CN109184812B - Nuclear energy coupling chemical energy power generation system and method based on two-loop boiler - Google Patents
Nuclear energy coupling chemical energy power generation system and method based on two-loop boiler Download PDFInfo
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- CN109184812B CN109184812B CN201810995209.4A CN201810995209A CN109184812B CN 109184812 B CN109184812 B CN 109184812B CN 201810995209 A CN201810995209 A CN 201810995209A CN 109184812 B CN109184812 B CN 109184812B
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- 239000000126 substance Substances 0.000 title claims abstract description 35
- 238000010248 power generation Methods 0.000 title claims abstract description 27
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 50
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- 239000012943 hotmelt Substances 0.000 claims description 14
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- 238000000605 extraction Methods 0.000 description 12
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- VNWKTOKETHGBQD-UHFFFAOYSA-N methane Chemical compound C VNWKTOKETHGBQD-UHFFFAOYSA-N 0.000 description 8
- 238000005516 engineering process Methods 0.000 description 7
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- 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steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating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steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating the engines using steam of critical or overcritical pressure
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
- F01D15/00—Adaptations of machines or engines for special use; Combinations of engines with devices driven thereby
- F01D15/10—Adaptations for driving, or combinations with, electric generators
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K11/00—Plants characterised by the engines being structurally combined with boilers or condensers
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K13/00—General layout or general methods of operation of complete plants
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K25/00—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for
- F01K25/08—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for using special vapours
- F01K25/10—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for using special vapours the vapours being cold, e.g. ammonia, carbon dioxide, ether
-
- 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
- F01K25/00—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for
- F01K25/08—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for using special vapours
- F01K25/10—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for using special vapours the vapours being cold, e.g. ammonia, carbon dioxide, ether
- F01K25/103—Carbon dioxide
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Abstract
The invention discloses a nuclear energy coupling chemical energy power generation system and method based on a two-loop boiler, which comprises the following steps: the boiler is connected with the gas-molten salt heat exchanger to form a boiler primary loop, the gas-molten salt heat exchanger is respectively connected with the cold molten salt tank and the hot molten salt tank, and the cold molten salt tank and the hot molten salt tank are respectively connected with the molten salt-superheated steam heat exchanger to form a boiler secondary loop; the steam outlet of the nuclear island is divided into two paths, wherein one path is connected with a basic load steam turbine, and the other path is connected with a molten salt-superheated steam heat exchanger; the steam outlet of the fused salt-superheated steam heat exchanger is connected with a coupling steam turbine; the turbine with the basic load drives the first generator to generate power, and the turbine for coupling drives the second generator to generate power; the invention fully utilizes the characteristics of high specific heat capacity of special gas and translational process time of molten salt heat storage, improves the cycle heat efficiency and the power generation efficiency, and simultaneously improves the operation safety of a coupling system and the adaptability to variable working conditions.
Description
Technical Field
The invention relates to the technical field of energy, in particular to a nuclear energy coupling chemical energy power generation system and method based on a two-loop boiler.
Background
Pressurized water reactors are the mainstream technology of modern commercial nuclear power. Conventional pressurized water reactors are generally two-circuit systems, wherein steam in the two-circuit system drives a steam turbine to generate electricity. Due to the limitation of the temperature of the heat carrier of the reactor (the average outlet temperature of a pressurized water reactor is generally lower than 330 ℃), only saturated steam or slightly superheated steam (the superheat degree is 20-30 ℃) with lower pressure can be produced, the ideal specific enthalpy drop of the whole machine is very small, the steam humidity is high, and the steam flow is inevitably very large in order to increase the power of a single machine. The parameters of the secondary loop system of the current commercial nuclear power plant are about 6-8 MPa of pressure, about 230-290 ℃ of temperature and about 34% of generating efficiency. According to the Rankine cycle, the improvement of the power generation efficiency of the pressurized water reactor power station is limited because the steam parameters which can be generated by the two circuits are low.
Most of nuclear power plants use saturated steam, the work of the nuclear turbine 2/3 is completed in a low-pressure cylinder, but the exhaust steam humidity of the low-pressure cylinder of the nuclear turbine is large and generally reaches 12% -14%, and the corrosion and erosion of blades are easily caused, so a half-speed turbine is generally adopted, and a special steam-water separation reheater is required to be added behind the high-pressure cylinder for dehumidification and reheating. And the thermal power plant generally adopts superheated steam, has high superheat degree and generally adopts a full-speed steam turbine. The diameter of a half-speed turbine rotor reaches and is heavy, generally speaking, the material consumption of the half-speed turbine exceeds that of a full-speed turbine by 2 times, and for the whole unit, the weight of the half-speed turbine is about 1.2-2.4 times of that of the full-speed unit. The bearing load of the corresponding turbine foundation is increased, and the civil engineering investment is increased; the investment of the half-speed turbine in the aspects of transportation, hoisting, installation and the like is higher than that of the full-speed turbine. The cost of equipment and civil engineering is higher by 20-30% than that of full-speed machine (the whole conventional island is about 7% higher).
In the prior art, although a series-parallel coupling power generation system of nuclear energy and conventional energy and a direct overheating coupling power generation system of the nuclear energy and the conventional energy are provided, the problems of fault tolerance and safety caused by a coupling process are not solved. If adopt traditional water and the boiler of vapor working medium, because in coupling power generation system, water gasifies in the nuclear island, and the vapor after the gasification gets into the boiler, and the specific heat capacity of vapor is less than liquid water far away to lead to the design degree of difficulty of boiler to increase greatly, and the operation security must not guarantee.
Disclosure of Invention
The invention aims to solve the problems and provides a nuclear energy coupling chemical energy power generation system and method based on a two-loop boiler.
In order to achieve the purpose, the invention adopts the following technical scheme:
in one or more embodiments, a two-circuit boiler based nuclear energy coupled chemical energy power generation system is disclosed, comprising: the system comprises a cooling tower, a condenser, a deaerator, a high-pressure heater, a nuclear island, a boiler, a gas-molten salt heat exchanger, a hot molten salt tank, a cold molten salt tank, a molten salt-superheated steam heat exchanger, a turbine with basic load and a turbine for coupling;
the boiler is connected with the gas-molten salt heat exchanger through a gas circulating fan to form a boiler primary loop; the gas-molten salt heat exchanger is respectively connected with the cold molten salt tank and the hot molten salt tank, and the cold molten salt tank and the hot molten salt tank are respectively connected with the molten salt-superheated steam heat exchanger to form a second boiler loop;
the steam outlet of the nuclear island is divided into two paths, wherein one path is connected with a basic load steam turbine, and the other path is connected with a molten salt-superheated steam heat exchanger; the steam outlet of the molten salt-superheated steam heat exchanger is connected with a coupling steam turbine; the turbine with the basic load drives a first generator to generate power, and the turbine for coupling drives a second generator to generate power;
the exhaust steam of the coupling steam turbine is cooled into condensed water through a condenser, the condensed water enters a high-pressure heater for heating after passing through a deaerator, and the heated feed water enters a nuclear island.
Further, the coupling steam turbine includes: a high-pressure cylinder of the coupling steam turbine, a medium-pressure cylinder of the coupling steam turbine and a low-pressure cylinder of the coupling steam turbine; the steam outlet of the molten salt-superheated steam heat exchanger is connected with the steam inlet of a high-pressure cylinder of a coupling steam turbine, and the steam outlet of the high-pressure cylinder of the coupling steam turbine is connected with the molten salt-reheated steam heat exchanger; the molten salt-reheat steam heat exchanger is respectively connected with the cold molten salt tank and the hot molten salt tank; and a steam outlet of the molten salt-reheat steam heat exchanger is connected with a steam inlet of a coupling steam turbine intermediate pressure cylinder, a steam outlet of the coupling steam turbine intermediate pressure cylinder is connected with a steam inlet of a coupling steam turbine low pressure cylinder, and the coupling steam turbine low pressure cylinder is connected with a second generator.
