-nuclear fuel can discharge and reforming unit selects fossil fuel dum boiler or fossil fuel
Direct current cooker or other can convert thermal energy for the chemical energy of non-nuclear fuel, and transfer thermal energy to thermal cycle working medium
Device.
Preferably, coupling steam turbine high-pressure cylinder is since steam is mainly in the acting of overheat section, therefore couples high with steam turbine
Cylinder pressure uses full speed steam turbine, compared with conventional nuclear power is using half speed turbine, reduces equipment and Civil Cost, and high-order arrangement
In boiler export, shorten main superheat steam pipeline length, further decreases the cost of the expensive main superheat steam pipeline of high temperature resistant；
Coupling uses half speed turbine with turbine low pressure cylinder, is adapted to the micro- superheated steam come from nuclear island outlet vapor direct-furnish pipeline
Parameter.When specific design, the parameter of the coupling parameter of steam turbine high-pressure cylinder steam discharge and nuclear island outlet vapor is similar, coupling
The inlet steam parameter for sharing turbine low pressure cylinder can use the parameter of coupling steam turbine high-pressure cylinder steam discharge, can also use core
The parameter of island outlet vapor substantially increases the flexibility of operation.Further, further includes: nuclear island accident spray system, it is described
Nuclear island accident spray system includes the cooling height of emergency drawn condenser recirculated cooling water bypassed into above nuclear reactor all the way
Position water tank, cooling high water tank of meeting an urgent need are located at nuclear reactor safety shell top, and accident conditions Shi Youying chilling occurs for nuclear reactor
But high water tank provides shower water to containment, and described shower water a part is heated to evaporate into atmosphere, and another part is extra
Shower water falls into spray recycling pond, and the water in spray recycling pond enters cooling after entering cooling tower cooler by suction pump
Pond, water circulating pump entrance are connected to cooling pond, and water circulating pump outlet is divided into two-way, connect condenser, another way connection all the way
The cooling high water tank of emergency.
The second object of the present invention is to disclose a kind of working method of high efficiency ultracritical nuclear power system, comprising:
The coupling of water side: coupling is condensed in condenser with turbine low pressure cylinder steam discharge becomes condensed water, normal coupling operation
When, condensed water is heated in low-temperature flue gas waste heat utilization apparatus；When low-temperature flue gas waste heat utilization apparatus deactivates, condensed water exists
It is heated in low-pressure heater；Condensed water after heating enters oxygen-eliminating device；
When normal coupling operation, the condensed water of oxygen-eliminating device output, which is directly entered in medium temperature flue gas waste heat utilization device, to be added
Heat；When medium temperature flue gas waste heat utilization device deactivates, the condensed water of oxygen-eliminating device output is heated in high-pressure heater；
When normal coupling operation, the water supply after heating is divided into two-way, and the feed-water intake pipeline of nuclear island is passed through in first via water supply
Into nuclear island, heated, vaporization becomes micro- superheated steam, and the second tunnel water supply is connected to that non-nuclear fuel can discharge and reforming unit is heated
The first superheated steam as height overheat；When starting or decoupling operation, water side coupling decoupling, the water supply after heating is only connected to
The feed-water intake of nuclear island；
The coupling of vapour side: micro- superheated steam is exported by nuclear island outlet vapor pipeline, is divided into two-way: wherein entering non-core all the way
Fuel can discharge and heated the second superheated steam for becoming height overheat of reforming unit；When normal coupling operation, the second overheat is steamed
After vapour and the first superheated steam converge, is done work and generated electricity with steam turbine high-pressure cylinder into coupling；Another way with couple it is high with steam turbine
After the steam discharge of cylinder pressure converges, is done work and generated electricity with turbine low pressure cylinder into coupling；
When starting or decoupling operation, the coupling decoupling of vapour side, non-nuclear fuel can discharge and reforming unit is not run, and coupling is used
Steam turbine high-pressure cylinder is not also run, and the steam that nuclear island generates only enters the acting power generation of coupling turbine low pressure cylinder；
Further,
It can be discharged and the flow of micro- superheated steam of reforming unit, be realized to entering non-core by adjusting into non-nuclear fuel
Fuel can discharge and the adjusting of the second superheat steam temperature of reforming unit, and then realizes to entrance coupling steam turbine high-pressure cylinder
The adjusting of the main steam temperature of acting.The invention has the benefit that
1, a kind of high efficiency ultracritical nuclear power system of special designing of the present invention takes full advantage of the nuclear island of existing maturation and non-
The technological parameter feature of nuclear fuel boiler solves the problems, such as that the device fabrication in previous scheme is difficult, enhances nuclear energy and routine
The availability of key equipment in the system design of energy coupling.
2, for nuclear island, feed temperature of the suction parameter using common 220 degrees centigrade of conventional nuclear power, outlet
Parameter uses the vapor (steam) temperature of common 280 degrees centigrade of conventional nuclear power；Non- nuclear fuel can be discharged and reforming unit comes
It says, entrance uses the common liquid water supply of conventional fossil fuel boiler, and outlet is commonly overheated using conventional fossil fuel boiler
Steam (parameter can be 700 degrees Celsius and less), therefore main equipment manufactures and designs the variation that matter is not present, thus significantly
Improve the availability of system.700 DEG C of boiler export temperature and hereinafter, compared with traditional nuclear power, greatly improves steam turbine effect
Rate, and the reliability of used heating surface heat-resisting material is verified in the thermal power plant gone into operation in the recent period, therefore
This system is safe and efficient, energy conservation and environmental protection.
