CN109448879B - Switchable supercritical carbon dioxide circulation cogeneration system for sodium-cooled fast reactor - Google Patents
Switchable supercritical carbon dioxide circulation cogeneration system for sodium-cooled fast reactor Download PDFInfo
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- CN109448879B CN109448879B CN201910027507.9A CN201910027507A CN109448879B CN 109448879 B CN109448879 B CN 109448879B CN 201910027507 A CN201910027507 A CN 201910027507A CN 109448879 B CN109448879 B CN 109448879B
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- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 title claims abstract description 64
- 239000001569 carbon dioxide Substances 0.000 title claims abstract description 35
- 229910002092 carbon dioxide Inorganic materials 0.000 title claims abstract description 35
- NWYRNCMKWHKPAI-UHFFFAOYSA-N C(=O)=O.[Na] Chemical compound C(=O)=O.[Na] NWYRNCMKWHKPAI-UHFFFAOYSA-N 0.000 claims abstract description 38
- 239000011734 sodium Substances 0.000 claims abstract description 12
- 229910052708 sodium Inorganic materials 0.000 claims abstract description 12
- QXNVGIXVLWOKEQ-UHFFFAOYSA-N Disodium Chemical compound [Na][Na] QXNVGIXVLWOKEQ-UHFFFAOYSA-N 0.000 claims abstract description 10
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 claims abstract description 10
- 238000010438 heat treatment Methods 0.000 claims description 12
- 238000001816 cooling Methods 0.000 claims description 6
- 238000012546 transfer Methods 0.000 claims description 3
- 239000002826 coolant Substances 0.000 claims 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 13
- 238000010248 power generation Methods 0.000 description 8
- 238000007906 compression Methods 0.000 description 4
- 230000000694 effects Effects 0.000 description 4
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 description 3
- 230000006835 compression Effects 0.000 description 3
- 230000007797 corrosion Effects 0.000 description 3
- 238000005260 corrosion Methods 0.000 description 3
- 238000011161 development Methods 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 238000006243 chemical reaction Methods 0.000 description 2
- 238000012360 testing method Methods 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 239000003518 caustics Substances 0.000 description 1
- 238000002485 combustion reaction Methods 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 239000002360 explosive Substances 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 125000004435 hydrogen atom Chemical class [H]* 0.000 description 1
- 230000010354 integration Effects 0.000 description 1
- 230000001737 promoting effect Effects 0.000 description 1
- 230000001172 regenerating effect Effects 0.000 description 1
- NASFKTWZWDYFER-UHFFFAOYSA-N sodium;hydrate Chemical compound O.[Na] NASFKTWZWDYFER-UHFFFAOYSA-N 0.000 description 1
- 238000012795 verification Methods 0.000 description 1
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
-
- 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
- F01K7/00—Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating
- F01K7/32—Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating the engines using steam of critical or overcritical pressure
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
- G21D5/04—Reactor and engine not structurally combined
- G21D5/06—Reactor and engine not structurally combined with engine working medium circulating through reactor core
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Combustion & Propulsion (AREA)
- Mechanical Engineering (AREA)
- Engine Equipment That Uses Special Cycles (AREA)
Abstract
A switchable supercritical carbon dioxide circulation cogeneration system for a sodium-cooled fast reactor belongs to the technical field of distributed energy sources. The invention aims to solve the problems of low heat and power combined supply circulation efficiency and poor system safety in the prior art by adopting steam-water working medium. The invention comprises a first loop for providing a heat source, a second loop for transferring heat, a third loop for converting heat energy into electric energy and a fourth loop for a heat supply pipe network, wherein the first loop and the second loop exchange heat through a sodium-sodium heat exchanger, the second loop and the third loop exchange heat through a sodium-carbon dioxide heat exchanger and realize power supply, the third loop is connected with a low-temperature heat regenerator, and the third loop and the fourth loop realize heat supply through the low-temperature heat regenerator. The invention can realize the switchable nuclear pile cogeneration, and the safety of the nuclear pile system is obviously improved by reasonably utilizing the characteristics of the sodium pile and combining the working medium operation parameters.