Furthermore, the hot-melt salt tank is connected with the molten salt-superheated steam heat exchanger through a hot-melt salt pump for superheated steam, and the hot-melt salt tank is connected with the molten salt-reheated steam heat exchanger through a hot-melt salt pump for reheated steam.
Further, the coupling steam turbine includes: the high-pressure turbine cylinder for coupling and the low-pressure turbine cylinder for coupling are respectively connected with the second generator, the steam outlet of the fused salt-superheated steam heat exchanger is connected with the steam inlet of the high-pressure turbine cylinder for coupling, the steam outlet of the high-pressure turbine cylinder for coupling is connected with the steam inlet of the low-pressure turbine cylinder for coupling, and the low-pressure turbine cylinder for coupling is connected with the second generator.
Further, the hot-melt salt tank is connected with the molten salt-superheated steam heat exchanger through a hot-melt salt pump for superheated steam.
Furthermore, valves are respectively arranged on the connecting pipelines of the nuclear island, the fused salt-superheated steam heat exchanger and the steam turbine with the basic load.
Disclosed in one or more embodiments is a method of nuclear energy coupled chemical energy power generation based on a two-circuit boiler, comprising:
the boiler provides high-temperature gas for the gas-molten salt heat exchanger, cold molten salt enters the gas-molten salt heat exchanger from the cold molten salt tank, the cold molten salt is heated by the high-temperature gas to form hot molten salt, and the hot molten salt enters the hot molten salt tank;
the feedwater is heated and then enters a nuclear island, the feedwater is heated and evaporated in the nuclear island to become saturated steam or wet steam, one part of the saturated steam or the wet steam enters a steam turbine with basic load to do work, and the other part of the saturated steam or the wet steam enters a molten salt-superheated steam heat exchanger;
after entering a molten salt-superheated steam heat exchanger to heat saturated steam or wet steam coming out of the nuclear island, the hot molten salt in the hot molten salt tank is cooled into cold molten salt and enters a cold molten salt tank; saturated steam or wet steam entering the molten salt-superheated steam heat exchanger is heated by hot molten salt to become superheated steam, and the superheated steam enters the coupling steam turbine to do work.
Further, the coupling steam turbine includes: a high-pressure cylinder of the coupling steam turbine, a medium-pressure cylinder of the coupling steam turbine and a low-pressure cylinder of the coupling steam turbine; the superheated steam enters a high-pressure cylinder of the coupling steam turbine, exhaust steam of the high-pressure cylinder of the coupling steam turbine is heated by hot molten salt to become reheated steam, the reheated steam enters a medium-pressure cylinder of the coupling steam turbine to do work, and exhaust steam of the medium-pressure cylinder of the coupling steam turbine enters a low-pressure cylinder of the coupling steam turbine to do work to drive a generator to generate power.
Further, the coupling steam turbine includes: a high-pressure cylinder of the coupling steam turbine and a low-pressure cylinder of the coupling steam turbine; the superheated steam enters a high-pressure cylinder of a coupling steam turbine to do work, and the exhaust steam of the high-pressure cylinder of the coupling steam turbine enters a low-pressure cylinder of the coupling steam turbine to do work to drive a generator to generate power.
Further, in the first stage of starting and load increasing, saturated steam or wet steam at the outlet of the nuclear island only enters a steam turbine with basic load to do work and generate electricity; in the second stage of starting and load increasing, the boiler is started and heats the molten salt for heat storage; in the third stage of starting and load increasing, a parallel coupling operation mode is entered, when the temperature of the molten salt reaches a set required value, steam for maintaining the basic load of the nuclear island still enters a steam turbine with the basic load, simultaneously, the amount of water supply entering the nuclear island and the amount of steam coming out of the nuclear island are increased, the steam except for the steam for maintaining the basic load of the nuclear island enters a molten salt-superheated steam heat exchanger to be further heated into superheated steam, and the superheated steam enters a coupling steam turbine to do work;
further, when the boiler fault time is less than a set threshold value, the system enters a primary decoupling operation mode, a primary loop of the boiler is cut off, only a secondary loop of the boiler is operated, and the heat storage in the hot-melt salt tank is adopted to meet the steam heating requirement;
further, when the molten salt system cannot be used, the system enters a secondary decoupling operation mode, a primary loop and a secondary loop of the boiler are cut off, steam from the nuclear island only enters the steam turbine with the basic load, in order to enable the molten salt to be in a liquid state and not to be solidified, the requirement of molten salt heat preservation is met through electric tracing, electric energy consumed by the electric tracing is preferentially provided by the steam turbine with the basic load to drive the first generator to generate electricity, and the reverse electricity of the power grid is only used as a standby electricity;
furthermore, when the nuclear island suddenly breaks down to throw load or is shut down, the second loop of the boiler can be quickly stopped to operate, and because the thermal inertia of the boiler during load lifting is large, the first loop of the boiler can still continuously operate in a short time, the load is gradually reduced, heat generated in the process is stored in molten salt through the gas-molten salt heat exchanger to store heat, and the heat storage process provides sufficient and safe operation adjustment time for the boiler to throw load or shut down along with the nuclear island.
Compared with the prior art, the invention has the beneficial effects that:
1. the nuclear energy coupled chemical energy power generation system based on the two-loop boiler is specially designed, the characteristic of high specific heat capacity of special gas (such as helium, supercritical carbon dioxide and the like) is fully utilized, the heat energy released and converted from chemical energy fuel is absorbed, the characteristic that the process time can be translated by fused salt heat storage is fully utilized, the operation modes of three main process procedures under various different working conditions such as starting and parallel coupling, accident decoupling and the like are reasonably combined, and the operation safety and the adaptability to variable working conditions of the coupling system are improved while the cycle thermal efficiency and the power generation efficiency are improved.
2. Through setting up the fused salt storage tank, improved the thermal inertia of system, multiple variable working condition of adaptation that can be nimble and safe. The heating of steam is controlled through fused salt energy storage, and the fused salt flow can be adjusted through a fused salt pump, so that the adjustment of the superheated steam temperature and the reheated steam temperature is simple and accurate, and the load response of the power station to the power grid dispatching requirement is quick.
3. The boiler is divided into a primary loop and a secondary loop, the absorption process of the heat energy converted from the chemical energy and the storage and utilization process of the heat energy are separated, the primary loop is used for absorbing the heat energy converted from the chemical energy to the maximum extent, and the secondary loop is used for storing the heat energy and using the heat energy for heating steam. The two loops are separated, so that the two processes can be respectively controlled according to the operation requirements of the coupling system under different working conditions.
4. The steam turbine with the basic load is arranged, so that the nuclear island can maintain the minimum load to stably and independently operate for a long time under the working conditions of starting, decoupling and the like, and the economic loss and the safety risk of starting and stopping the reactor are greatly reduced; in addition, under the decoupling operation mode, the steam turbine with the basic load drives the first generator to generate electricity, and the electricity can be used for service power (such as fused salt heat tracing electricity) so as to enhance the safety of a fused salt system.
5. The steam temperature of the coupling system reaches 400-700 ℃, compared with the temperature below 300 ℃ at the outlet of the nuclear island, the circulating heat efficiency is greatly improved, and the power generated by the nuclear energy is greatly improved under the same investment and operation cost of the nuclear island, so that the efficient nuclear energy utilization is realized.
6. Because the superheat degree of the coupled steam is high, after the steam turbine works, the exhaust steam humidity is far lower than that of a modern commercial nuclear steam turbine, so that the coupled steam turbine has the condition of adopting a lighter and more compact full-speed steam turbine, and the investment cost is greatly reduced.
