Waste heat industrial steam supply system based on nuclear reactor and fused salt energy storage power generation

Abstract

The invention discloses a waste heat industrial steam supply system based on a nuclear reactor and fused salt energy storage power generation, and the system comprises a fused salt energy storage device which comprises a circulating heat storage working medium which is fluoride fused salt; the nuclear energy side power generation device comprises a fourth-generation nuclear reactor, a first power generation device, a second power generation device and a pretreatment backflow pipeline, supercritical carbon dioxide serves as a heat absorption medium of the fourth-generation nuclear reactor, and the output end of the fourth-generation nuclear reactor is divided into a main flow path and a branch flow path. The main flow path conveys supercritical carbon dioxide to the first power generation device for acting and power generation, and the branch flow path introduces the supercritical carbon dioxide into the fused salt energy storage device for heat exchange; the waste heat recovery steam supply device comprises an industrial water inlet pipeline and a pretreatment heat exchange pipeline. Therefore, the temperature upper limit bottleneck that steam serves as a heating medium traditionally can be broken through, the requirement for waste heat recovery is met, meanwhile, the medium obtained after heating fused salt energy storage can be effectively recovered and reused, and resource waste is remarkably reduced.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of waste heat recycling, and particularly relates to a waste heat industrial steam supply system based on nuclear reactors and molten salt energy storage power generation. BACKGROUND

[0002] In the field of power generation system technology, in order to achieve the goal of efficient use and stable supply of energy, various technical solutions focus on the collaborative operation of the nuclear power side and the molten salt energy storage side. On the nuclear energy side, mainly relying on nuclear reaction steam turbine units, the steam generated by the nuclear reactor is branched to provide a heat source for the molten salt heat storage side. When the power generation demand is high, the high-temperature molten salt exchanges heat with part of the backwater or backflow steam discharged from the turbine, thereby generating high-temperature steam, which is then transported to another turbine for power generation. In addition, there is a scheme of coupling pressurized water reactor nuclear power and molten salt heat storage technology, in which the nuclear power side adopts a steam work cycle, and the main steam and high-pressure cylinder exhaust steam of the turbine are used to provide heat for the molten salt heat storage side; the molten salt heat storage side supplies heat to the outside through the machine-side thermal system, thereby realizing the energy supply of the heat storage side.

[0003] However, in the technical solution of the collaborative operation of the nuclear power side and the molten salt energy storage side, the current processing method for the medium after the nuclear reactor branched heating of the molten salt energy storage is usually direct discharge or transportation back to the nuclear reactor, but this process does not fully consider the recycling of waste heat, thereby causing waste of resources. On the other hand, even if some solutions attempt to recycle waste heat from steam, since the upper limit temperature of steam is generally around 550-600℃, after heat exchange with the molten salt energy storage system, the steam flows into the turbine unit to do work, and the temperature of the steam after flowing out has been reduced twice, which is not high enough for waste heat recycling. SUMMARY

[0004] The present application aims to at least partially solve one of the technical problems in the related art.

[0005] To this end, one object of the present application is to provide a waste heat industrial steam supply system based on nuclear reactors and molten salt energy storage power generation, which can break through the temperature upper limit bottleneck of traditional steam as a heating medium, meet the requirements of waste heat recycling, and effectively recycle and reuse the medium after heating the molten salt energy storage, thereby significantly reducing resource waste and improving economic benefits.

[0006] To achieve the above object, the application provides a waste heat industrial steam supply system based on a nuclear reactor and a molten salt energy storage power generation, which comprises a molten salt energy storage device, a nuclear energy side power generation device and a waste heat recovery steam supply device.

[0007] The waste heat industrial steam supply system based on a nuclear reactor and molten salt energy storage power generation of the application selects a fourth generation nuclear reactor and adopts supercritical carbon dioxide as a heat absorption medium, successfully realizing a Brayton cycle based on the fourth generation nuclear reactor. The temperature of the supercritical carbon dioxide is raised to 950 DEG C in this design, which is significantly higher than the temperature upper limit of the traditional nuclear reactor using steam as a circulating medium. Therefore, even after heat exchange with the molten salt energy storage device and completing work and power generation in the second power generation device, the temperature of the supercritical carbon dioxide can still be maintained at about 250 DEG C. The industrial water only needs to be heated to about 200 DEG C to meet the requirements, so that the industrial application requirements can be met. The industrial water flows into the cooler through the industrial water inlet pipeline 31, and the industrial water and the supercritical carbon dioxide flowing through the cooler are heat exchanged in the cooler. The temperature of the supercritical carbon dioxide flowing through the cooler is about 150 DEG C, and the temperature of the industrial water in the industrial water inlet pipeline is about 35 DEG C. The industrial water and the supercritical carbon dioxide are heat exchanged in the cooler. The cooler inlet is used as the industrial water inlet, and the heat released by the supercritical carbon dioxide flowing back in the cooler is reasonably utilized. The first heated industrial water flows into the pretreatment heat exchange pipeline and is heat exchanged with the supercritical carbon dioxide after power generation in the second power generation device, forming secondary heating. The waste heat of the supercritical carbon dioxide after power generation in the second power generation device is reasonably utilized, and the medium (supercritical carbon dioxide) after heating the molten salt energy storage can be effectively recovered and reused. This design breaks through the limitation of the traditional system that the waste heat after power generation is directly wasted, realizes the cascade utilization of heat energy, significantly reduces resource waste, and improves economic benefits.