Description
Technical Field
The invention relates to a cogeneration system realized by supercritical carbon dioxide circulation, and belongs to the technical field of efficient clean energy utilization.
Background
The sodium-cooled fast reactor in the new generation of nuclear power is a key development reactor type with reliability through experimental verification. At present, a conventional island of a sodium-cooled fast reactor mainly adopts a steam-water working medium, but the thermodynamic cycle efficiency is lower due to the lower steam temperature (about 480 ℃). In addition, sodium-water reactions produce sodium hydroxide, a highly corrosive substance, and hydrogen, an explosive gas, which affects the safety of the nuclear reactor. The conventional island steam turbine adopting the steam-water working medium has huge volume, weight and auxiliary machine quantity, and the system integrated design is complex.
At present, domestic power requirements tend to be stable, but the internal combustion engine has obvious trend of reducing internal heat and promoting the development of large nuclear piles. Meanwhile, the concept of nuclear reactor heating is increasingly gaining attention for better utilization of nuclear energy. In order to improve the advantages of large nuclear pile in energy supply and reduce energy supply cost, development of a cogeneration cycle structure suitable for the nuclear pile is required.
Supercritical carbon dioxide brayton cycle power generation is considered a new power generation cycle mode that has potential to replace the steam-water rankine cycle. The main characteristic is that carbon dioxide is used as working medium and is always in supercritical state in circulation, the working medium has large energy flow density and strong heat carrying capacity, so that the volume of main equipment is obviously reduced compared with that of water-steam circulation, and the main equipment can also save water or be used in areas with lack of water resources. Simple circulation and recompression circulation are commonly adopted in test systems, and a simple circulation system is simple but low in efficiency, so that a cogeneration circulation system with high efficiency is needed to meet the cogeneration requirement of large-scale nuclear piles on land.
Disclosure of Invention
The invention aims to solve the problems of low heat and power combined supply circulation efficiency and poor system safety of the existing system realized by adopting a steam-water working medium, and further provides a switchable supercritical carbon dioxide circulation heat and power combined supply system for a sodium-cooled fast reactor.
The technical scheme of the invention is as follows:
the switchable supercritical carbon dioxide circulating cogeneration system for the sodium-cooled fast reactor comprises a first loop for providing a heat source, a second loop for transferring heat, a third loop for converting the heat energy into electric energy and a fourth loop for a heat supply pipe network, wherein the circulating working media of the first loop and the second loop are sodium, the circulating working media of the third loop and the fourth loop are carbon dioxide, the heat exchange is carried out between the first loop and the second loop through a sodium-sodium heat exchanger, the heat exchange is carried out between the second loop and the third loop through a sodium-carbon dioxide heat exchanger, the power supply is realized, the third loop is connected with a low-temperature heat regenerator, and the third loop and the fourth loop realize the heat supply through the low-temperature heat regenerator.
Further, the first loop realizes heat transfer in the core of the sodium-cooled fast reactor, the hot end outlet of the sodium-sodium heat exchanger is communicated with the hot end inlet of the sodium-carbon dioxide heat exchanger, and the cold end inlet of the sodium-sodium heat exchanger is communicated with the cold end outlet of the sodium-carbon dioxide heat exchanger; the third loop on be equipped with the turbine and with the generator that the turbine is connected, the hot junction export of sodium-carbon dioxide heat exchanger with the entry linkage of turbine, the hot junction entry of the exit linkage low temperature regenerator of turbine links to each other, the cold junction export of low temperature regenerator links to each other with the cold junction entry of sodium-carbon dioxide heat exchanger, the fourth loop on be equipped with cooler and main compressor, the hot junction export of low temperature regenerator communicates with the entry of cooler, the export of cooler links to each other with the entry of main compressor, the export of main compressor communicates with the cold junction entry of low temperature regenerator, the cooler is established to be connected with the heat supply pipe network interface, installs main compressor driving motor on the main compressor.