7. The nuclear island adopts the conventional two-loop technology of the nuclear island, the technology of the nuclear island is mature, and the radiation protection and waste treatment are also mature and simple.
Drawings
The accompanying drawings, which are incorporated in and constitute a part of this application, illustrate embodiments of the application and, together with the description, serve to explain the application and are not intended to limit the application.
FIG. 1 is a schematic diagram of a nuclear energy coupled chemical energy power generation system based on a two-loop boiler according to a first embodiment;
FIG. 2 is a schematic diagram of a nuclear energy coupled chemical energy power generation system based on a two-loop boiler according to a second embodiment;
wherein, 1, the nuclear island, 1-1, the nuclear reactor, 1-2, the steam generator, 1-3, a primary loop main pump of the nuclear island; 2. the system comprises a basic load turbine, 3, a first generator, 4, a molten salt-superheated steam heat exchanger, 5, a molten salt-reheated steam heat exchanger, 6, a hot molten salt tank, 7, a cold molten salt tank, 8, a cold molten salt pump, 9, a gas-molten salt heat exchanger, 10, a gas circulating fan, 11, a boiler, 12, a hot molten salt pump for superheated steam, 13, a hot molten salt pump for reheated steam, 14, a high-pressure heater, 15, a high-pressure turbine cylinder for coupling, 16, a medium-pressure turbine cylinder for coupling, 17, a low-pressure turbine cylinder for coupling, 18, a second generator, 19, a deaerator, 20, a water feeding pump, 21.1# low-pressure heaters, 22.2# low-pressure heaters, 23, a condenser, 24, a circulating water pump, 25, a cooling water tank and 26, and a cooling tower.
The specific implementation mode is as follows:
the invention is further described with reference to the following figures and examples.
It should be noted that the following detailed description is exemplary and is intended to provide further explanation of the disclosure. Unless defined otherwise, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this application belongs.
It is noted that the terminology used herein is for the purpose of describing particular embodiments only and is not intended to be limiting of example embodiments according to the present application. As used herein, the singular forms "a", "an" and "the" are intended to include the plural forms as well, and it should be understood that when the terms "comprises" and/or "comprising" are used in this specification, they specify the presence of stated features, steps, operations, devices, components, and/or combinations thereof, unless the context clearly indicates otherwise.
Example one
In one or more embodiments, a two-circuit boiler based nuclear energy coupled chemical energy power generation system is disclosed, as shown in fig. 1, comprising: the system comprises a nuclear island 1, a boiler 11, a gas-molten salt heat exchanger 9, a hot molten salt tank 6, a cold molten salt tank 7, a cold molten salt pump 8, a hot molten salt pump 12 for superheated steam, a hot molten salt pump 13 for reheated steam, a molten salt-superheated steam heat exchanger 4, a molten salt-reheated steam heat exchanger 5, a turbine 2 with basic load, a first generator 3, a turbine for coupling, a second generator 18, a low-pressure heater, a high-pressure heater 14, a deaerator 19, a condenser 23, a cooling tower 26, a circulating water pump 24, a water feed pump 20 and the like.
The nuclear island 1 comprises a nuclear reactor 1-1, a primary loop main pump 1-3 of the nuclear island, a steam generator 1-2 and the like. The feed water entering the nuclear island 1 is heated by the steam generator 1-2 and then evaporated into saturated steam or wet steam with the dryness of more than 0.9.
Wherein, the steam turbine for coupling includes: a coupling turbine high-pressure cylinder 15, a coupling turbine intermediate-pressure cylinder 16, and a coupling turbine low-pressure cylinder 17; a steam outlet of the fused salt-superheated steam heat exchanger 4 is connected with a steam inlet of a high-pressure cylinder 15 of the coupling steam turbine, a steam outlet of the high-pressure cylinder 15 of the coupling steam turbine is connected with a fused salt-reheated steam heat exchanger 5, and the fused salt-reheated steam heat exchanger 5 is respectively connected with a cold fused salt tank 7 and a hot fused salt tank 6; the molten salt-reheat steam heat exchanger 5 has a steam outlet connected to a steam inlet of a coupling turbine intermediate pressure cylinder 16, the coupling turbine intermediate pressure cylinder 16 has a steam outlet connected to a steam inlet of a coupling turbine low pressure cylinder 17, and the coupling turbine low pressure cylinder 17 is connected to a second power generator 18.
The boiler 11 is connected with the gas-molten salt heat exchanger 9 to form a boiler loop, the boiler 11 converts chemical energy into heat energy by burning chemical energy fuels (such as fossil fuels like coal, oil and natural gas, and renewable energy fuels like biomass and garbage), the heat energy is transferred out by special gas (such as helium and supercritical carbon dioxide), low-temperature gas (such as helium and supercritical carbon dioxide) is arranged at the inlet of the boiler, high-temperature gas (such as helium and supercritical carbon dioxide) is arranged at the outlet of the boiler, and circulating power of the gas is provided by a gas circulating fan 10 arranged at the inlet of the boiler.
The gas-molten salt heat exchanger 9 is respectively connected with the cold molten salt tank 7 and the hot molten salt tank 6, and the cold molten salt tank 7 and the hot molten salt tank 6 are respectively connected with the molten salt-superheated steam heat exchanger 4 to form a second boiler loop; cold molten salt is pumped into a gas-molten salt heat exchanger 9 from a cold molten salt tank 7 through a cold molten salt pump 8, the cold molten salt is heated by high-temperature gas to form hot molten salt, and the hot molten salt enters a hot molten salt tank 6. A part of hot molten salt in the hot molten salt tank 6 is pumped into the molten salt-superheated steam heat exchanger 4 through superheated steam by using a hot molten salt pump 12 to heat steam coming out of the nuclear island 1, and then cold molten salt cooled by the steam coming out of the nuclear island 1 enters a cold molten salt tank 7; the other part of the hot molten salt in the hot molten salt tank 6 is pumped into the molten salt-reheat steam heat exchanger 5 through the hot molten salt pump 13 for reheat steam to heat the exhaust steam of the high-pressure cylinder 15 of the coupling turbine coming out of the high-pressure cylinder 15 of the coupling turbine, and then the cold molten salt cooled by the exhaust steam of the high-pressure cylinder of the coupling turbine coming out of the high-pressure cylinder of the coupling turbine enters the cold molten salt tank 7.
An inlet of a circulating water pump 24 is connected with a cooling water tank 25, an outlet of the circulating water pump 24 is connected with a condenser 23 to cool the low-pressure cylinder for steam exhaust, circulating water after cooling the low-pressure cylinder for steam exhaust is heated and heated, and the circulating water enters the cooling water tank 25 after being cooled in a cooling tower 26. The cooling principle of the cooling tower 26 is the same as that of the cooling tower 26 of the conventional thermal power and nuclear power, for example, the cooling tower is cooled by adopting a cooling tower filling mode.
Condensed water in a condenser 23 sequentially passes through a # 1 low-pressure heater 21 and a # 2 low-pressure heater 22 to reach a deaerator 19, feed water at the outlet of the deaerator 19 enters the nuclear island 1 after passing through a feed water pump 20 and the high-pressure heater 14, deaerated water in the deaerator 19 is sent to the high-pressure heater 14 through the feed water pump 20 to be heated by high-pressure extraction steam, the feed water heated by the high-pressure extraction steam in the high-pressure heater 14 enters the nuclear island 1, and the feed water is heated and evaporated into saturated steam or wet steam with the dryness greater than 0.9 in the nuclear island 1. The extraction steam of the high pressure heater 14 is taken from the basic load turbine 2, the extraction steam of the # 1 low pressure heater 21 and the extraction steam of the # 2 low pressure heater 22 are taken from the coupling turbine low pressure cylinder 17, and the extraction steam of the deaerator 19 for heating is taken from the coupling turbine intermediate pressure cylinder 16.