3, the smoke evacuation after making full use of air-introduced machine carrys out heat-setting water, and normal coupling does not have to the low-pressure heating that puts into operation when running
The low plus steam extraction of device, saving can be with multiple electricity.
4, flue gas before making full use of denitrification apparatus heats water supply, and when normal coupling operation does not have to the hyperbaric heating that puts into operation
Device, the height of saving add steam extraction to can be used for generating electricity, and thus the application takes full advantage of high-quality energy.
5, the thermal efficiency of coupled heat system of the present invention is improved on the basis of conventional nuclear power 34% to 45% or so, simultaneously
Used nuclear island technology is mature, avoids the various technical problems occurred in Supercritical-Pressure Light Water Cooled Reactor research application process
(for example thermal-hydraulic calculates problem, critical material performance puzzle, radiation protection problem etc.)；It is and same with the raising of efficiency
The nuclear power unit of generated energy is compared, and is coupled quantity of steam required for unit generation and is declined to a great extent, and about 15%, with identical carbonated drink damage
It loses to consider, the operating cost of moisturizing processing will also be greatly reduced.
6, there is special overheating steam temperature regulation measure, it can be normal to avoid traditional apparatus of thermo-electric power boiler such as overheating steam temperature overtemperature tube burst
The operation problem seen.
7, since steam superheat is higher, after steam turbine does work, exhaust steam moisture is far below the nuclear power vapour of modern Commercial
Turbine, therefore have the condition using lighter more compact full speed steam turbine, greatly reduce cost of investment.
8, using conventional two circuit technology of nuclear island, radiation protection and waste processing comparative maturity are simple.
9, when fossil-fuel boiler blowpipe, the conventional method for generating steam using fossil fuel is lighted, and this system, due to
First start nuclear island and low pressure (LP) cylinder, therefore can be gone using the steam that nuclear island generates to fossil-fuel boiler blowpipe, nuclear fuel cost is remote
Lower than fossil fuel, to save the expense of fossil fuel.
10. the advantages of steam turbine split axle is arranged further include: coupling uses full speed steam turbine with steam turbine high-pressure cylinder, with routine
Nuclear power is compared using half speed turbine, reduces equipment and Civil Cost, and a high position is arranged in boiler export, is exported with Boiler Steam
Arrangement nearby, shortens main superheat steam pipeline length, further decreases the cost of the expensive main superheat steam pipeline of high temperature resistant；Coupling
Turbine low pressure cylinder is shared using half speed turbine, is adapted to the micro- superheated steam come from nuclear island outlet vapor direct-furnish pipeline
Parameter.When specific design, the parameter of the coupling parameter of steam turbine high-pressure cylinder steam discharge and nuclear island outlet vapor is similar, coupling
The parameter that coupling steam turbine high-pressure cylinder steam discharge can be used with the inlet steam parameter of turbine low pressure cylinder, can also use nuclear island
The parameter of outlet vapor substantially increases the flexibility of operation.
Detailed description of the invention
Fig. 1 is high efficiency ultracritical nuclear power system structural schematic diagram of the present invention；
Fig. 2 can discharge for the non-nuclear fuel of the present invention and reforming unit schematic diagram；
Wherein, 1. non-nuclear fuels can discharge and reforming unit, 2. medium temperature flue gas waste heat utilization devices, 3. denitrification apparatus, and 4.
Steam turbine is used in air preheater, 5. dedusters, 6. air-introduced machines, 7. nuclear islands, 8. first generators, 9. second generators, 10. couplings
High pressure cylinder, 11. coupling turbine low pressure cylinders, 12. oxygen-eliminating devices, 13. feed pumps, 14. high-pressure heaters, more than 15. low-temperature flue gas
Heat utilization device, 16. low-pressure heaters, 17. desulfurizers, 18. chimneys, 19. gland heaters, 20. condensers, 21. sprays
Recycle pond, the cooling high water tank of 22. emergency, 23. suction pumps, 24. water circulating pumps, 25. cooling towers, 26. cooling ponds.
Specific embodiment:
The invention will be further described with embodiment with reference to the accompanying drawing.
It is noted that following detailed description is all illustrative, it is intended to provide further instruction to the application.Unless another
It indicates, all technical and scientific terms used herein has usual with the application person of an ordinary skill in the technical field
The identical meanings of understanding.
It should be noted that term used herein above is merely to describe specific embodiment, and be not intended to restricted root
According to the illustrative embodiments of the application.As used herein, unless the context clearly indicates otherwise, otherwise singular
Also it is intended to include plural form, additionally, it should be understood that, when in the present specification using term "comprising" and/or " packet
Include " when, indicate existing characteristics, step, operation, device, component and/or their combination.