Further, a high-temperature heat regenerator is further arranged on the third loop, an outlet of the turbine is communicated with a hot end inlet of the high-temperature heat regenerator, a hot end outlet of the high-temperature heat regenerator is communicated with a hot end inlet of the low-temperature heat regenerator, a hot end outlet of the low-temperature heat regenerator is communicated with an inlet end of the fourth loop, an outlet end of the fourth loop is communicated with a cold end inlet of the low-temperature heat regenerator, a cold end outlet of the low-temperature heat regenerator is communicated with a cold end inlet of the high-temperature heat regenerator, and a cold end outlet of the high-temperature heat regenerator is communicated with a cold end inlet of the sodium-carbon dioxide heat exchanger.
The cold end of the low-temperature heat regenerator is connected with the cold end of the high-temperature heat regenerator through the flow combiner, and the outlet of the high-temperature heat regenerator is communicated with the cold end inlet of the high-temperature heat regenerator after being converged by the flow combiner.
Further, the cooler is communicated with the heat supply pipe network interface to realize heat supply.
The invention has the following beneficial effects:
1. The invention provides a land large-scale sodium-cooled fast reactor energy supply system, which adopts carbon dioxide circulating working medium to replace water-steam working medium used on the current test reactor, achieves or exceeds the original system efficiency, realizes switchable nuclear reactor cogeneration, and reasonably utilizes the characteristics of sodium reactor and the working medium operation parameters to obviously improve the safety of the nuclear reactor system;
2. According to the characteristics of the sodium-cooled fast reactor, the invention adopts the supercritical carbon dioxide working medium to match with the characteristics of the sodium-cooled fast reactor, and combines the land large-scale nuclear reactor cogeneration application background, so that a simple-recompression supercritical carbon dioxide energy supply system is designed, and the cycle efficiency of a pure power generation system can be realized to exceed 41%;
3. The switchable supercritical carbon dioxide circulating cogeneration system for the sodium-cooled fast reactor can realize cogeneration with the circulating power generation efficiency of 35 percent, provides hot water with the temperature of 85 ℃ and the pressure of 0.8MPa, and the heat power of the hot water accounts for 50 percent of the heat source power of a heat power loop;
4. The rotary machinery of the main compressor, the recompression and the turbine adopts split-shaft arrangement, is suitable for large-scale nuclear reactors on land, avoids technical difficulties in the process of high integration, and has more equipment and system adjustability.
Drawings
FIG. 1 is a system connection diagram of a switchable supercritical carbon dioxide cycle cogeneration system for a sodium cooled fast reactor;
In the figure, a first loop, a second loop, a third loop, a fourth loop, a 10-sodium cold fast reactor core, a 11-sodium heat exchanger, a 12-sodium-carbon dioxide heat exchanger, a 13-low temperature heat regenerator, a 14-high temperature heat regenerator, a 15-cooler, a 21-turbine, a 22-main compressor, a 23-recompressor, a 31-generator, a 32-main compressor driving motor, a 33-recompression driving motor, a 41-shunt, a 42-combiner and a 51-heating pipe network interface are arranged.
Detailed Description
The first embodiment is as follows: the switchable supercritical carbon dioxide circulating cogeneration system for a sodium-cooled fast reactor according to the present embodiment is described with reference to fig. 1, and includes a first circuit 1 for providing a heat source, a second circuit 2 for transferring heat, a third circuit 3 for converting heat energy into electric energy, and a fourth circuit 4 for a heating network, where the circulating media of the first circuit 1 and the second circuit 2 are sodium, the circulating media of the third circuit 3 and the fourth circuit are carbon dioxide, heat exchange is performed between the first circuit 1 and the second circuit 2 by a sodium-sodium heat exchanger 11, heat exchange is performed between the second circuit 2 and the third circuit 3 by a sodium-carbon dioxide heat exchanger 12, power supply is realized, a low-temperature regenerator 13 is connected to the third circuit 3, and the third circuit 3 and the fourth circuit 4 realize heat supply by the low-temperature regenerator 13. The supercritical carbon dioxide Brayton cycle power generation is adopted as a potential novel power generation cycle mode, and is mainly characterized in that carbon dioxide is used as a working medium and is always in a supercritical state in the cycle, the energy flow density of the working medium is high, the heat carrying capacity is high, the volume of main equipment of the whole cogeneration system which uses the supercritical carbon dioxide as the cycle working medium is obviously reduced compared with that of water-steam cycle, and meanwhile, the system can save water or be used in areas with lack of water resources.