It is noted that the art is conventionally bound to deaerators, which are referred to as condensate before and feedwater after deaerators.
Saturated steam or wet steam with the dryness of more than 0.9 at the outlet of the nuclear island 1 is divided into two paths, wherein the first path is connected to a turbine 2 with a basic load, and the second path is connected to a molten salt-superheated steam heat exchanger 4. The first path of saturated steam or wet steam with the dryness greater than 0.9 applies work in the turbine 2 with the basic load to drive the first generator 3 to generate electricity; the second path of saturated steam or wet steam with the dryness being more than 0.9 is heated by hot molten salt in the molten salt-superheated steam heat exchanger 4 to become superheated steam, the superheated steam enters the coupling steam turbine high-pressure cylinder 15 to do work, the exhaust steam of the coupling steam turbine high-pressure cylinder 15 is connected with the molten salt-reheated steam heat exchanger 5, the exhaust steam of the coupling steam turbine high-pressure cylinder 15 is heated by the hot molten salt in the molten salt-reheated steam heat exchanger 5 to become reheated steam, the reheated steam enters the coupling steam turbine intermediate-pressure cylinder 16 to do work, the exhaust steam of the coupling steam turbine intermediate-pressure cylinder 16 enters the coupling steam turbine low-pressure cylinder 17 to do work, and the high-pressure cylinder, the intermediate-pressure cylinder and the low-pressure cylinder of the coupling steam turbine do work to drive the second generator 18 to generate electricity.
A valve 2-2 is arranged on a connecting pipeline of the nuclear island 1 and the fused salt-superheated steam heat exchanger 4, and a valve 2-1 is arranged on a connecting pipeline of the nuclear island 1 and the steam turbine 2 with the basic load.
The working principle of the normal coupling operation condition is described above. Compared with the prior art, the invention can better embody the advantages of the invention that the invention can flexibly and safely adapt to a plurality of typical variable working conditions:
1. starting and coupling working conditions:
when the coupling system is started and loads are increased, in the first stage of starting and load increasing, the valve 2-2 is closed, the valve 2-1 is opened, and saturated steam or wet steam with the dryness greater than 0.9 at the outlet of the nuclear island enters the steam turbine 2 with the basic load to do work and generate power; in the second stage of starting and load increasing, the boiler 11 is started to heat the molten salt for heat storage; in the third stage of starting and load increasing, a parallel coupling operation mode is entered, when the temperature of the molten salt reaches a set required value, the valve 2-1 is still opened, steam for maintaining the basic load of the nuclear island still enters the steam turbine 2 with the basic load, meanwhile, the valve 2-2 is also opened, the amount of feed water entering the nuclear island 1 and the amount of steam coming out of the nuclear island 1 are increased, the steam except for the steam for maintaining the basic load of the nuclear island enters the molten salt-superheated steam heat exchanger 4 through the valve 2-2 and is further heated to be superheated steam, and the superheated steam enters the high-pressure cylinder 15 of the steam turbine for coupling to do work.
2. Boiler split working condition:
the operation of the nuclear island 1 involves a problem of nuclear safety, and the prior art does not solve the problem of how the coupling system adapts to the rapid adjustment of the load when the boiler is suddenly shut down. In the invention, when the boiler 11 breaks down for a short time, the system enters a primary decoupling operation mode, a primary loop of the boiler is cut off, only a secondary loop of the boiler is operated, the heating requirements of steam coming out of the nuclear island 1 and steam exhausted by a high-pressure cylinder of a coupling steam turbine coming out of a high-pressure cylinder 15 of the coupling steam turbine are met by adopting heat storage in a molten salt tank, the load of the whole coupling system can be gradually reduced by controlling the flow of hot molten salt, the load impact of sudden load reduction on the nuclear island 1 is avoided, and the safety of the operation of the nuclear reactor 1-1 under the working condition of sudden disconnection of the boiler 11 is ensured. The technical scheme of the invention adopts the molten salt tank for heat storage, the technology is mature and reliable, and the molten salt flow can be adjusted by the molten salt pump, so that the adjustment of the superheated steam temperature and the reheated steam temperature is simpler and more accurate.
3. Molten salt system split conditions:
when the fused salt system cannot be used due to an accident (such as a fused salt pump failure) and the like, the system enters a secondary decoupling operation mode, a secondary loop of the boiler is quickly cut off, the valve 2-2 is closed, the valve 2-1 is opened, and steam from the nuclear island 1 only enters the steam turbine 2 with the basic load. In order to ensure that the molten salt is maintained in a liquid state and is not solidified, the requirement of the molten salt heat preservation is met through electric tracing, electric energy consumed by the electric tracing is preferentially provided by the steam turbine 2 with the basic load to drive the first generator 3 to generate electricity, and reverse electricity of a power grid is only used as a standby power.
Simultaneously, a boiler primary circuit is gradually cut: the second loop of the boiler can be stopped quickly, and because the thermal inertia of the boiler during load lifting is large, the first loop of the boiler can still continue to operate in a short time, the load is reduced step by step, heat generated in the process is stored in molten salt through the gas-molten salt heat exchanger 9 for heat storage, and sufficient and safe operation adjustment time is provided for the boiler to dump load or stop following the nuclear island in the heat storage process.
4. The nuclear island accident disconnection working condition is as follows:
the prior art does not have the heat accumulation function, does not solve when the sudden failure load shedding of nuclear island or shut down, the problem of how to adjust the load of boiler. In the invention, when the nuclear island 1 suddenly breaks down to throw load or stop, the primary loop of the boiler can still continue to operate in a short time, the load is gradually reduced, heat generated in the process is stored in molten salt through the gas-molten salt heat exchanger 9 to store heat, and the heat storage process provides sufficient and safe operation adjustment time for the boiler to throw load or stop following the nuclear island.
In some embodiments, the turbine 2 with the basic load is a half-speed turbine, and the coupling turbine is a full-speed turbine. Because the steam adopted by the steam turbine 2 with the basic load is saturated steam or wet steam with the dryness greater than 0.9, and the rated capacity of the steam turbine 2 with the basic load is smaller, the influence on saving investment is not great, and therefore, the preferred scheme still adopts a half-speed steam turbine commonly used for nuclear power. The coupling steam turbine uses highly superheated steam to avoid erosion and corrosion of wet steam to blades, so that the coupling steam turbine has a condition of using a full-speed steam turbine.
Example two
In one or more embodiments, a two-circuit boiler based nuclear energy coupled chemical energy power generation system is disclosed, as shown in fig. 2, comprising: the system comprises a nuclear island 1, a boiler 11, a gas-molten salt heat exchanger 9, a hot molten salt tank 6, a cold molten salt tank 7, a cold molten salt pump 8, a hot molten salt pump 12 for superheated steam, a molten salt-superheated steam heat exchanger 4, a turbine with basic load 2, a first generator 3, a turbine for coupling, a second generator 18, a low-pressure heater, a high-pressure heater 14, a deaerator 19, a condenser 23, a cooling tower 26, a circulating water pump 24, a water feed pump 20 and the like.
The nuclear island 1 comprises a nuclear reactor 1-1, a primary loop main pump 1-3 of the nuclear island, a steam generator 1-2 and the like. The feed water entering the nuclear island 1 is heated by the steam generator 1-2 and then evaporated into saturated steam or wet steam with the dryness of more than 0.9.
Wherein, the coupling steam turbine comprises a coupling steam turbine high pressure cylinder 15 and a coupling steam turbine low pressure cylinder 17; the exhaust steam of the high-pressure coupling turbine cylinder 15 directly enters the low-pressure coupling turbine cylinder 17 to do work, and the exhaust steam of the low-pressure coupling turbine cylinder 17 is connected with a condenser 23.