[0008] In addition, the waste heat industrial steam supply system based on a nuclear reactor and molten salt energy storage power generation according to the above application can have the following additional technical features: Specifically, the pretreatment heat exchange pipeline comprises a vacuum deaerator, a first heat exchanger and a steam-water separator, wherein The vacuum deaerator is in communication with the cooler and the first heat exchanger, respectively; The steam-water separator and the first heat exchanger are in communication, wherein the steam-water separator is used for steam and liquid separation treatment of the steam-water mixture, the steam outlet end of the steam-water separator is used for outputting the separated steam, and the liquid outlet end of the steam-water separator is in communication with a communication pipeline between the vacuum deaerator and the first heat exchanger, and is used for returning the separated water to the first heat exchanger for continuous circulation heat exchange.

[0009] Specifically, the pretreatment heat exchange pipeline comprises a regenerator, a compressor and the cooler, wherein The regenerator is connected to the first power generation device, the cooler, the compressor and the fourth generation nuclear reactor, and the compressor and the cooler are connected, wherein the supercritical carbon dioxide after the first power generation device generates power flows through the regenerator, the cooler, the compressor, the regenerator and back to the fourth generation nuclear reactor to complete the closed loop flow. The first heat exchanger is connected to the communication pipeline between the regenerator and the cooler, and is used for the supercritical carbon dioxide after the second power generation device generates power to flow through the first heat exchanger and back to the cooler to complete the closed loop flow.

[0010] Specifically, the molten salt energy storage device further comprises a low-temperature molten salt tank, a first conveying pump, a second heat exchanger, a high-temperature molten salt tank, a second conveying pump and a third heat exchanger, wherein, The low-temperature molten salt tank stores the fluoride molten salt, and the low-temperature molten salt tank is connected to the second heat exchanger, and the first conveying pump is arranged on the communication pipeline between the low-temperature molten salt tank and the second heat exchanger. The second heat exchanger is connected to the shunt and the second power generation device. The high-temperature molten salt tank is connected to the second heat exchanger and the third heat exchanger, and the second conveying pump is arranged on the communication pipeline between the high-temperature molten salt tank and the third heat exchanger, wherein the high-temperature molten salt tank is used to store the fluoride molten salt in high-temperature state after heat exchange in the second heat exchanger. The third heat exchanger is connected to the low-temperature molten salt tank.

[0011] Specifically, it further comprises: The energy storage side power generation device comprises an energy storage side pipeline and a third power generation device, wherein one end of the energy storage side pipeline is connected to the third heat exchanger, and the other end of the energy storage side pipeline is connected to the backflow pipeline between the regenerator and the fourth generation nuclear reactor. The third power generation device is connected to the third heat exchanger and the pipeline between the regenerator and the first power generation device, respectively, and the supercritical carbon dioxide in the energy storage side pipeline is used to exchange heat with the fluoride molten salt in high-temperature state after heat storage, and the supercritical carbon dioxide after heat exchange is supplied to the third power generation device to drive the third power generation device to generate power.

[0012] Specifically, the first power generation device, the second power generation device and the third power generation device each comprise a turbine and a generator, wherein, The turbine in the first power generation device is connected to the main flow path and the regenerator, respectively. The turbine in the second power generation device respectively communicates with the first heat exchanger and the second heat exchanger; The turbine in the third power generation device respectively communicates with the third heat exchanger and a pipeline connecting the regenerator and the first power generation device.

[0013] Specifically, the first adjusting valve is arranged on the branch flow path and is between the fourth generation nuclear reactor and the second heat exchanger.

[0014] Specifically, the second adjusting valve is arranged on the energy storage side pipeline and is adjacent to the fourth generation nuclear reactor.

[0015] Specifically, the waste heat recovery steam supply device further comprises a third delivery pump, which is connected in series on the industrial water inlet pipeline.

[0016] Specifically, the waste heat recovery steam supply device further comprises a fourth delivery pump, which is connected in series on the pipeline between the vacuum deaerator and the first heat exchanger. BRIEF DESCRIPTION OF DRAWINGS

[0017] The accompanying drawings, which are incorporated herein and constitute part of the specification, illustrate embodiments consistent with the present application and, together with the description, serve to explain the principles of the application.

[0018] In order to more clearly illustrate the technical solutions in the embodiments of the present application or the prior art, the accompanying drawings needed to be used in the embodiments or prior art description will be briefly introduced. Obviously, those skilled in the art can obtain other drawings from these drawings without any creative effort.