The second embodiment is as follows: referring to fig. 1, a switchable supercritical carbon dioxide circulating cogeneration system for a sodium-cooled fast reactor according to the present embodiment is described, wherein the first loop 1 realizes heat transfer inside a sodium-cooled fast reactor core 10, a hot end outlet of a sodium-sodium heat exchanger 11 is communicated with a hot end inlet of a sodium-carbon dioxide heat exchanger 12, and a cold end inlet of the sodium-sodium heat exchanger 11 is communicated with a cold end outlet of the sodium-carbon dioxide heat exchanger 12; the third loop 3 is provided with a turbine 21 and a generator 31 connected with the turbine 21, a hot end outlet of the sodium-carbon dioxide heat exchanger 12 is connected with an inlet of the turbine 21, an outlet of the turbine 21 is connected with a hot end inlet of the low-temperature heat regenerator 13, a cold end outlet of the low-temperature heat regenerator 13 is connected with a cold end inlet of the sodium-carbon dioxide heat exchanger 12, the fourth loop 4 is provided with a cooler 15 and a main compressor 22, a hot end outlet of the low-temperature heat regenerator 13 is communicated with an inlet of the cooler 15, an outlet of the cooler 15 is connected with an inlet of the main compressor 22, an outlet of the main compressor 22 is communicated with a cold end inlet of the low-temperature heat regenerator 13, the cooler 15 is connected with a heating pipe network interface 51, and a main compressor driving motor 32 is arranged on the main compressor 22; the main compressor 22 is driven by a main compressor drive motor 32, the recompression 23 is driven by a recompression drive motor 33, and the generator 31 is driven by the turbine 21.
And a third specific embodiment: referring to fig. 1, the switchable supercritical carbon dioxide circulation cogeneration system for a sodium-cooled fast reactor according to the present embodiment is described, wherein the third circuit 3 is further provided with a high-temperature regenerator 14, an outlet of the turbine 21 is connected to a hot-side inlet of the high-temperature regenerator 14, a hot-side outlet of the high-temperature regenerator 14 is connected to a hot-side inlet of the low-temperature regenerator 13, a hot-side outlet of the low-temperature regenerator 13 is connected to an inlet end of the fourth circuit 4, an outlet end of the fourth circuit 4 is connected to a cold-side inlet of the low-temperature regenerator 13, a cold-side outlet of the low-temperature regenerator 13 is connected to a cold-side inlet of the high-temperature regenerator 14, and a cold-side outlet of the high-temperature regenerator 14 is connected to a cold-side inlet of the sodium-carbon dioxide heat exchanger 12. So set up, be provided with high temperature regenerator 14 on third circuit 3, high temperature regenerator 14 can improve the heat exchange efficiency between third circuit 3 and the fourth circuit 4, guarantees that the system remains high efficiency during the change of power supply and/or heat supply demand.
The specific embodiment IV is as follows: referring to fig. 1, the switchable supercritical carbon dioxide circulation cogeneration system for a sodium-cooled fast reactor according to this embodiment is described, a recompression 23 is disposed in parallel on the fourth loop 4, a diverter 41 and a combiner 42 are further disposed on the fourth loop 4, a hot end outlet of the low-temperature regenerator 13 is connected to an inlet of the diverter 41, one of two branches of the low-temperature regenerator 13 is connected to the cooler 15 through one end of the diverter 41, an outlet of the cooler 15 is connected to an inlet of the main compressor 22, an outlet of the main compressor 22 is connected to a cold end inlet of the low-temperature regenerator 13, the other end of the two branches of the diverter 41 is connected to an inlet of the recompression 23, and an outlet of the recompression 23 is connected to a cold end inlet of the high-temperature regenerator 14 after being combined with the cold end of the low-temperature regenerator 13 through the combiner 42. The arrangement of the recompression device 23 in parallel connection with the fourth loop 4 can improve the thermoelectric efficiency of the system, and is characterized in that the circulation efficiency of the carbon dioxide circulation working medium in the third loop 3 communicated with the fourth loop under the action of the recompression device 23 is enhanced, so that the recompression device 23 in parallel connection improves the thermoelectric efficiency of the whole cogeneration system, the recompression device 23 in parallel connection interconnects the third loop 3 and the fourth loop 4 on the whole, the effect achieved by the interconnection is far greater than the effect of only increasing the heat supply circulation efficiency achieved by only adding the serial compressors on the fourth loop, and the parallel connection mode has a more reasonable control system, and can realize independent control of the on-off of the parallel connection line in the cogeneration process, thereby effectively controlling the cogeneration efficiency.