In order to solve the problems, such as to point out in background technique, the invention discloses a kind of high efficiency ultracritical nuclear power system, such as Fig. 1
It is shown, comprising: the condensate system with low-temperature flue gas waste heat utilization apparatus gives water system with medium temperature flue gas waste heat utilization device
System, coupling steam turbine high-pressure cylinder, coupling turbine low pressure cylinder, non-nuclear fuel can discharge and reforming unit, nuclear island, nuclear island thing
Therefore spray system and circulation.
Condensate system with low-temperature flue gas waste heat utilization apparatus includes: condenser 20, gland heater 19, low-pressure heating
Device 16, low-temperature flue gas waste heat utilization apparatus 15, valve 1-3, valve 1-4, valve 1-5, valve 1-6 and valve 1-17；For solidifying
For bearing water system, low-pressure heater 16 and low-temperature flue gas waste heat utilization apparatus 15 are connected in parallel；When normal coupling operation, valve
1-4 and valve 1-6 is closed, and valve 1-3 and valve 1-5 are opened, and condensed water is heated in low-temperature flue gas waste heat utilization apparatus 15；
When low-temperature flue gas waste heat utilization apparatus 15 deactivates, valve 1-3 and valve 1-5 are closed, and valve 1-4 and valve 1-6 are opened, condensation
Water is heated in low-pressure heater 16.
It should be noted that valve 1-17 is also switched off when valve 1-4 and valve 1-6 is closed；When valve 1-4 and valve
When 1-6 is opened, valve 1-17 is also opened.
Water supply system with medium temperature flue gas waste heat utilization device include: oxygen-eliminating device 12, feed pump 13, high-pressure heater 14,
Medium temperature flue gas waste heat utilization device 2, valve 1-7, valve 1-8, valve 1-9, valve 1-10, valve 1-11, valve 1-12, valve
1-16, valve 1-18 and valve 1-19.
For water supply system, high-pressure heater 14 and medium temperature flue gas waste heat utilization device 2 are connected in parallel；Normal coupling
When operation, valve 1-8, valve 1-9 and valve 1-12 are closed, and valve 1-7, valve 1-10 and valve 1-11 are opened, and water supply is in
It is heated in warm flue gas waste heat utilization device 2；When medium temperature flue gas waste heat utilization device 2 deactivates, valve 1-7, valve 1-10 and
Valve 1-11 is closed, and valve 1-8, valve 1-9 and valve 1-12 are opened, and condensed water is heated in high-pressure heater 14.
When normal coupling operation, valve 1-18 and valve 1-19 are opened, and the condensed water output after heating is divided into two-way, the
Water supply is connected to the feed-water intake of nuclear island 7 by the feedwater piping to nuclear island where valve 1-19 all the way, and the second tunnel water supply passes through
Can be discharged to non-nuclear fuel where the valve 1-18 and feedwater piping of reforming unit 1 is connected to non-nuclear fuel can discharge and convert dress
The economizer entrance set.
When starting or decoupling operation, valve 1-18 is closed, and water supply only passes through the water supply to nuclear island 7 where valve 1-19
Pipeline is connected to the feed-water intake of nuclear island 7.
It should be noted that valve 1-16 is also switched off when valve 1-8 and valve 1-9 is closed；When valve 1-8 and valve
When 1-9 is opened, valve 1-16 is also opened.
Above-mentioned low-temperature flue gas waste heat utilization apparatus 15 deactivates or medium temperature flue gas waste heat utilization device 2 deactivates operating condition and refers to
Non- nuclear fuel can discharge when starting or decoupling operation and reforming unit 1 deactivates caused low-temperature flue gas waste heat utilization apparatus 15 and deactivates
Or medium temperature flue gas waste heat utilization device 2 deactivates；Alternatively, when normal coupling operation due to low-temperature flue gas waste heat utilization apparatus 15 or
It is deactivated caused by 2 failure of person's medium temperature flue gas waste heat utilization device itself.
Oxygen-eliminating device 12 is using the steam extraction of turbine low pressure cylinder or steam discharge as the heat source of water supply, and high-pressure heater 14 is with vapour
Heat source of the steam extraction or steam discharge of turbine high pressure cylinder as water supply, low-pressure heater 16 is with the steam extraction of turbine low pressure cylinder or row
Heat source of the vapour as condensed water, low-temperature flue gas waste heat utilization apparatus 15 is using low-temperature flue gas as heat source heat-setting water, medium temperature
Flue gas waste heat utilization device 2 heats water supply by heat source of medium temperature flue gas.
The first via water supply exported after medium temperature flue gas waste heat utilization device 2 or high-pressure heater 14 heat is by core
The feed-water intake pipeline on island enters nuclear island 7, and heated, vaporization becomes micro- superheated steam, and micro- superheated steam is exported by nuclear island to be steamed
The output of steam pipe road.Nuclear island outlet vapor pipeline is divided into two-way pipeline, couples pipeline all the way for nuclear island outlet vapor, passes through valve 1-
1, which is connected to non-nuclear fuel, can discharge and reforming unit 1, and another way is nuclear island outlet vapor direct-furnish pipeline, be connected to coupling by valve 1-2
Share turbine low pressure cylinder 11.