[0019] Figure 1 FIG. 1 is a structural schematic diagram of a waste heat industrial steam supply system based on a nuclear reactor and a molten salt energy storage power generation according to an embodiment of the present application.

[0020] As shown in the figure: 1, molten salt energy storage device; 10, low-temperature molten salt tank; 11, first delivery pump; 12, second heat exchanger; 13, high-temperature molten salt tank; 14, second delivery pump; 15, third heat exchanger; 2, nuclear energy side power generation device; 20, fourth generation nuclear reactor; 21, first power generation device; 22, second power generation device; 23, pretreatment backflow pipeline; 200, main flow path; 201, branch flow path; 210, turbine; 211, generator; 230, regenerator; 231, compressor; 232, cooler; 2010, first adjusting valve; 3. Waste heat recovery steam supply unit; 31. Industrial water inlet pipeline; 32. Pretreatment heat exchange pipeline; 33. Third transfer pump; 34. Fourth transfer pump; 320. Vacuum deaerator; 321. First heat exchanger; 322. Steam-water separator; 3220. Steam port end; 3221. Liquid port end; 4. Energy storage side power generation device; 40. Energy storage side pipeline; 41. Third power generation device; 42. Second regulating valve. Detailed Implementation

[0021] To better understand the above-mentioned objectives, features, and advantages of the present invention, the solutions of the present invention will be further described below. It should be noted that, unless otherwise specified, the embodiments of the present invention and the features thereof can be combined with each other.

[0022] Many specific details are set forth in the following description in order to provide a full understanding of the invention, but the invention may also be practiced in other ways different from those described herein; obviously, the embodiments in the specification are only some embodiments of the invention, and not all embodiments.

[0023] The waste heat industrial steam supply system based on nuclear reactor and molten salt energy storage power generation according to an embodiment of the present invention will be described below with reference to the accompanying drawings.

[0024] like Figure 1 As shown, the waste heat industrial steam supply system based on nuclear reactor and molten salt energy storage power generation in this embodiment of the invention may include: molten salt energy storage device 1, nuclear energy side power generation device 2, and waste heat recovery steam supply device 3.

[0025] The molten salt energy storage device 1 includes a circulating thermal storage medium, which is a fluoride molten salt used for heat storage and exchange. The fluoride molten salt, as the circulating thermal storage medium, can be heated to 900℃, breaking through the traditional temperature limit of molten salt thermal storage (600℃ for nitrates), significantly improving energy storage efficiency. Simultaneously, the outlet temperature of the fourth-generation nuclear reactor 20 can reach 950℃. The fluoride molten salt has high-temperature resistance characteristics, which are highly compatible with the heat output characteristics of the fourth-generation nuclear reactor 20, eliminating the temperature limitations of traditional working fluids. Furthermore, the fluoride molten salt has a higher thermal storage density, nearly doubling the heat storage capacity compared to nitrates.

[0026] The nuclear power generation unit 2 includes a fourth-generation nuclear reactor 20, a first power generation unit 21, a second power generation unit 22, and a pretreatment recirculation pipeline 23. The fourth-generation nuclear reactor 20 uses supercritical carbon dioxide as the heat-absorbing medium.

[0027] The output end of the fourth generation nuclear reactor 20 is divided into a main flow path 200 and a branch flow path 201. The main flow path 200 delivers supercritical carbon dioxide to the first power generation device 21 to generate power, and the supercritical carbon dioxide after work is returned to the fourth generation nuclear reactor 20 through a pretreatment return pipeline 23 containing a cooler 232. The branch flow path 201 introduces supercritical carbon dioxide into the molten salt energy storage device 1 to exchange heat, and the supercritical carbon dioxide after heat exchange is delivered to the second power generation device 22 to generate power.

[0028] It should be noted that the fourth generation nuclear reactor 20 is selected, and supercritical carbon dioxide is used as the heat absorption medium, and the Brayton cycle based on the fourth generation nuclear reactor 20 is successfully realized. This design raises the temperature of supercritical carbon dioxide to 950℃, which is significantly higher than the temperature limit of the traditional nuclear reactor using steam as the circulating medium. Therefore, even after heat exchange with the molten salt energy storage device 1 and completing the work in the second power generation device 22, the temperature of the supercritical carbon dioxide can still be maintained at about 250℃. Industrial water only needs to be heated to about 200℃ to meet the demand, so it can meet the requirements of industrial applications.

[0029] The waste heat recovery and steam supply device 3 includes an industrial water inlet pipeline 31 and a pretreatment heat exchange pipeline 32. The cooler 232 is in communication with the industrial water inlet pipeline 31 and the pretreatment heat exchange pipeline 32, respectively. The industrial water is heated by the cooler 232 in one stage. In terms of industrial steam, the heat dissipated by the cooler 232 is additionally considered. The inlet of the cooler 232 is used as the inlet of the industrial water, and the heat released by the supercritical carbon dioxide in the cooler 232 during backflow is reasonably utilized. This part of the heat is used as the one-stage heating of the industrial water to increase the heating temperature of the industrial water, that is, the industrial water can be increased from the original 35℃ to about 120℃.