The parallel arrangement of the recompressor 23 on the fourth loop 4 provided by the embodiment is a significant breakthrough of the invention in the cogeneration energy system, and the mode improves the cogeneration efficiency and further improves the energy utilization rate.
To further illustrate that the use of the recompressor 23 to increase cogeneration efficiency is greater than the effect of merely increasing heating cycle efficiency achieved by merely adding a series compressor to the fourth circuit, the following is set forth in detail:
The fourth loop is connected with a recompressor in parallel, at the moment, the circulating working medium output through the hot end outlet of the low-temperature heat regenerator 13 is split by the splitter 41, one part of the circulating working medium is used for heating a heating pipe network, the other part of the circulating working medium enters the sodium-carbon dioxide heat exchanger 12 after passing through the recompressor 23 and the high-temperature heat regenerator 14, the circulating working medium enters the sodium-carbon dioxide heat exchanger 12 for heat exchange again and then is used for turbine 21 to apply work and generate power, at the moment, the power supply of the third loop 3 and the heating efficiency of the fourth loop 4 are both improved, and the power supply and the heating efficiency of the fourth loop 4 are synchronously carried out;
the effect of the parallel recompression 23 is therefore significant.
Fifth embodiment: referring to fig. 1, the switchable supercritical carbon dioxide circulation cogeneration system for a sodium-cooled fast reactor according to the present embodiment is described, wherein the recompressor 23 is provided with a recompression driving motor 33, and the cooler 15 is communicated with a heating pipe network interface 51 to supply heat.
Specific embodiment six: referring to fig. 1, the switchable supercritical carbon dioxide cycle cogeneration system for a sodium-cooled fast reactor in this embodiment is described, and the turbocompressor split shaft structure is characterized in that a turbine is arranged, a compressor split shaft is arranged, a turbine driving motor generates electricity, a compressor is driven by the compressor driving motor, the turbocompressor comprises a turbine 21, a main compressor 22, a recompressor 23, a generator 31, a main compressor driving motor 32, a recompression driving motor 33, a low-temperature regenerator 13, a high-temperature regenerator 14, a cooler 15, a shunt 41 and a confluence device 42, the sodium-carbon dioxide heat exchanger 12 exchanges heat in a heat source of the sodium-cooled fast reactor core 10, a cold end outlet of the sodium-carbon dioxide heat exchanger 12 is connected with an inlet of the turbine 21, an outlet of the turbine 21 is connected with a hot end inlet of the high-temperature regenerator 14, a hot end outlet of the high-temperature regenerator 14 is connected with a hot end inlet of the low-temperature regenerator 13, an outlet of the low-temperature regenerator 13 is connected with an inlet of the shunt 41, an outlet of the shunt 41 is connected with a B outlet of the shunt 41 is connected with the cooler 15, an outlet of the main compressor 15 is connected with a cold end inlet of the low-temperature regenerator 22, a cold end of the shunt 41 is connected with a cold end of the cold end 12 is connected with a cold end of the high-carbon dioxide heat exchanger 12, and a cold end of the cold end 42 is connected with a cold end of the high-carbon dioxide heat regenerator 14 is connected with a cold end inlet of the cold end 12; the main compressor 22 is driven by a main compressor driving motor 32, the recompression 23 is driven by a recompression driving motor 33, and the generator 31 is driven by the turbine 21; the outlet of the cooling working medium side of the cooler 15 is connected with the output end of the heat supply pipe network interface 51.