The boiler 11 is connected with the gas-molten salt heat exchanger 9 to form a boiler loop, the boiler 11 converts chemical energy into heat energy by burning chemical energy fuels (such as fossil fuels like coal, oil and natural gas, and renewable energy fuels like biomass and garbage), the heat energy is transferred out by special gas (such as helium and supercritical carbon dioxide), low-temperature gas (such as helium and supercritical carbon dioxide) is arranged at the inlet of the boiler, high-temperature gas (such as helium and supercritical carbon dioxide) is arranged at the outlet of the boiler, and circulating power of the gas is provided by a gas circulating fan 10 arranged at the inlet of the boiler.
The gas-molten salt heat exchanger 9 is respectively connected with the cold molten salt tank 7 and the hot molten salt tank 6, and the cold molten salt tank 7 and the hot molten salt tank 6 are respectively connected with the molten salt-superheated steam heat exchanger 4 to form a second boiler loop; cold molten salt is pumped into a gas-molten salt heat exchanger 9 from a cold molten salt tank 7 through a cold molten salt pump 8, the cold molten salt is heated by high-temperature gas to form hot molten salt, and the hot molten salt enters a hot molten salt tank 6. The hot molten salt in the hot molten salt tank 6 is pumped into the molten salt-superheated steam heat exchanger 4 through the hot molten salt pump 12 for superheated steam to heat the steam coming out of the nuclear island 1, and then the cold molten salt cooled by the steam coming out of the nuclear island 1 enters the cold molten salt tank 7.
An inlet of a circulating water pump 24 is connected with a cooling water tank 25, an outlet of the circulating water pump 24 is connected with a condenser 23 to cool the low-pressure cylinder for steam exhaust, circulating water after cooling the low-pressure cylinder for steam exhaust is heated and heated, and the circulating water enters the cooling water tank 25 after being cooled in a cooling tower 26. The cooling principle of the cooling tower 26 is the same as that of the cooling tower 26 of the conventional thermal power and nuclear power, for example, the cooling tower is cooled by adopting a cooling tower filling mode.
Condensed water in a condenser 23 sequentially passes through a # 1 low-pressure heater 21 and a # 2 low-pressure heater 22 to reach a deaerator 19, feed water at the outlet of the deaerator 19 enters the nuclear island 1 after passing through a feed water pump 20 and the high-pressure heater 14, deaerated water in the deaerator 19 is sent to the high-pressure heater 14 through the feed water pump 20 to be heated by high-pressure extraction steam, the feed water heated by the high-pressure extraction steam in the high-pressure heater 14 enters the nuclear island 1, and the feed water is heated and evaporated into saturated steam or wet steam with the dryness greater than 0.9 in the nuclear island 1. The extraction steam of the high-pressure heater 14 is taken from the turbine with basic load 2, the extraction steam of the # 1 low-pressure heater 21 and the extraction steam of the # 2 low-pressure heater 22 are taken from the turbine low-pressure cylinder 17 for coupling, and the extraction steam of the deaerator 19 for heating is taken from the turbine with basic load 2.
It is noted that the art is conventionally bound to deaerators, which are referred to as condensate before and feedwater after deaerators.
Saturated steam or wet steam with the dryness of more than 0.9 at the outlet of the nuclear island 1 is divided into two paths, wherein the first path is connected to a turbine 2 with a basic load, and the second path is connected to a molten salt-superheated steam heat exchanger 4. The first path of saturated steam or wet steam with the dryness greater than 0.9 applies work in the turbine 2 with the basic load to drive the first generator 3 to generate electricity; the second path of saturated steam or wet steam with the dryness being more than 0.9 is heated by hot molten salt in the molten salt-superheated steam heat exchanger 4 to become superheated steam, the superheated steam enters the high-pressure cylinder 15 of the coupling steam turbine for acting, the exhaust steam of the high-pressure cylinder 15 of the coupling steam turbine enters the low-pressure cylinder 17 of the coupling steam turbine for acting, and the high-pressure cylinder and the low-pressure cylinder of the coupling steam turbine for acting drive the second generator 18 to generate power.
A valve 2-2 is arranged on a connecting pipeline of the nuclear island 1 and the fused salt-superheated steam heat exchanger 4, and a valve 2-1 is arranged on a connecting pipeline of the nuclear island 1 and the steam turbine 2 with the basic load.
The working principle of the normal coupling operation condition is described above. Compared with the prior art, the invention can better embody the advantages of the invention that the invention can flexibly and safely adapt to a plurality of typical variable working conditions:
1. starting and coupling working conditions:
when the coupling system is started and loads are increased, in the first stage of starting and load increasing, the valve 2-2 is closed, the valve 2-1 is opened, and saturated steam or wet steam with the dryness greater than 0.9 at the outlet of the nuclear island 1 enters the steam turbine 2 with the basic load to do work and generate power; in the second stage of starting and load increasing, the boiler 11 is started to heat the molten salt for heat storage; in the third stage of starting and load increasing, a parallel coupling operation mode is entered, when the temperature of the molten salt reaches a set required value, the valve 2-1 is still opened, steam for maintaining the basic load of the nuclear island still enters the steam turbine 2 with the basic load, meanwhile, the valve 2-2 is also opened, the amount of feed water entering the nuclear island 1 and the amount of steam coming out of the nuclear island 1 are increased, the steam except for the steam for maintaining the basic load of the nuclear island enters the molten salt-superheated steam heat exchanger 4 through the valve 2-2 and is further heated to be superheated steam, and the superheated steam enters the high-pressure cylinder 15 of the steam turbine for coupling to do work.
2. Boiler split working condition:
the operation of the nuclear island relates to the problem of nuclear safety, and the prior art does not solve the problem of how to adapt a coupling system to quickly adjust the load when the boiler is suddenly shut down. In the invention, when the boiler 11 breaks down for a short time, the system enters a primary decoupling operation mode, a primary loop of the boiler is cut off, only a secondary loop of the boiler is operated, the heat storage in the molten salt tank is adopted to meet the heating requirement of the steam coming out of the nuclear island 1, the load of the whole coupling system can be gradually reduced by controlling the flow of the hot molten salt, the load impact of sudden load drop on the nuclear island 1 is avoided, and the safety of the operation of the nuclear reactor 1-1 under the working condition of sudden disconnection of the boiler 11 is ensured. The technical scheme of the invention adopts the molten salt tank to store heat, the technology is mature and reliable, and the flow of the molten salt can be adjusted by the molten salt pump, so that the adjustment of the temperature of the superheated steam is simple and accurate.
3. Molten salt system split conditions:
when the fused salt system cannot be used due to an accident (such as a fused salt pump failure) and the like, the system enters a secondary decoupling operation mode, a secondary loop of the boiler is quickly cut off, the valve 2-2 is closed, the valve 2-1 is opened, and steam from the nuclear island 1 only enters the steam turbine 2 with the basic load. In order to ensure that the molten salt is maintained in a liquid state and is not solidified, the requirement of the molten salt heat preservation is met through electric tracing, electric energy consumed by the electric tracing is preferentially provided by the steam turbine 2 with the basic load to drive the first generator 3 to generate electricity, and reverse electricity of a power grid is only used as a standby power.
Simultaneously, a boiler primary circuit is gradually cut: the second loop of the boiler can be stopped quickly, and because the thermal inertia of the boiler during load lifting is large, the first loop of the boiler can still continue to operate in a short time, the load is reduced step by step, heat generated in the process is stored in molten salt through the gas-molten salt heat exchanger 9 for heat storage, and sufficient and safe operation adjustment time is provided for the boiler to dump load or stop following the nuclear island in the heat storage process.
4. The nuclear island accident disconnection working condition is as follows:
the prior art does not have the heat accumulation function, does not solve when the sudden failure load shedding of nuclear island or shut down, the problem of how to adjust the load of boiler. In the invention, when the nuclear island 1 suddenly breaks down to throw load or stop, the primary loop of the boiler can still continue to operate in a short time, the load is gradually reduced, heat generated in the process is stored in molten salt through the gas-molten salt heat exchanger 9 to store heat, and the heat storage process provides sufficient and safe operation adjustment time for the boiler to throw load or stop following the nuclear island.