[0030] The heated industrial water flows into the pretreatment heat exchange pipeline 32, and the supercritical carbon dioxide after power generation in the second power generation device 22 flows through the pretreatment heat exchange pipeline 32 to perform two-stage heating on the one-stage heated industrial water to form a steam-water mixture. That is, the waste heat of about 250℃ of the supercritical carbon dioxide after power generation in the second power generation device 22 is used to perform two-stage heating on the one-stage heated industrial water through the pretreatment heat exchange pipeline 32, so that the temperature of the industrial water reaches about 200℃, meeting the use requirements.

[0031] The supercritical carbon dioxide after heat exchange with the industrial water is treated by the pretreatment return pipeline 23 and returned to the fourth generation nuclear reactor 20. The steam-water mixture is subjected to steam-water separation treatment in the pretreatment heat exchange pipeline 32. The separated steam is output as industrial steam, and the separated water returns to the pretreatment heat exchange pipeline 32 for cyclic heat exchange, which can reduce the waste of resources.

[0032] It should be noted that the separated steam is output as industrial steam, which can be directed to the purchaser for use, wherein the purchaser can be a printing and dyeing plant, a paper mill, a tire factory, etc.

[0033] Specifically, the supercritical carbon dioxide is heated to about 950℃ in the fourth generation nuclear reactor 20, and is divided into a main flow path 200 and a branch flow path 201, wherein the main flow path 200 delivers the supercritical carbon dioxide to the first power generation device 21 for work and power generation, and the supercritical carbon dioxide after work is returned to the fourth generation nuclear reactor 20 through a pretreatment return pipeline 23 for treatment to complete the closed loop of the main flow path 200.

[0034] The branch flow path 201 introduces the supercritical carbon dioxide at 950℃ into the molten salt energy storage device 1 for heat exchange, and the supercritical carbon dioxide after heat exchange is about 450℃, and is delivered to the second power generation device 22 for driving the second power generation device 22 to work and generate power. The supercritical carbon dioxide after work is about 250℃ after consuming heat, and enters the pretreatment heat exchange pipeline 32 for heat exchange.

[0035] The industrial water flows into the cooler 232 through the industrial water inlet pipeline 31, and the industrial water and the supercritical carbon dioxide flowing through the cooler 232 are heat exchanged in the cooler 232, wherein the temperature of the supercritical carbon dioxide flowing through the cooler 232 is about 150℃, and the temperature of the industrial water in the industrial water inlet pipeline 31 is about 35℃. The industrial water and the supercritical carbon dioxide are heat exchanged in the cooler 232, on the one hand, the waste heat of the supercritical carbon dioxide can be used to heat the industrial water to about 120℃, on the other hand, the industrial water can also be used to cool the supercritical carbon dioxide, which is a reasonable recycling of resources and greatly improves the economic benefit.

[0036] The first heated industrial water flows into the pretreatment heat exchange pipeline 32, and is heat exchanged with the supercritical carbon dioxide after power generation in the second power generation device 22 to form secondary heating, which reasonably utilizes the waste heat of the supercritical carbon dioxide after power generation in the second power generation device 22.

[0037] The supercritical carbon dioxide after power generation in the second power generation device 22 still retains about 250℃ of waste heat, which is used for secondary heating of the industrial water through the pretreatment heat exchange pipeline 32, and the low-grade heat energy that would have been wasted is converted into effective energy. This design breaks through the limitation of "waste heat directly wasted after power generation" in traditional systems, realizes the cascade utilization of heat energy, and greatly improves the comprehensive energy efficiency of the system.

[0038] Secondly, the industrial water needs to be heated to about 200℃, and the primary heating can quickly raise the water temperature to close to the target temperature, and then the secondary temperature compensation is performed through the supercritical carbon dioxide waste heat of 250℃, and finally 200℃ is reached. This staged heating method avoids the energy waste of "direct heating of low-temperature demand by high-temperature heat source", and realizes the cascade utilization of heat energy.

[0039] In addition, through waste heat heating, the system not only realizes power generation (first power generation device 21, second power generation device 22), but also synchronously provides industrial heat, forming a "cogeneration" mode. This multi-cogeneration mode improves the load rate and utilization rate of the fourth generation nuclear reactor 20, and unit nuclear fuel can output electric energy and heat energy at the same time, which significantly improves the economy and investment return rate of the project compared with the single power generation mode.

[0040] Further, as shown in Figure 1 , the pretreatment heat exchange pipeline 32 includes a vacuum deaerator 320, a first heat exchanger 321, and a steam-water separator 322.