The circulation structure can be switched through a heat regenerator, a confluence device and a shunt bypass, when the bypass of the low-temperature heat regenerator 13, the bypass of the confluence device 42 and the bypass of the shunt 41 are closed, the third loop only outputs electric energy, the turbine 21 and the generator 31 connected with the turbine 21, the hot end outlet of the sodium-carbon dioxide heat exchanger 12 is connected with the inlet of the turbine 21, the outlet of the turbine 21 is connected with the hot end inlet of the high-temperature heat regenerator 14, the hot end outlet of the high-temperature heat regenerator 14 is connected with the inlet of the low-temperature heat regenerator 13, the hot end outlet of the low-temperature heat regenerator 13 is connected with the inlet of the shunt 41, the A outlet of the shunt 41 is connected with the inlet of the recompressor 23, the hot end outlet of the shunt 41B is connected with the cooler 15, the outlet of the cooler 15 is connected with the inlet of the main compressor 22, the outlet of the main compressor 22 is connected with the cold end inlet of the low-temperature heat regenerator 13, the cold end outlet of the low-temperature heat regenerator 14 is connected with the B inlet of the confluence device 42, the outlet of the high-temperature heat regenerator 14 is connected with the cold end inlet of the high-temperature heat regenerator 14, and the cold end outlet of the high-temperature heat regenerator 13 is connected with the cold end inlet of the sodium-carbon dioxide heat exchanger 12;
When the bypass of the low-temperature heat regenerator 13, the bypass of the combiner 42 and the bypass of the shunt 41 are opened, the third loop outputs electric energy and simultaneously starts the fourth loop to supply heat, and the water-cooling working medium of the cooler is used for supplying heat for users; the cold end outlet of the sodium-carbon dioxide heat exchanger 12 is connected with the inlet of the turbine 21, the outlet of the turbine 21 is connected with the hot end inlet of the high-temperature heat regenerator 14, the hot end outlet of the high-temperature heat regenerator 14 is connected with the hot end bypass inlet of the low-temperature heat regenerator 13, the hot end bypass outlet of the low-temperature heat regenerator 13 is connected with the bypass inlet of the diverter 41, the bypass outlet of the diverter 41 is connected with the cooler 15, the outlet of the cooler 15 is connected with the inlet of the main compressor 22, the outlet of the main compressor 22 is connected with the cold end bypass inlet of the low-temperature heat regenerator 14, the cold end bypass outlet of the low-temperature heat regenerator 14 is connected with the bypass inlet of the combiner 42, the bypass outlet of the combiner 42 is connected with the cold end inlet of the high-temperature heat regenerator 13, and the cold end outlet of the high-temperature heat regenerator 13 is connected with the cold end inlet of the sodium-carbon dioxide heat exchanger 12. The outlet of the cooling working medium side of the cooler 15 is connected with the output end of the heat supply pipe network interface 51.
The principle of the simple circulation cogeneration system is as follows: the system is characterized in that the recompression circulation is switched into the simple regenerative circulation through a device bypass, a cooler water-cooling working medium is used for user heat supply, a sodium-carbon dioxide heat exchanger 12 exchanges heat in a heat source of a sodium-cooled fast reactor core 10 and enters a turbine 21 to be used for acting of the turbine 21, further the power generation of a generator 31 is realized, the generated heat source is subjected to heat exchange through a low-temperature heat regenerator 13 and is provided for a cooler 15, and a cooling working medium side outlet of the cooler 15 is connected with an output end of a heat supply pipe network interface 51 and is used for providing heat for a heat supply pipe network.
In this embodiment, the sodium-carbon dioxide heat exchanger 12 has a sodium side pressure of normal pressure, i.e. one atmosphere, and a carbon dioxide side pressure of about 15 to 25MPa, when sodium-carbon dioxide realizes a heat exchange process in the sodium-carbon dioxide heat exchanger 12 and a pipe of the sodium-carbon dioxide heat exchanger 12 leaks, the circulating medium carbon dioxide in the sodium-carbon dioxide heat exchanger 12 can effectively block the secondary-loop sodium leakage caused by the damage of the heat exchanger channel, and the contact reaction of carbon dioxide and sodium is slow, and the product adheres to the contact surface, so that the risk of aggravating the accident degree is avoided, thereby obviously improving the safety of the nuclear reactor system.