Coupling with steam turbine high-pressure cylinder 10 due to steam mainly overheat section do work, therefore couple use steam turbine high-pressure cylinder 10
Using full speed steam turbine, compared with conventional nuclear power is using half speed turbine, equipment and Civil Cost are reduced, and a high position is arranged in pot
Outlet of still shortens main superheat steam pipeline length, further decreases the cost of the expensive main superheat steam pipeline of high temperature resistant；Coupling
Half speed turbine is used with turbine low pressure cylinder 11, is adapted to the micro- superheated steam come from nuclear island outlet vapor direct-furnish pipeline
Parameter.When specific design, the parameter of the coupling parameter of steam turbine high-pressure cylinder steam discharge and nuclear island outlet vapor is similar, coupling
The parameter that coupling steam turbine high-pressure cylinder steam discharge can be used with the inlet steam parameter of turbine low pressure cylinder 11, can also use core
The parameter of island outlet vapor substantially increases the flexibility of operation.
Non- nuclear fuel can discharge and reforming unit 1 include sequentially connected economizer, water-cooling wall entrance header, water-cooling wall and
First superheater；Second superheater is connect with super-heater exit case respectively with the first superheater, as shown in Figure 2.
The the second tunnel water supply exported after medium temperature flue gas waste heat utilization device 2 or high-pressure heater 14 heat is by non-
Nuclear fuel can discharge and the economizer entrance of reforming unit 1, is heated into economizer and enters water-cooling wall entrance header；Water-cooling wall
Being heated again through the first superheater after the water cooled wall vaporization of the water supply of entrance header becomes the superheated steam of height overheat, and referred to as first
Superheated steam；
Non- nuclear fuel can discharge and reforming unit 1 further includes a steam inlet, and pipeline company is coupled with nuclear island outlet vapor
It connects；Steam in nuclear island outlet vapor coupling pipeline can be discharged into non-nuclear fuel and the second superheater of reforming unit 1 is heated
Become the superheated steam of height overheat, referred to as the second superheated steam afterwards；First superheated steam and the second superheated steam are in superheater
Outlet header is known as main superheated steam after converging, main superheat steam pipeline is connect with coupling with steam turbine high-pressure cylinder 10, main overheat
Steam Actuation high pressure cylinder does work and the first generator 8 is driven to generate electricity.
Preferably embodiment can adjust to go out by nuclear island by the aperture of control valve 1-1 and valve 1-2
Mouth steam coupling pipeline can be discharged into non-nuclear fuel and the flow of the steam of reforming unit 1, and the adjusting of steam flow being capable of shadow
The temperature of steam is rung, to realize the adjusting to the main superheat steam temperature for entering coupling steam turbine high-pressure cylinder 10.
On startup, first start nuclear island and low pressure (LP) cylinder, therefore the steam that can be generated using nuclear island passes through nuclear island outlet vapor
Coupling pipeline is gone to fossil-fuel boiler blowpipe, and nuclear fuel cost is far below fossil fuel, to save the expense of fossil fuel
With.When blowpipe, valve 1-1 is opened, and 1-20 is closed, and 1-22 is closed, and 1-21 is opened, steam flow: nuclear island outlet vapor is exported by nuclear island to be steamed
Vapour couples pipeline and enters the second superheater, enters back into super-heater exit case, enters back into the first superheater, enter back into water-cooling wall,
Water-cooling wall entrance header is entered back into, economizer is entered back into, arranges Xiang great Qi finally by the blowpipe diffuse channel where valve 1-21.
Nuclear island accident spray system includes meet an urgent need cooling high water tank 22, spray recycling pond 21, suction pump 23.To prevent
The heat dissipation of nuclear reactor heat is insufficient under any operating condition, exports in water circulating pump 24 20 recirculated cooling water of condenser drawing one
Road bypasses into the cooling high water tank 22 of the emergency above nuclear reactor, and cooling high water tank 22 of meeting an urgent need is located at nuclear reactor safety
Shell top provides shower water, discharge safety to containment from meeting an urgent need cooling high water tank 22 when accident conditions occur for nuclear reactor
Heat in shell reduces in containment pressure and temperature to reach the receptible level of integrality institute for maintaining containment, shower water
A part is heated to evaporate into atmosphere, and a part of extra shower water falls into spray recycling pond 21, spray recycling pond 21
Water enters cooling pond 26 after entering the cooling of cooling tower 25 by suction pump 23.
Circulation includes water circulating pump 24, cooling pond 26, cooling tower 25.24 entrance of water circulating pump is connected to cooling water
Pond 26.The outlet of water circulating pump 24 is divided into two-way, removes the cooling low pressure (LP) cylinder steam discharge of condenser 20 all the way, removes cooling high-order water of meeting an urgent need all the way
Case 26.The heated heating of recirculated water after cooling low pressure (LP) cylinder steam discharge, enters cooling pond 26 after the cooling of cooling tower 25.Cooling tower 25
Cool principle is identical as conventional thermoelectricity, the cooling tower principle of nuclear power, cooling for example, by using cooling tower filler mode.