[0041] The vacuum deaerator 320 is in communication with the cooler 232 and the first heat exchanger 321, and the steam-water separator 322 is in communication with the first heat exchanger 321, wherein the steam-water separator 322 is used for steam-liquid separation treatment of the steam-water mixture, the steam outlet end 3220 of the steam-water separator 322 is used for outputting the separated steam, and the liquid outlet end 3221 of the steam-water separator 322 is in communication with the communication pipeline between the vacuum deaerator 320 and the first heat exchanger 321, and is used for returning the separated water to the first heat exchanger 321 for continuous circulation heat exchange.

[0042] In the above scheme, the industrial water first flows through the cooler 232 for primary heating treatment, and then is introduced into the vacuum deaerator 320. The vacuum deaerator 320 effectively removes dissolved oxygen in the industrial water. After the deoxygenation step is completed, the industrial water enters the first heat exchanger 321, where it exchanges heat with the supercritical carbon dioxide flowing through the first heat exchanger 321, thereby forming a steam-water mixture. Next, the steam-water separator 322 separates the steam-water mixture flowing out of the first heat exchanger 321, the separated water is returned to the first heat exchanger 321 to continue participating in the circulation heat exchange process, and the separated steam is used for external delivery.

[0043] In an embodiment of the present application, as shown in Figure 1 , the pretreatment return pipeline 23 includes a regenerator 230, a compressor 231, and a cooler 232.

[0044] The regenerator 230 is connected with the first power generation device 21, the cooler 232, the compressor 231 and the fourth generation nuclear reactor 20 respectively, and the compressor 231 and the cooler 232 are connected, wherein the supercritical carbon dioxide after power generation of the first power generation device 21 flows through the regenerator 230, the cooler 232, the compressor 231 and the regenerator 230 in turn and returns to the fourth generation nuclear reactor 20, thereby completing the closed loop flow.

[0045] The first heat exchanger 321 is connected with the connecting pipeline between the regenerator 230 and the cooler 232, and is used for making the supercritical carbon dioxide after power generation of the second power generation device 22 flow through the first heat exchanger 321 and return to the cooler 232, thereby completing the closed loop flow.

[0046] In the above scheme, the supercritical carbon dioxide flowing out of the first power generation device 21 has a temperature of about 450 DEG C, and in view of the high temperature condition, in order to reduce the heat loss, the supercritical carbon dioxide needs to flow into the regenerator 230 first to release heat, and then flows into the cooler 232 to complete the condensation treatment after the temperature is adjusted to a suitable range, and finally flows into the regenerator 230 through the compressor 231 to absorb heat and then flows into the fourth generation nuclear reactor 20.

[0047] The supercritical carbon dioxide flowing out of the second power generation device 22 has a temperature of about 150 DEG C, because it has been heat exchanged by the second heat exchanger 12, and releases part of the energy in the driving process and after heat exchange with industrial water. Based on the low temperature, the supercritical carbon dioxide does not need to flow into the regenerator 230 first to release heat, and can be directly transported to the cooler 232 to complete the condensation treatment, and then flows into the fourth generation nuclear reactor 20 through the compressor 231 and the regenerator 230, thereby forming the closed loop flow.

[0048] In one embodiment of the present application, as shown in Figure 1 The molten salt energy storage device 1 further comprises a low-temperature molten salt tank 10, a first conveying pump 11, a second heat exchanger 12, a high-temperature molten salt tank 13, a second conveying pump 14 and a third heat exchanger 15.

[0049] The low-temperature molten salt tank 10 stores fluoride molten salt, and the low-temperature molten salt tank 10 is connected with the second heat exchanger 12, and the first conveying pump 11 is arranged on the connecting pipeline between the low-temperature molten salt tank 10 and the second heat exchanger 12.

[0050] The second heat exchanger 12 is connected with the shunt 201 and the second power generation device 22, the high-temperature molten salt tank 13 is connected with the second heat exchanger 12 and the third heat exchanger 15 respectively, and the second conveying pump 14 is arranged on the connecting pipeline between the high-temperature molten salt tank 13 and the third heat exchanger 15, wherein the high-temperature molten salt tank 13 is used for storing the high-temperature fluoride molten salt after heat exchange of the second heat exchanger 12, and the third heat exchanger 15 is connected with the low-temperature molten salt tank 10.

[0051] It should be noted that the first delivery pump 11 is used to deliver fluoride molten salt in a low temperature state, and the second delivery pump 14 is used to deliver fluoride molten salt in a high temperature heat storage state, so in the selection of the delivery pump, the first delivery pump 11 can be selected as a low temperature molten salt pump, and the second delivery pump 14 can be selected as a high temperature molten salt pump.

[0052] Specifically, the fluoride molten salt stored in the low temperature molten salt tank 10 can be extracted by controlling the first delivery pump 11 and delivered to the second heat exchanger 12 to exchange heat with the high temperature supercritical carbon dioxide flowing in the branch path 201, and the fluoride molten salt that absorbs and stores heat is transferred to the high temperature molten salt tank 13 for storage. At this time, the temperature of the fluoride molten salt in the high temperature molten salt tank 13 is about 900℃, and the high temperature molten salt tank 13 is a special container for storing high temperature molten salt. The heat preservation layer outside the tank body reduces heat loss and maintains the temperature of the molten salt, so the fluoride molten salt in the high temperature molten salt tank 13 can ensure that the stored heat meets the use requirements for a long time.