In some embodiments, the turbine 2 with the basic load is a half-speed turbine, and the coupling turbine is a full-speed turbine. Because the steam adopted by the steam turbine 2 with the basic load is saturated steam or wet steam with the dryness greater than 0.9, and the rated capacity of the steam turbine 2 with the basic load is smaller, the influence on saving investment is not great, and therefore, the preferred scheme still adopts a half-speed steam turbine commonly used for nuclear power. The coupling steam turbine uses highly superheated steam to avoid erosion and corrosion of wet steam to blades, so that the coupling steam turbine has a condition of using a full-speed steam turbine.
EXAMPLE III
In one or more embodiments, a method of nuclear energy coupled chemical energy power generation based on a two-circuit boiler is disclosed, comprising: the boiler 11 converts chemical energy into heat energy by burning chemical energy fuels (such as fossil fuels like coal, oil and natural gas, and renewable energy fuels like biomass and garbage), transfers the heat energy out by using special gases (such as helium and supercritical carbon dioxide), and provides low-temperature gases (such as helium or supercritical carbon dioxide with the temperature lower than 500 ℃) at the inlet of the boiler and high-temperature gases (such as helium or supercritical carbon dioxide with the temperature ranging from 500 ℃ to 700 ℃) at the outlet of the boiler, and the circulating power of the gases is provided by a gas circulating fan 10 at the inlet of the boiler.
The feedwater enters the nuclear island 1 after being heated in the high-pressure heater 14, is heated and evaporated in the nuclear island 1 to become saturated steam or wet steam with the dryness being more than 0.9, one part of the saturated steam or the wet steam with the dryness being more than 0.9 enters the turbine with the basic load 2 to do work, and the other part of the saturated steam or the wet steam enters the fused salt-superheated steam heat exchanger 4;
cold molten salt is pumped into a gas-molten salt heat exchanger 9 from a cold molten salt tank 7 through a cold molten salt pump 8, the cold molten salt is heated by high-temperature gas to form hot molten salt, and the hot molten salt enters a hot molten salt tank 6. A part of hot molten salt in the hot molten salt tank 6 is pumped into the molten salt-superheated steam heat exchanger 4 through superheated steam by using a hot molten salt pump 12 to heat steam coming out of the nuclear island 1, and then cold molten salt cooled by the steam coming out of the nuclear island 1 enters a cold molten salt tank 7; the other part of the hot molten salt in the hot molten salt tank 6 is pumped into the molten salt-reheat steam heat exchanger 5 through the hot molten salt pump 13 for reheat steam to heat the exhaust steam of the high-pressure coupling turbine cylinder 15 which is discharged from the high-pressure coupling turbine cylinder 15, and then the cold molten salt cooled by the exhaust steam of the high-pressure coupling turbine cylinder 15 which is discharged from the high-pressure coupling turbine cylinder 15 enters the cold molten salt tank 7. The exhaust steam of the high-pressure cylinder 15 of the coupling steam turbine is heated by hot molten salt in the molten salt-reheat steam heat exchanger 5 to become reheat steam, the reheat steam enters the intermediate pressure cylinder 16 of the coupling steam turbine to do work, the exhaust steam of the intermediate pressure cylinder 16 of the coupling steam turbine enters the low-pressure cylinder 17 of the coupling steam turbine to do work, and the high-pressure cylinder, the intermediate pressure cylinder and the low-pressure cylinder of the coupling steam turbine do work to drive the second generator 18 to generate electricity.
Compared with the prior art, the invention can better embody the advantages of the invention that the invention can flexibly and safely adapt to a plurality of typical variable working conditions:
1. starting and coupling working conditions:
when the coupling system is started and loads are increased, in the first stage of starting and load increasing, the valve 2-2 is closed, the valve 2-1 is opened, and saturated steam or wet steam with the dryness greater than 0.9 at the outlet of the nuclear island 1 enters the steam turbine 2 with the basic load to do work and generate power; in the second stage of starting and load increasing, the boiler 11 is started to heat the molten salt for heat storage; in the third stage of starting and load increasing, a parallel coupling operation mode is entered, when the temperature of the molten salt reaches a set required value, the valve 2-1 is still opened, steam for maintaining the basic load of the nuclear island still enters the steam turbine 2 with the basic load, meanwhile, the valve 2-2 is also opened, the amount of feed water entering the nuclear island 1 and the amount of steam coming out of the nuclear island 1 are increased, the steam except for the steam for maintaining the basic load of the nuclear island enters the molten salt-superheated steam heat exchanger 4 through the valve 2-2 and is further heated to be superheated steam, and the superheated steam enters the high-pressure cylinder 15 of the steam turbine for coupling to do work.
2. Boiler split working condition:
the operation of the nuclear island relates to the problem of nuclear safety, and the prior art does not solve the problem of how to adapt a coupling system to quickly adjust the load when the boiler is suddenly shut down. In the invention, when the boiler 11 breaks down for a short time, the system enters a primary decoupling operation mode, a primary loop of the boiler is cut off, only a secondary loop of the boiler is operated, the heating requirements of steam coming out of the nuclear island 1 and steam exhausted by a high-pressure cylinder of a coupling steam turbine coming out of a high-pressure cylinder 15 of the coupling steam turbine are met by adopting heat storage in a molten salt tank, the load of the whole coupling system can be gradually reduced by controlling the flow of hot molten salt, the load impact of sudden load reduction on the nuclear island 1 is avoided, and the safety of the operation of the nuclear reactor 1-1 under the working condition of sudden disconnection of the boiler 11 is ensured. The technical scheme of the invention adopts the molten salt tank for heat storage, the technology is mature and reliable, and the molten salt flow can be adjusted by the molten salt pump, so that the adjustment of the superheated steam temperature and the reheated steam temperature is simpler and more accurate.
3. Molten salt system split conditions:
when the fused salt system cannot be used due to an accident (such as a fused salt pump failure) and the like, the system enters a secondary decoupling operation mode, a secondary loop of the boiler is quickly cut off, the valve 2-2 is closed, the valve 2-1 is opened, and steam from the nuclear island 1 only enters the steam turbine 2 with the basic load. In order to ensure that the molten salt is maintained in a liquid state and is not solidified, the requirement of the molten salt heat preservation is met through electric tracing, electric energy consumed by the electric tracing is preferentially provided by the steam turbine 2 with the basic load to drive the first generator 3 to generate electricity, and reverse electricity of a power grid is only used as a standby power.
Simultaneously, a boiler primary circuit is gradually cut: the second loop of the boiler can be stopped quickly, and because the thermal inertia of the boiler during load lifting is large, the first loop of the boiler can still continue to operate in a short time, the load is reduced step by step, heat generated in the process is stored in molten salt through the gas-molten salt heat exchanger 9 for heat storage, and sufficient and safe operation adjustment time is provided for the boiler to dump load or stop following the nuclear island in the heat storage process.
4. The nuclear island accident disconnection working condition is as follows:
the prior art does not have the heat accumulation function, does not solve when the sudden failure load shedding of nuclear island or shut down, the problem of how to adjust the load of boiler. In the invention, when the nuclear island 1 suddenly breaks down to throw load or stop, the primary loop of the boiler can still continue to operate in a short time, the load is gradually reduced, heat generated in the process is stored in molten salt through the gas-molten salt heat exchanger 9 to store heat, and the heat storage process provides sufficient and safe operation adjustment time for the boiler to throw load or stop following the nuclear island.