It should be noted that non-nuclear fuel can discharge and reforming unit 1 selects fossil fuel dum boiler or fossil combustion
Material direct current cooker or other can convert thermal energy for the chemical energy of non-nuclear fuel, and transfer thermal energy to thermal cycle working medium
Device, such as coal-burning boiler, oil burning boiler, gas fired-boiler, biomass boiler, waste incinerator etc..
When using conventional fossil fuel dum boiler, water supply sequentially enters the heated production such as water-cooling wall, drum, superheater
Raw superheated steam is entered the acting power generation of coupling steam turbine high-pressure cylinder 10 and is given when using conventional fossil fuel direct current cooker
Water sequentially enters the heated generation superheated steam such as water-cooling wall, superheater and enters the acting power generation of coupling steam turbine high-pressure cylinder 10.
The explanation carried out by taking direct current cooker as an example in Fig. 1, but dum boiler also should be within the scope of the present invention.
As an implementation, the smoke inlet of medium temperature flue gas waste heat utilization device 2 and non-nuclear fuel can discharge and turn
1 exhanst gas outlet connection is set in makeup, and non-nuclear fuel can discharge and the flue gas of reforming unit 1 successively utilizes dress through medium temperature fume afterheat
Set 2, denitrification apparatus 3, air preheater 4, deduster 5, air-introduced machine 6, low-temperature flue gas waste heat utilization apparatus 15,17 row of desulfurizer
To chimney 18.
On the other hand, the invention discloses a kind of working method of high efficiency ultracritical nuclear power system, two parts are specifically included
Coupling:
One, water side couples:
Coupling is condensed in condenser 20 with turbine low pressure cylinder steam discharge becomes condensed water, when normal coupling is run, condensation
Water is heated in low-temperature flue gas waste heat utilization apparatus 15；When low-temperature flue gas waste heat utilization apparatus 15 deactivates, condensed water is low
It is heated in pressure heater 16；Condensed water after heating enters oxygen-eliminating device 12；
When normal coupling operation, the condensed water that oxygen-eliminating device 12 exports is directly entered quilt in medium temperature flue gas waste heat utilization device 2
Heating；When medium temperature flue gas waste heat utilization device 2 deactivates, the condensed water that oxygen-eliminating device 12 exports is added in high-pressure heater 14
Heat；
When normal coupling operation, condensed water is by flue gas in low-temperature flue gas waste heat utilization apparatus, and water supply is in medium temperature cigarette
By flue gas in gas residual heat using device, and the water supply after heating is divided into two-way, and first via water supply enters by the water supply of nuclear island
Mouth pipeline enters nuclear island 7, and heated, vaporization becomes micro- superheated steam, and the second tunnel water supply, which is connected to non-nuclear fuel, can discharge and convert
The heated superheated steam for becoming height overheat of device 1；When starting or decoupling operation, the decoupling of water side, condensed water is in low-pressure heating
Device is by low plus steam extraction heating, and water supply is heated in high-pressure heater by height plus steam extraction, and water supply only passes through the feedwater piping to nuclear island
It is connected to the feed-water intake of nuclear island 7.
It should be noted that micro- superheated steam involved in the present invention refers to steam of the degree of superheat less than 50 DEG C；
The superheated steam of height overheat refers to that the degree of superheat is greater than 50 DEG C of steam.
Two, vapour side couples:
Micro- superheated steam is exported by nuclear island outlet vapor pipeline, is divided into two-way: can wherein be released into non-nuclear fuel all the way
It puts and the economizer entrance of reforming unit 1, is heated into economizer and enters water-cooling wall entrance header；Water-cooling wall entrance header
Again through the heated superheated steam for becoming height overheat of the first superheater, referred to as the first superheated steam after the water cooled wall vaporization of water supply；
Steam in nuclear island outlet vapor coupling pipeline can be discharged into non-nuclear fuel and the second superheater of reforming unit 1
Become the superheated steam of height overheat, referred to as the second superheated steam after heated；First superheated steam and the second superheated steam are in mistake
Hot device outlet header is known as main superheated steam after converging, main superheat steam pipeline is connect with coupling with steam turbine high-pressure cylinder 10, main
Superheated steam pushes high pressure cylinder to do work and the first generator 8 is driven to generate electricity.
Another way with couple and converged with the steam discharge of steam turbine high-pressure cylinder 10 after, do work into coupling turbine low pressure cylinder 11
Power generation.
Preferably, couple that pipeline, to be equipped with aperture on nuclear island outlet vapor direct-furnish pipeline adjustable in nuclear island outlet vapor
Valve, being realized by the adjusting of valve opening can discharge and convert into non-nuclear fuel to by nuclear island outlet vapor coupling pipeline
The control of the steam flow of device 1, so adjust converge with the first superheated steam after into coupling with steam turbine high-pressure cylinder 10
Vapor (steam) temperature.
When starting or decoupling operation, nuclear island outlet vapor is delivered directly to coupling by nuclear island outlet vapor direct-furnish pipeline
With turbine low pressure cylinder 11, low pressure (LP) cylinder acting drives the power generation of the second generator 9.