[0053] If it is needed to use according to the actual situation, the fluoride molten salt in the high temperature molten salt tank 13 can be extracted by controlling the second delivery pump 14 and delivered to the third heat exchanger 15 to heat the medium (supercritical carbon dioxide in the energy storage side power generation device 4) flowing in the third heat exchanger 15, and the fluoride molten salt after heat exchange flowing out of the third heat exchanger 15 is stored in the low temperature molten salt tank 10 to form a closed loop circulation.

[0054] In an embodiment of the present application, as shown in Figure 1 The waste heat industrial steam supply system based on a nuclear reactor and a molten salt energy storage power generation of the embodiment of the present application further comprises: an energy storage side power generation device 4, which comprises an energy storage side pipeline 40 and a third power generation device 41. The energy storage side pipeline 40 is connected to the third heat exchanger 15 at one end and connected to the backflow pipeline between the back heat exchanger 230 and the fourth generation nuclear reactor 20 at the other end. The third power generation device 41 is connected to the third heat exchanger 15 and the pipeline between the back heat exchanger 230 and the first power generation device 21, respectively. The supercritical carbon dioxide in the energy storage side pipeline 40 is used to exchange heat with the fluoride molten salt in a high temperature state after completing heat storage. The supercritical carbon dioxide after heat exchange is supplied to the third power generation device 41 to drive the third power generation device 41 to generate power.

[0055] In the above scheme, by designing the energy storage side power generation device 4, the heat energy stored in the molten salt is reasonably utilized, the high-efficiency power generation capability of the supercritical carbon dioxide Brayton cycle is combined with the flexible peak shaving characteristics of the molten salt energy storage device 1, the flexibility of the overall nuclear power system is increased, for example, when the energy storage side power generation device 4 needs to be started according to the electricity demand, the fluoride molten salt in the high-temperature molten salt tank 13 is extracted by the second delivery pump 14 and delivered to the third heat exchanger 15 to heat the supercritical carbon dioxide in the energy storage side pipeline 40, so that the supercritical carbon dioxide is heated to about 850 DEG C, and is supplied into the third power generation device 41 to do work and generate power.

[0056] At the same time, the energy storage side power generation device 4 is partially coupled with the nuclear energy side power generation device 2, that is, the energy storage side power generation device 4 shares the pre-treatment return pipeline 23 in the nuclear energy side power generation device 2, and under the condition that the thermodynamic parameters do not conflict, the system cost is saved to a certain extent.

[0057] In addition, the supercritical carbon dioxide heated by the regenerator 230 flows into the fourth-generation nuclear reactor 20 in a large part, and flows into the third heat exchanger 15 in another part to be heated by the fluoride molten salt. At the same time, when the fourth-generation nuclear reactor 20 needs to be overhauled, the heat energy delivery function can be completely taken over by adjusting the split ratio. This cross-backup mechanism reduces the unplanned downtime, significantly improves the availability of the system, and ensures the power generation demand.

[0058] In an embodiment of the present application, as shown in Figure 1 The first power generation device 21, the second power generation device 22 and the third power generation device 41 each include a turbine 210 and a generator 211, the turbine 210 is connected with the generator 211, and the turbine 210 and the generator 211 can be connected through a shaft coupling.

[0059] The turbine 210 in the first power generation device 21 is in communication with the main flow path 200 and the regenerator 230 respectively; the turbine 210 in the second power generation device 22 is in communication with the first heat exchanger 321 and the second heat exchanger 12 respectively; and the turbine 210 in the third power generation device 41 is in communication with the third heat exchanger 15 and the pipeline connecting the regenerator 230 and the first power generation device 21 respectively.

[0060] Specifically, the high-temperature and high-pressure supercritical carbon dioxide enters the turbine 210, the supercritical carbon dioxide expands to do work, pushes the turbine 210 blades to rotate, converts the heat energy into the rotating mechanical energy of the turbine 210, the turbine 210 operates to drive the generator 211 rotor to rotate, cuts the magnetic induction lines in the magnetic field to generate induced electromotive force, and finally outputs electric energy, and the supercritical carbon dioxide after doing work is discharged.

[0061] In an embodiment of the present application, as shown in Figure 1As shown in the figure, the first regulating valve 2010 is arranged on the shunt path 201 and between the fourth-generation nuclear reactor 20 and the second heat exchanger 12.

[0062] In the above scheme, the flow in the shunt path 201 can be regulated or closed by the first regulating valve 2010, and by regulating the supercritical carbon dioxide flow in the shunt path 201, the main and secondary power generation power ratio can be quickly adjusted. For example, when the demand of the power grid decreases, the flow of the shunt path 201 is increased, and more heat is stored; when the demand increases, the flow of the shunt path 201 is reduced, and the power generation output on the main flow path 200 is preferentially ensured to meet the demand of the power grid.