Example four
In one or more embodiments, a method of nuclear energy coupled chemical energy power generation based on a two-circuit boiler is disclosed, comprising: the boiler 11 converts chemical energy into heat energy by burning chemical energy fuel (such as fossil fuel such as coal, oil, and natural gas, and renewable energy fuel such as biomass and garbage), and transfers the heat energy out by using special gas (such as helium and supercritical carbon dioxide), low-temperature gas (such as helium and supercritical carbon dioxide) is provided at an inlet of the boiler 11, high-temperature gas (such as helium and supercritical carbon dioxide) is provided at an outlet of the boiler 11, and circulating power of the gas is provided by a gas circulating fan 10 at the inlet of the boiler 11.
The feedwater enters the nuclear island 1 after being heated in the high-pressure heater 14, is heated and evaporated in the nuclear island 1 to become saturated steam or wet steam with the dryness being more than 0.9, one part of the saturated steam or the wet steam with the dryness being more than 0.9 enters the turbine with the basic load 2 to do work, and the other part of the saturated steam or the wet steam enters the fused salt-superheated steam heat exchanger 4;
cold molten salt is pumped into a gas-molten salt heat exchanger 9 from a cold molten salt tank 7 through a cold molten salt pump 8, the cold molten salt is heated by high-temperature gas to form hot molten salt, and the hot molten salt enters a hot molten salt tank 6. Hot molten salt in the hot molten salt tank 6 is pumped into the molten salt-superheated steam heat exchanger 4 through superheated steam by using a hot molten salt pump 12 to heat steam coming out of the nuclear island 1, and then cold molten salt cooled by the steam coming out of the nuclear island 1 enters the cold molten salt tank 7; the other part of the hot molten salt in the hot molten salt tank 6 is pumped into the molten salt-reheat steam heat exchanger 5 through the hot molten salt pump 13 for reheat steam to heat the exhaust steam of the high-pressure coupling turbine cylinder 15 which is discharged from the high-pressure coupling turbine cylinder 15, and then the cold molten salt cooled by the exhaust steam of the high-pressure coupling turbine cylinder 15 which is discharged from the high-pressure coupling turbine cylinder 15 enters the cold molten salt tank 7. The exhaust steam of the high-pressure cylinder 15 of the coupling steam turbine enters the low-pressure cylinder 17 of the coupling steam turbine to do work, and the high-pressure cylinder and the low-pressure cylinder of the coupling steam turbine do work to drive the second generator 18 to generate electricity.
Compared with the prior art, the invention can better embody the advantages of the invention that the invention can flexibly and safely adapt to a plurality of typical variable working conditions:
1. starting and coupling working conditions:
when the coupling system is started and loads are increased, in the first stage of starting and load increasing, the valve 2-2 is closed, the valve 2-1 is opened, and saturated steam or wet steam with the dryness greater than 0.9 at the outlet of the nuclear island 1 enters the steam turbine 2 with the basic load to do work and generate power; in the second stage of starting and load increasing, the boiler 11 is started to heat the molten salt for heat storage; in the third stage of starting and load increasing, a parallel coupling operation mode is entered, when the temperature of the molten salt reaches a set required value, the valve 2-1 is still opened, steam for maintaining the basic load of the nuclear island still enters the steam turbine 2 with the basic load, meanwhile, the valve 2-2 is also opened, the amount of feed water entering the nuclear island 1 and the amount of steam coming out of the nuclear island 1 are increased, the steam except for the steam for maintaining the basic load of the nuclear island enters the molten salt-superheated steam heat exchanger 4 through the valve 2-2 and is further heated to be superheated steam, and the superheated steam enters the high-pressure cylinder 15 of the steam turbine for coupling to do work.
2. Boiler split working condition:
the operation of the nuclear island relates to the problem of nuclear safety, and the prior art does not solve the problem of how to adapt a coupling system to quickly adjust the load when the boiler is suddenly shut down. In the invention, when the boiler 11 breaks down for a short time, the system enters a primary decoupling operation mode, a primary loop of the boiler is cut off, only a secondary loop of the boiler is operated, the heating requirements of steam coming out of the nuclear island 1 and steam exhausted by a high-pressure cylinder of a coupling steam turbine coming out of a high-pressure cylinder 15 of the coupling steam turbine are met by adopting heat storage in a molten salt tank, the load of the whole coupling system can be gradually reduced by controlling the flow of hot molten salt, the load impact of sudden load reduction on the nuclear island 1 is avoided, and the safety of the operation of the nuclear reactor 1-1 under the working condition of sudden disconnection of the boiler 11 is ensured. The technical scheme of the invention adopts the molten salt tank for heat storage, the technology is mature and reliable, and the molten salt flow can be adjusted by the molten salt pump, so that the adjustment of the superheated steam temperature and the reheated steam temperature is simpler and more accurate.
3. Molten salt system split conditions:
when the fused salt system cannot be used due to an accident (such as a fused salt pump failure) and the like, the system enters a secondary decoupling operation mode, a secondary loop of the boiler is quickly cut off, the valve 2-2 is closed, the valve 2-1 is opened, and steam from the nuclear island 1 only enters the steam turbine 2 with the basic load. In order to ensure that the molten salt is maintained in a liquid state and is not solidified, the requirement of the molten salt heat preservation is met through electric tracing, electric energy consumed by the electric tracing is preferentially provided by the steam turbine 2 with the basic load to drive the first generator 3 to generate electricity, and reverse electricity of a power grid is only used as a standby power.
Simultaneously, a boiler primary circuit is gradually cut: the second loop of the boiler can be stopped quickly, and because the thermal inertia of the boiler during load lifting is large, the first loop of the boiler can still continue to operate in a short time, the load is reduced step by step, heat generated in the process is stored in molten salt through the gas-molten salt heat exchanger 9 for heat storage, and sufficient and safe operation adjustment time is provided for the boiler 11 to carry out load shedding or stop following the nuclear island 1 in the heat storage process.
4. The nuclear island accident disconnection working condition is as follows:
the prior art does not have the heat accumulation function, does not solve when the sudden failure load shedding of nuclear island or shut down, the problem of how to adjust the load of boiler. In the invention, when the nuclear island 1 suddenly breaks down to throw load or stop, the primary loop of the boiler can still continue to operate in a short time, the load is gradually reduced, heat generated in the process is stored in molten salt through the gas-molten salt heat exchanger 9 to store heat, and the heat storage process provides sufficient and safe operation adjustment time for the boiler to throw load or stop following the nuclear island.
Although the embodiments of the present invention have been described with reference to the accompanying drawings, it is not intended to limit the scope of the present invention, and it should be understood by those skilled in the art that various modifications and variations can be made without inventive efforts by those skilled in the art based on the technical solution of the present invention.
Claims (10)
1. A nuclear energy coupling chemical energy power generation system based on a two-loop boiler is characterized by comprising: the system comprises a cooling tower, a condenser, a deaerator, a high-pressure heater, a nuclear island, a boiler, a gas-molten salt heat exchanger, a hot molten salt tank, a cold molten salt tank, a molten salt-superheated steam heat exchanger, a turbine with basic load and a turbine for coupling;
the boiler is connected with the gas-molten salt heat exchanger through a gas circulating fan to form a boiler primary loop; the gas-molten salt heat exchanger is respectively connected with the cold molten salt tank and the hot molten salt tank, and the cold molten salt tank and the hot molten salt tank are respectively connected with the molten salt-superheated steam heat exchanger to form a second boiler loop;
the steam outlet of the nuclear island is divided into two paths, wherein one path is connected with a basic load steam turbine, and the other path is connected with a molten salt-superheated steam heat exchanger; the steam outlet of the molten salt-superheated steam heat exchanger is connected with a coupling steam turbine; the turbine with the basic load drives a first generator to generate power, and the turbine for coupling drives a second generator to generate power;
the exhaust steam of the coupling steam turbine is cooled into condensed water through a condenser, the condensed water enters a high-pressure heater for heating after passing through a deaerator, and the heated feed water enters a nuclear island; the steam outlet of the molten salt-superheated steam heat exchanger is connected with the steam inlet of a high-pressure cylinder of a coupling steam turbine, and the steam outlet of the high-pressure cylinder of the coupling steam turbine is connected with the molten salt-reheated steam heat exchanger; the molten salt-reheat steam heat exchanger is respectively connected with the cold molten salt tank and the hot molten salt tank.