When operating normally, water side and vapour side are in couple state, in entire thermodynamic cycle, are respectively in coupling
The water side of state joins end to end with vapour side, completes acting process；When starting or decoupling operation, the coupling decoupling of vapour side, non-core combustion
Material can discharge and reforming unit 1 is not run, and coupling is not also run with steam turbine high-pressure cylinder, and the steam that nuclear island generates only enters coupling
It is done work and is generated electricity with turbine low pressure cylinder 11.
Coupling process of the present invention makes full use of the technical characterstic of nuclear island and fossil-fuel boiler, and water and vapor are divided
Grade, segmentation rise parameter, improve generating efficiency by breaking through thermal power generating equipment to adapt to the thinking of nuclear island parameter.Wherein it has been generally acknowledged that
The higher nuclear island part of technical difficulty can slightly change can be realized on the basis of existing mature technology, fossil-fuel boiler part
It is also easy to realize by the optimization of conventional design means, therefore with other efficient nuclear power technologies (as Zhu Shutang 2007 propose
It is scheme that Modular high-temperature air cooled reactor technology is coupled with supercritical steam power cycle technology mature at present, overcritical
Water cooled reator technology etc.) it compares, a whole set of technology is more easily performed.
When normal coupling operation, flue gas before making full use of denitrification apparatus heats water supply, and when normal coupling operation does not have to
Put into operation high-pressure heater, and the height of saving adds steam extraction to can be used for generating electricity, and takes full advantage of high-quality energy, due to being filled in denitration
Economizer and medium temperature flue gas waste heat utilization device are provided with before setting 3,3 entrance flue gas temperature of denitrification apparatus can be reduced to commonly
350 degrees centigrades that denitrating catalyst can be born, and do not have to using expensive high temperature denitrating catalyst.
Coupling and decoupling method are related to double-strand coupling process.The liter parametric procedure of traditional thermal power plant, water and vapor
It is carried out all in fossil-fuel boiler；The liter parametric procedure of traditional nuclear power plant, water and vapor carries out all in nuclear island.This is specially
Coupling process described in benefit makes full use of the technical characterstic of nuclear island and fossil-fuel boiler, and water and vapor are carried out double-strand coupling
It closes, it may be assumed that
The parameter of gasification of the water in nuclear island takes full advantage of the parameter area of existing reactor core primary Ioops, such as
AP1000 primary Ioops hot-side temperature is about 324 DEG C, it is contemplated that the factors such as heat exchange difference, the upper limit of corresponding secondary circuit outlet temperature
Substantially at 300 DEG C hereinafter, the corresponding pressure of 300 DEG C of saturated vapors is about 8.58MPa according to the thermal physical property data of saturated vapor.
For preferred 280 DEG C of secondary circuit outlet temperature design parameter, the corresponding pressure of saturated vapor is about 6.4MPa, this and modern times
The secondary circuit pressure and temperature of commercial nuclear power plant relatively coincide.Due to the inlet and outlet fluid properties of nuclear island in coupled system and now
The generation inlet and outlet fluid properties of commercial nuclear island are very close, so difficult point is technically not present, this is dropped significantly for nuclear island
Low technical application difficulty.In fossil-fuel boiler, since the vaporescence from liquid water to steam still occurring in the boiler,
Still using conventional water-cooling wall, this technology carries out appropriate there is no the essential problem manufactured and designed on the basis of conventional boiler
Parameters Optimal Design can be realized, this greatly reduces technical application difficulty.
In coupled heat system, the vapor (steam) temperature into the superheated steam of steam turbine has reached close to critical or overcritical steaming
The parameter of vapour power cycle, in general, turbine inlet initial steam temperature and every 20 degree of the raising of reheat temperature, cycle efficieny can
To improve 1 percentage point, for overcritical 566 DEG C, compared with 280 DEG C of conventional nuclear island 7, vapor (steam) temperature improves 286 DEG C,
So steam cycle efficiency theoretically can be improved about 14.3% or so, this will degree of being greatly reduced electricity cost, simultaneously as efficiency
It improves, compared with the nuclear power unit of same generated energy, coupling quantity of steam required for unit generation can also decline to a great extent about
15%, considered with identical loss of steam and water, moisturizing processing cost will also be greatly reduced.On the other hand, due to steam superheating
Degree is higher, and after steam turbine does work, exhaust steam moisture is far below the nuclear steam turbine of modern Commercial, therefore it is lighter to have use
The condition of more compact full speed steam turbine, greatly reduces investment.
When normal coupling operation, flue gas before making full use of denitrification apparatus heats water supply, and when normal coupling operation does not have to
Put into operation high-pressure heater, and the height of saving adds steam extraction to can be used for generating electricity, have document report (Sun Fengzhong, large-size steam turbine operation,
P178), when the height in traditional thermal power plant adds (high-pressure heater) all to withdraw from from heat regenerative system, the power of condensing turbine
10% can be increased, the power of cogeneration turbine can increase by 14%.