In the embodiment, a micro-channel heat exchanger is adopted as the sodium-carbon dioxide heat exchanger 12, so that the performance of the end difference is less than 20 ℃, the size of the heat exchanger is twenty times that of a shell-and-tube heat exchanger, and the heat exchanger has corrosion resistance and compression resistance under the conditions of high temperature (300-480 ℃) and high pressure (15-25 MPa) of industrial-grade carbon dioxide, and has corrosion resistance and compression resistance under the conditions of 0.101MPa and 320-500 ℃ of a two-loop sodium working medium.
Meanwhile, a microchannel heat exchanger is adopted as the low temperature regenerator 13 and the high temperature regenerator 14: the performance of the end difference of less than 10 ℃ is achieved, the size of the heat exchanger is twenty times of that of a shell-and-tube heat exchanger, and the heat exchanger has corrosion resistance and compression resistance under the condition of high pressure (15 MPa-25 MPa) of industrial-grade carbon dioxide.
The thermodynamic characteristics of the circulation system are calculated and analyzed, and the obtained data result is as follows:
under the starting of the re-compression circulation in the scheme, if the turbine efficiency reaches 90% and the compressor efficiency reaches 85%, the circulation efficiency of the whole thermodynamic system can exceed 41%.
Under the condition of simple circulation starting, the combined heat and power can be realized, the circulation power generation efficiency is 35%, hot water with the temperature of 85 ℃ and the pressure of 0.8MPa is provided, and the heat power of the hot water accounts for 50% of the heat source power of the heat power loop.
The present embodiment is only exemplary of the present patent, and does not limit the scope of protection thereof, and those skilled in the art may also change the part thereof, so long as the spirit of the present patent is not exceeded, and the present patent is within the scope of protection thereof.
Claims (1)
1. A switchable supercritical carbon dioxide circulation cogeneration system for sodium-cooled fast reactor, its characterized in that: the heat supply system comprises a first loop (1) for providing a heat source, a second loop (2) for transferring heat, a third loop (3) for converting heat energy into electric energy and a fourth loop (4) for a heat supply pipe network, wherein the circulating working media of the first loop (1) and the second loop (2) are sodium, the circulating working media of the third loop (3) and the fourth loop are carbon dioxide, the heat exchange is carried out between the first loop (1) and the second loop (2) through a sodium-sodium heat exchanger (11), the heat exchange is carried out between the second loop (2) and the third loop (3) through a sodium-carbon dioxide heat exchanger (12), the power supply is realized, the third loop (3) is connected with a low-temperature heat regenerator (13), and the heat exchange is carried out between the third loop (3) and the fourth loop (4) through the low-temperature heat regenerator (13), and the heat supply is realized;
The first loop (1) realizes heat transfer in the sodium-cooled fast reactor core (10), a hot end outlet of the sodium-sodium heat exchanger (11) is communicated with a hot end inlet of the sodium-carbon dioxide heat exchanger (12), and a cold end inlet of the sodium-sodium heat exchanger (11) is communicated with a cold end outlet of the sodium-carbon dioxide heat exchanger (12); the third loop (3) is provided with a turbine (21) and a generator (31) connected with the turbine (21), a hot end outlet of the sodium-carbon dioxide heat exchanger (12) is connected with an inlet of the turbine (21), an outlet of the turbine (21) is connected with a hot end inlet of the low-temperature heat regenerator (13), a cold end outlet of the low-temperature heat regenerator (13) is connected with a cold end inlet of the sodium-carbon dioxide heat exchanger (12), the fourth loop (4) is provided with a cooler (15) and a main compressor (22), a hot end outlet of the low-temperature heat regenerator (13) is communicated with an inlet of the cooler (15), an outlet of the cooler (15) is connected with a cold end inlet of the low-temperature heat regenerator (13), the cooler (15) is connected with a heat supply pipe network interface (51), and a main compressor driving motor (32) is arranged on the main compressor (22);