[0063] In an embodiment of the present application, as shown in the figure, Figure 1 The second regulating valve 42 is arranged on the energy storage side pipeline 40 and near the fourth-generation nuclear reactor 20.

[0064] In the above scheme, by adjusting the opening of the second regulating valve 42, the supercritical carbon dioxide flow into the energy storage side power generation device 4 can be accurately controlled, and the ratio of the energy storage side power generation power to the nuclear energy side power generation power can be adjusted.

[0065] In an embodiment of the present application, as shown in the figure, Figure 1 The waste heat recovery steam supply device 3 further comprises a third delivery pump 33 connected in series on the industrial water inlet pipeline 31.

[0066] Wherein, when the industrial water enters the cooler 232 from the external pipe network, the pressure may be insufficient due to pipeline resistance or long-distance transportation, and the third delivery pump 33 is arranged to pressurize to ensure that the industrial water flows stably into the cooler 232, avoiding the influence of flow fluctuation on the primary heating effect, and providing a basis for subsequent treatment. In addition, when the pressure of the industrial water source (such as municipal pipe network or industrial circulating water) fluctuates, the third delivery pump 33 can dynamically adjust the output pressure to ensure that the water supplied into the cooler 232 is not affected by the external water supply conditions, and maintain stable operation.

[0067] In an embodiment of the present application, as shown in the figure, Figure 1 The waste heat recovery steam supply device 3 further comprises a fourth delivery pump 34 connected in series on the pipeline between the vacuum deaerator 320 and the first heat exchanger 321.

[0068] In the above scheme, the vacuum deaerator 320 removes dissolved oxygen in the industrial water through a negative pressure environment, but the deaeration process may cause the water flow pressure to decrease, and the fourth delivery pump 34 pressurizes to compensate for the pressure loss in the deaeration process, ensuring that the deaerated water enters the first heat exchanger 321 with stable flow.

[0069] It should be noted that the communication between the components in the above described waste heat industrial steam supply system based on nuclear reactors and molten salt energy storage power generation is all sealed communication through the setting of pipelines, for example, the heat exchanger 230 and the cooler 232 are sealed and communicated through the pipeline, and for example, the cooler 232 and the compressor 231 are sealed and communicated through the pipeline.

[0070] It should be noted that in this document, the terms such as "first" and "second" are only used to distinguish one entity or operation from another entity or operation, and do not necessarily require or imply any such actual relationship or order between the entities or operations. Moreover, the terms "include", "contain" or any other variants thereof are intended to cover non-exclusive inclusion, so that the process, method, article or device including a series of elements not only includes those elements, but also includes other elements not explicitly listed or inherent to such process, method, article or device. Without more limitations, the element defined by the statement "including a" does not exclude the presence of other identical elements in the process, method, article or device including the element.

[0071] The above description is only a specific implementation of the present application, enabling those skilled in the art to understand or implement the present application. Various modifications to these embodiments will be apparent to those skilled in the art, and the general principles defined herein can be implemented in other embodiments without departing from the spirit or scope of the present application. Therefore, the present application will not be limited to these embodiments described herein, but will conform to the widest scope consistent with the principles and novel features disclosed herein.

Claims

1. A waste heat industrial steam supply system based on nuclear reactor and molten salt energy storage power generation, characterized in that, include: A molten salt energy storage device includes a circulating thermal storage medium, wherein the circulating thermal storage medium is a fluoride molten salt, used for thermal storage and heat exchange. The nuclear power generation unit includes a fourth-generation nuclear reactor, a first power generation unit, a second power generation unit, and a pretreatment recirculation pipeline. The fourth-generation nuclear reactor uses supercritical carbon dioxide as the heat-absorbing medium. The output of the fourth-generation nuclear reactor is divided into a main flow path and a branch flow path. The main flow path transports supercritical carbon dioxide to the first power generation unit to generate electricity. After generating electricity, the supercritical carbon dioxide is treated by the pretreatment recirculation pipeline containing a cooler and then returned to the fourth-generation nuclear reactor. The branch flow path introduces supercritical carbon dioxide into the molten salt energy storage device for heat exchange. After heat exchange, the supercritical carbon dioxide is transported to the second power generation unit to generate electricity. The waste heat recovery steam supply device includes an industrial water inlet pipeline and a pretreatment heat exchange pipeline. The cooler is connected to both the industrial water inlet pipeline and the pretreatment heat exchange pipeline. The industrial water is heated in the first stage by the cooler, and the heated industrial water flows into the pretreatment heat exchange pipeline. The supercritical carbon dioxide generated by the second power generation device flows through the pretreatment heat exchange pipeline to perform secondary heating on the industrial water after the first stage heating, forming a steam-water mixture. The supercritical carbon dioxide, after exchanging heat with the industrial water, is treated by the pretreatment return pipeline and then returned to the fourth-generation nuclear reactor. The steam-water mixture undergoes steam-water separation treatment in the pretreatment heat exchange pipeline. The separated steam is output as industrial steam, and the separated water is returned to the pretreatment heat exchange pipeline for circulating heat exchange.