For traditional thermal power plant, height, which adds to withdraw from, will lead to reduction thermal efficiency of cycle, although therefore can be increased with multiple electricity
Coal consumption, thus it is in general uneconomical；But for the nuclear energy of 1000MW grade and fossil energy coupled system, due to the water inlet of nuclear island
Temperature requirement is not higher than 220 degrees Celsius, and the feed temperature than 300 degrees Celsius traditional of 1000MW thermal power plant is low, is fired by fossil
The medium temperature flue gas waste heat utilization device in dum boiler or fossil fuel direct current cooker back-end ductwork is expected to continue to heat water supply
Thermal efficiency of cycle will not be reduced.
Above-mentioned, although the foregoing specific embodiments of the present invention is described with reference to the accompanying drawings, not protects model to the present invention
The limitation enclosed, those skilled in the art should understand that, based on the technical solutions of the present invention, those skilled in the art are not
Need to make the creative labor the various modifications or changes that can be made still within protection scope of the present invention.
Claims (10)
1. a kind of high efficiency ultracritical nuclear power system characterized by comprising the condensation water system with low-temperature flue gas waste heat utilization apparatus
It is system, the water supply system with medium temperature flue gas waste heat utilization device, coupling steam turbine high-pressure cylinder, coupling turbine low pressure cylinder, non-
Nuclear fuel can discharge and reforming unit and nuclear island；The water supply system with medium temperature flue gas waste heat utilization device include: oxygen-eliminating device,
Feed pump, high-pressure heater and medium temperature flue gas waste heat utilization device；Oxygen-eliminating device, feed pump and high-pressure heater are sequentially connected in series company
It connects, the high-pressure heater and medium temperature flue gas waste heat utilization device are connected in parallel；
The output end of the condensate system with low-temperature flue gas waste heat utilization apparatus is connect with oxygen-eliminating device, normal coupling operation
When, the water supply of oxygen-eliminating device output, which enters in medium temperature flue gas waste heat utilization device, to be heated；When medium temperature flue gas waste heat utilization device stops
The water supply of used time, oxygen-eliminating device output are heated in high-pressure heater；
When normal coupling operation, the water supply after heating is divided into two-way, and first via water supply is connected to the feed-water intake of nuclear island, and the second tunnel is given
Water, which is connected to non-nuclear fuel, can discharge and reforming unit；When starting or decoupling operation when, the water supply after heating be only connected to nuclear island to
Water inlet；
The first via water supply enters nuclear island by the feed-water intake pipeline of nuclear island, and heated, vaporization becomes micro- superheated steam, institute
Micro- superheated steam is stated to export by nuclear island outlet vapor pipeline；
The outlet vapor pipeline of nuclear island is divided into two-way, wherein can discharge with non-nuclear fuel all the way and reforming unit is connect, another way
It is connect with coupling with turbine low pressure cylinder.
2. a kind of high efficiency ultracritical nuclear power system as described in claim 1, which is characterized in that the non-nuclear fuel can discharge and
Reforming unit includes sequentially connected economizer, water-cooling wall entrance header, water-cooling wall and the first superheater；
Second tunnel water supply can be discharged by non-nuclear fuel and the economizer entrance of reforming unit, goes forward side by side into economizer is heated
Enter water-cooling wall entrance header；Become height through the first superheater is heated again after the water cooled wall vaporization of the water supply of water-cooling wall entrance header
The superheated steam of overheat, referred to as the first superheated steam；
Nuclear island outlet vapor enter non-nuclear fuel can discharge and the second superheater of reforming unit it is heated after become height overheat
Superheated steam, referred to as the second superheated steam；
When normal coupling operation, first superheated steam and the second superheated steam are known as leading after super-heater exit case converges
Superheated steam, main superheat steam pipeline are connected with steam turbine high-pressure cylinder with coupling, and main superheated steam pushes high pressure cylinder acting and band
Dynamic first electrical power generators；When starting or decoupling operation, non-nuclear fuel can discharge and reforming unit is not run, and steamer is used in coupling
Machine high pressure cylinder is not also run, and the steam that nuclear island generates only enters the acting power generation of coupling turbine low pressure cylinder；
Further, it can be discharged by adjusting into non-nuclear fuel and the second overheat is steamed in the steam flow of reforming unit, realization
The adjusting of stripping temperature, and then realize the adjusting to main superheat steam temperature.
3. a kind of high efficiency ultracritical nuclear power system as claimed in claim 2, which is characterized in that can discharge and turn in non-nuclear fuel
Disguise set feedwater piping inlet setting blowpipe diffuse channel, nuclear island outlet vapor by nuclear island outlet vapor couple pipeline into
Enter the second superheater, then in turn through hot device outlet header, the first superheater, water-cooling wall, water-cooling wall entrance header and saves coal
Device finally enters blowpipe diffuse channel row Xiang great Qi.
4. a kind of high efficiency ultracritical nuclear power system as described in claim 1, which is characterized in that the band low-temperature flue gas waste heat benefit
It include: condenser, gland heater, low-pressure heater and low-temperature flue gas waste heat utilization apparatus with the condensate system of device；Institute
It states condenser to connect with gland heater, gland heater connects respectively with low-pressure heater and low-temperature flue gas waste heat utilization apparatus
It connects；When normal coupling operation, condensed water is heated in low-temperature flue gas waste heat utilization apparatus；Work as low-temperature flue gas waste heat utilization apparatus
When deactivating, condensed water is heated in low-pressure heater.