The third loop (3) is also provided with a high-temperature heat regenerator (14), an outlet of the turbine (21) is communicated with a hot end inlet of the high-temperature heat regenerator (14), a hot end outlet of the high-temperature heat regenerator (14) is communicated with a hot end inlet of the low-temperature heat regenerator (13), a hot end outlet of the low-temperature heat regenerator (13) is communicated with an inlet end of the fourth loop (4), an outlet end of the fourth loop (4) is communicated with a cold end inlet of the low-temperature heat regenerator (13), a cold end outlet of the low-temperature heat regenerator (13) is communicated with a cold end inlet of the high-temperature heat regenerator (14), and a cold end outlet of the high-temperature heat regenerator (14) is communicated with a cold end inlet of the sodium-carbon dioxide heat exchanger (12);
The fourth loop (4) is provided with a recompression (23) in parallel, the fourth loop (4) is also provided with a diverter (41) and a combiner (42), the hot end outlet of the low-temperature heat regenerator (13) is connected with the inlet of the diverter (41), one end of two branches of the diverter (41) is connected with the cooler (15), the outlet of the cooler (15) is connected with the inlet of the main compressor (22), the outlet of the main compressor (22) is connected with the cold end inlet of the low-temperature heat regenerator (13), the other end of two branches of the diverter (41) is connected with the inlet of the recompression (23), and the outlet of the recompression (23) is connected with the cold end inlet of the high-temperature heat regenerator (14) after being combined by the combiner (42);
The recompression (23) is provided with a recompression driving motor (33), and the cooler (15) is communicated with the heating pipe network interface (51) to realize heating;
The circulating structure can be switched through a heat regenerator, a confluence device and a shunt bypass, when a bypass of a low-temperature heat regenerator (13), a bypass of a confluence device (42) and a bypass of a shunt (41) are closed, a third loop only outputs electric energy, a turbine (21) and a generator (31) connected with the turbine (21), a hot end outlet of a sodium-carbon dioxide heat exchanger (12) is connected with an inlet of the turbine (21), an outlet of the turbine (21) is connected with a hot end inlet of a high-temperature heat regenerator (14), a hot end outlet of the high-temperature heat regenerator (14) is connected with a hot end inlet of a low-temperature heat regenerator (13), a hot end outlet of the low-temperature heat regenerator (13) is connected with a shunt (41) inlet, an A outlet of the shunt (41) is connected with a recompressor (23) inlet, a B outlet of the shunt (41) is connected with a cooler (15), an outlet of the cooler (15) is connected with a main compressor (22) inlet, a main compressor (22) outlet is connected with a cold end inlet of the low-temperature regenerator (13), a cold end outlet of the low-temperature heat regenerator (13) is connected with a cold end inlet of the low-temperature heat regenerator (42) is connected with a cold end inlet of the low-temperature regenerator (42) and a cold end of the low-heat regenerator (42) is connected with a cold end inlet of the low-heat regenerator (42), the cold end outlet of the high-temperature heat regenerator (14) is connected with the cold end inlet of the sodium-carbon dioxide heat exchanger (12);
When the bypass of the low-temperature heat regenerator (13), the bypass of the combiner (42) and the bypass of the shunt (41) are opened, the third loop outputs electric energy and simultaneously starts the fourth loop to supply heat, and the water-cooling working medium of the cooler is used for supplying heat for users; the cold end outlet of the sodium-carbon dioxide heat exchanger (12) is connected with the inlet of the turbine (21), the outlet of the turbine (21) is connected with the hot end inlet of the high-temperature heat regenerator (14), the hot end outlet of the high-temperature heat regenerator (14) is connected with the hot end bypass inlet of the low-temperature heat regenerator (13), the hot end bypass outlet of the low-temperature heat regenerator (13) is connected with the bypass inlet of the shunt (41), the bypass outlet of the shunt (41) is connected with the cooler (15), the outlet of the cooler (15) is connected with the inlet of the main compressor (22), the outlet of the main compressor (22) is connected with the cold end bypass inlet of the low-temperature heat regenerator (13), the cold end bypass outlet of the low-temperature heat regenerator (13) is connected with the bypass inlet of the combiner (42), the cold end outlet of the high-temperature heat regenerator (14) is connected with the cold end inlet of the sodium-carbon dioxide heat exchanger (12), and the cooling medium side outlet of the cooler (15) is connected with the output end of the heat supply pipe network interface (51).
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