2. The two-circuit boiler based nuclear coupled chemical energy power generation system of claim 1, wherein said coupling steam turbine comprises: a high-pressure cylinder of the coupling steam turbine, a medium-pressure cylinder of the coupling steam turbine and a low-pressure cylinder of the coupling steam turbine; and a steam outlet of the molten salt-reheat steam heat exchanger is connected with a steam inlet of a coupling steam turbine intermediate pressure cylinder, a steam outlet of the coupling steam turbine intermediate pressure cylinder is connected with a steam inlet of a coupling steam turbine low pressure cylinder, and the coupling steam turbine low pressure cylinder is connected with a second generator.
3. The two-circuit boiler based nuclear energy coupled chemical energy power generation system of claim 2, wherein said hot melt salt tank is connected to the molten salt-superheated steam heat exchanger through a hot melt salt pump for superheated steam, and said hot melt salt tank is connected to the molten salt-reheat steam heat exchanger through a hot melt salt pump for reheat steam.
4. The two-circuit boiler based nuclear coupled chemical energy power generation system of claim 1, wherein said coupling steam turbine comprises: the high-pressure turbine cylinder for coupling and the low-pressure turbine cylinder for coupling are respectively connected with the second generator, the steam outlet of the fused salt-superheated steam heat exchanger is connected with the steam inlet of the high-pressure turbine cylinder for coupling, the steam outlet of the high-pressure turbine cylinder for coupling is connected with the steam inlet of the low-pressure turbine cylinder for coupling, and the low-pressure turbine cylinder for coupling is connected with the second generator.
5. The two-circuit boiler based nuclear-energy-coupled chemical energy power generation system of claim 4, wherein said hot-melt salt tank is connected to the molten salt-superheated steam heat exchanger by a hot-melt salt pump for superheated steam.
6. The system for nuclear coupled chemical energy power generation based on a two-circuit boiler as claimed in claim 2 or 4, characterized in that valves are respectively arranged on the connection pipelines of the nuclear island and the molten salt-superheated steam heat exchanger and the steam turbine with basic load.
7. A nuclear energy coupling chemical energy power generation method based on a two-loop boiler is characterized by comprising the following steps:
the boiler provides high-temperature gas for the gas-molten salt heat exchanger, cold molten salt enters the gas-molten salt heat exchanger from the cold molten salt tank, the cold molten salt is heated by the high-temperature gas to form hot molten salt, and the hot molten salt enters the hot molten salt tank;
the feedwater is heated and then enters a nuclear island, the feedwater is heated and evaporated in the nuclear island to become saturated steam or wet steam, one part of the saturated steam or the wet steam enters a steam turbine with basic load to do work, and the other part of the saturated steam or the wet steam enters a molten salt-superheated steam heat exchanger;
after entering a molten salt-superheated steam heat exchanger to heat saturated steam or wet steam coming out of the nuclear island, the hot molten salt in the hot molten salt tank is cooled into cold molten salt and enters a cold molten salt tank; saturated steam or wet steam entering the molten salt-superheated steam heat exchanger is heated by hot molten salt to become superheated steam, and the superheated steam enters the coupling steam turbine to do work.
8. A method of generating power from nuclear coupled chemical energy based on a two-circuit boiler as claimed in claim 7 wherein said coupling turbine comprises: a high-pressure cylinder of the coupling steam turbine, a medium-pressure cylinder of the coupling steam turbine and a low-pressure cylinder of the coupling steam turbine; the superheated steam enters a high-pressure cylinder of the coupling steam turbine, exhaust steam of the high-pressure cylinder of the coupling steam turbine is heated by hot molten salt to become reheated steam, the reheated steam enters a medium-pressure cylinder of the coupling steam turbine to do work, and exhaust steam of the medium-pressure cylinder of the coupling steam turbine enters a low-pressure cylinder of the coupling steam turbine to do work to drive a generator to generate power.
9. A method of generating power from nuclear coupled chemical energy based on a two-circuit boiler as claimed in claim 7 wherein said coupling turbine comprises: a high-pressure cylinder of the coupling steam turbine and a low-pressure cylinder of the coupling steam turbine; the superheated steam enters a high-pressure cylinder of a coupling steam turbine to do work, and the exhaust steam of the high-pressure cylinder of the coupling steam turbine enters a low-pressure cylinder of the coupling steam turbine to do work to drive a generator to generate power.
10. The method for generating electricity by coupling nuclear energy with chemical energy based on the two-loop boiler as claimed in claim 7, wherein in the first stage of starting and load rising, the saturated steam or wet steam at the outlet of the nuclear island only enters the steam turbine with basic load to do work and generate electricity; in the second stage of starting and load increasing, the boiler is started and heats the molten salt for heat storage; in the third stage of starting and load increasing, a parallel coupling operation mode is entered, when the temperature of the molten salt reaches a set required value, steam for maintaining the basic load of the nuclear island still enters a steam turbine with the basic load, simultaneously, the amount of water supply entering the nuclear island and the amount of steam coming out of the nuclear island are increased, the steam except for the steam for maintaining the basic load of the nuclear island enters a molten salt-superheated steam heat exchanger to be further heated into superheated steam, and the superheated steam enters a coupling steam turbine to do work;
when the fault time of the boiler is less than a set threshold value, the system enters a primary decoupling operation mode, a primary loop of the boiler is cut off, only a secondary loop of the boiler is operated, and the heat storage in the hot-melt salt tank is adopted to meet the steam heating requirement;
when the molten salt system cannot be used, the system enters a secondary decoupling operation mode, a primary loop and a secondary loop of the boiler are cut off, and steam coming out of the nuclear island only enters a steam turbine with basic load and does not enter a molten salt-superheated steam heat exchanger;
when the nuclear island suddenly breaks down to throw load or shut down, the boiler secondary circuit stops operating rapidly, because the thermal inertia when the boiler goes up and down the load is great, the boiler primary circuit still continues to operate in the short time, reduces the load step by step to store the heat that produces in this process in the fused salt through gas-fused salt heat exchanger and accumulate heat, the process of heat accumulation provides sufficient and safe operation adjustment time for the boiler to throw load or shut down along with the nuclear island.
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| CN112065519A (en) * | 2020-09-11 | 2020-12-11 | 上海康恒环境股份有限公司 | High-parameter waste incineration power generation system with dehumidification function |
| CN112610292A (en) * | 2020-12-11 | 2021-04-06 | 北京前沿动力科技股份有限公司 | Deep peak regulation power generation system |
| CN113217986B (en) * | 2021-04-30 | 2022-06-10 | 董荣华 | Chemical heat accumulator and heating system adopting same |
| CN114263509A (en) * | 2021-12-24 | 2022-04-01 | 中煤科工集团南京设计研究院有限公司 | Turbine reheating system based on molten salt heating |
| CN114776408B (en) * | 2022-04-24 | 2023-10-17 | 南京航空航天大学 | Liquid metal nuclear power energy storage circulating system and operation method |
| CN115807700B (en) * | 2022-11-30 | 2024-10-29 | 西安交通大学 | A nuclear-storage power generation system and its working method by throttling and frequency modulation through low-pressure steam extraction |
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| CN106677844B (en) * | 2015-11-09 | 2019-02-22 | 国家电投集团科学技术研究院有限公司 | Series-parallel coupling power generation system of nuclear energy and conventional energy |
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