5. a kind of high efficiency ultracritical nuclear power system as described in claim 1, which is characterized in that non-nuclear fuel can be discharged and be converted
The flue gas of device discharge heats water supply in medium temperature flue gas waste heat utilization device, the cigarette come out from medium temperature flue gas waste heat utilization device
Gas successively enters low-temperature flue gas waste heat utilization apparatus after denitrification apparatus, air preheater, deduster and air-introduced machine, from low temperature
The flue gas that flue gas waste heat utilization device comes out passes through desulfurizer, is finally discharged from chimney.
6. a kind of high efficiency ultracritical nuclear power system as described in claim 1, which is characterized in that the nuclear island outlet vapor pipeline
It is divided into two-way pipeline, is all the way that nuclear island outlet vapor couples pipeline, being connected to non-nuclear fuel by the first valve can discharge and convert
Device, another way are nuclear island outlet vapor direct-furnish pipeline, are connected to coupling turbine low pressure cylinder by the second valve.
7. a kind of high efficiency ultracritical nuclear power system as described in claim 1, which is characterized in that the non-nuclear fuel can discharge and
Reforming unit select fossil fuel dum boiler or fossil fuel direct current cooker or other can be by the chemistry of non-nuclear fuel
It can be converted into thermal energy, and transfer thermal energy to the device of thermal cycle working medium.
8. a kind of high efficiency ultracritical nuclear power system as described in claim 1, which is characterized in that coupling is adopted with steam turbine high-pressure cylinder
With full speed steam turbine, and a high position is arranged in boiler export, and coupling uses half speed turbine with turbine low pressure cylinder；
Further, the parameter of coupling steam turbine high-pressure cylinder steam discharge uses the parameter of nuclear island outlet vapor, and steam turbine is used in coupling
The inlet steam parameter of low pressure (LP) cylinder can use the parameter of coupling steam turbine high-pressure cylinder steam discharge, can also use nuclear island outlet vapor
Parameter.
9. a kind of high efficiency ultracritical nuclear power system as described in claim 1, which is characterized in that further include: nuclear island accident spray
System, the nuclear island accident spray system include drawing condenser recirculated cooling water to bypass into answering above nuclear reactor all the way
Chilling but high water tank, cooling high water tank of meeting an urgent need are located at nuclear reactor safety shell top, when nuclear reactor generation accident conditions
Shower water is provided to containment from meeting an urgent need cooling high water tank, described shower water a part is heated to evaporate into atmosphere, another portion
Extra shower water is divided to fall into spray recycling pond, after the water in spray recycling pond enters cooling tower cooler by suction pump
Into cooling pond, water circulating pump entrance is connected to cooling pond, and water circulating pump outlet is divided into two-way, connects condenser all the way, separately
The cooling high water tank of connection emergency all the way.
10. a kind of working method of high efficiency ultracritical nuclear power system characterized by comprising
The coupling of water side: coupling is condensed in condenser with turbine low pressure cylinder steam discharge becomes condensed water, when normal coupling is run, coagulates
It bears water and is heated in low-temperature flue gas waste heat utilization apparatus；When low-temperature flue gas waste heat utilization apparatus deactivates, condensed water is in low pressure
It is heated in heater；Condensed water after heating enters oxygen-eliminating device；
When normal coupling operation, the condensed water of oxygen-eliminating device output, which is directly entered in medium temperature flue gas waste heat utilization device, to be heated；When
When medium temperature flue gas waste heat utilization device deactivates, the condensed water of oxygen-eliminating device output is heated in high-pressure heater；
When normal coupling operation, the water supply after heating is divided into two-way, and first via water supply enters by the feed-water intake pipeline of nuclear island
Nuclear island, heated, vaporization become micro- superheated steam, and the second tunnel water supply is connected to that non-nuclear fuel can discharge and reforming unit is heated becomes
First superheated steam of height overheat；When starting or decoupling operation, water side coupling decoupling, the water supply after heating is only connected to nuclear island
Feed-water intake；
The coupling of vapour side: micro- superheated steam is exported by nuclear island outlet vapor pipeline, is divided into two-way: wherein entering non-nuclear fuel all the way
It can release and heated the second superheated steam for becoming height overheat of reforming unit；When normal coupling operation, the second superheated steam with
After first superheated steam converges, is done work and generated electricity with steam turbine high-pressure cylinder into coupling；Another way uses steam turbine high-pressure cylinder with coupling
Steam discharge converge after, into coupling with turbine low pressure cylinder do work generate electricity；
When starting or decoupling operation, the coupling decoupling of vapour side, non-nuclear fuel can discharge and reforming unit is not run, and steamer is used in coupling
Machine high pressure cylinder is not also run, and the steam that nuclear island generates only enters the acting power generation of coupling turbine low pressure cylinder；
Further,
It can be discharged and the flow of micro- superheated steam of reforming unit, be realized to entering non-nuclear fuel by adjusting into non-nuclear fuel
The adjusting of second superheat steam temperature of energy release and reforming unit, and then realize and done work into coupling with steam turbine high-pressure cylinder
Main steam temperature adjusting.
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