2. The waste heat industrial steam supply system based on nuclear reactor and molten salt energy storage power generation according to claim 1, characterized in that, The pretreatment heat exchange pipeline includes a vacuum deaerator, a first heat exchanger, and a steam-water separator, wherein... The vacuum deaerator is connected to the cooler and the first heat exchanger respectively; The steam-water separator is connected to the first heat exchanger. The steam-water separator is used to separate the steam and water mixture. The steam port of the steam-water separator is used to output the separated steam. The liquid port of the steam-water separator is connected to the connecting pipeline between the vacuum deaerator and the first heat exchanger, and is used to return the separated water to the first heat exchanger for continued heat exchange.

3. The waste heat industrial steam supply system based on nuclear reactor and molten salt energy storage power generation according to claim 2, characterized in that, The pretreatment reflux pipeline includes a regenerator, a compressor, and the cooler, wherein... The regenerator is connected to the first power generation device, the cooler, the compressor and the fourth-generation nuclear reactor respectively. The compressor and the cooler are connected. The supercritical carbon dioxide generated by the first power generation device flows sequentially through the regenerator, the cooler, the compressor and back to the fourth-generation nuclear reactor, completing a closed-loop flow. The first heat exchanger is connected to the connecting pipe between the regenerator and the cooler, and is used to allow the supercritical carbon dioxide generated by the second power generation device to flow through the first heat exchanger and back to the cooler in a closed loop.

4. The waste heat industrial steam supply system based on nuclear reactor and molten salt energy storage power generation according to claim 3, characterized in that, The molten salt energy storage device further includes a low-temperature molten salt tank, a first transfer pump, a second heat exchanger, a high-temperature molten salt tank, a second transfer pump, and a third heat exchanger, wherein... The cryogenic molten salt tank stores the fluoride molten salt, the cryogenic molten salt tank is connected to the second heat exchanger, and the first delivery pump is installed on the connecting pipeline between the cryogenic molten salt tank and the second heat exchanger; The second heat exchanger is connected to the branch path and the second power generation device; The high-temperature molten salt tank is connected to the second heat exchanger and the third heat exchanger respectively, and a second delivery pump is provided on the connecting pipeline between the high-temperature molten salt tank and the third heat exchanger. The high-temperature molten salt tank is used to store the fluoride molten salt in a high-temperature state after heat exchange by the second heat exchanger. The third heat exchanger is connected to the cryogenic molten salt tank.

5. The waste heat industrial steam supply system based on nuclear reactor and molten salt energy storage power generation according to claim 4, characterized in that, Also includes: An energy storage-side power generation device, comprising an energy storage-side pipeline and a third power generation device, wherein one end of the energy storage-side pipeline is connected to the third heat exchanger, and the other end of the energy storage-side pipeline is connected to a reflux pipeline connecting the regenerator and the fourth-generation nuclear reactor. The third power generation device is connected to the third heat exchanger and the pipeline connecting the regenerator and the first power generation device. The supercritical carbon dioxide in the energy storage side pipeline is used to exchange heat with the fluoride molten salt that has completed heat storage and is in a high temperature state. The supercritical carbon dioxide after heat exchange is supplied to the third power generation device to drive the third power generation device to generate electricity.

6. The waste heat industrial steam supply system based on nuclear reactor and molten salt energy storage power generation according to claim 5, characterized in that, The first, second, and third power generation devices all include a turbine and a generator, with the turbine connected to the generator. The turbine in the first power generation unit is connected to the main flow path and the regenerator, respectively. The turbine in the second power generation unit is connected to both the first heat exchanger and the second heat exchanger. The turbine in the third power generation unit is connected to the third heat exchanger and the pipeline connecting the regenerator to the first power generation unit.

7. The waste heat industrial steam supply system based on nuclear reactor and molten salt energy storage power generation according to claim 4, characterized in that, A first regulating valve is provided on the diversion path, and the first regulating valve is located between the fourth-generation nuclear reactor and the second heat exchanger.

8. The waste heat industrial steam supply system based on nuclear reactor and molten salt energy storage power generation according to claim 5, characterized in that, A second regulating valve is installed on the energy storage side pipeline, and the second regulating valve is located near the fourth-generation nuclear reactor.

9. The waste heat industrial steam supply system based on nuclear reactor and molten salt energy storage power generation according to claim 2, characterized in that, The waste heat recovery steam supply device also includes a third delivery pump, which is connected in series to the industrial water inlet pipeline.

10. The waste heat industrial steam supply system based on nuclear reactor and molten salt energy storage power generation according to claim 2, characterized in that, The waste heat recovery steam supply device also includes a fourth delivery pump, which is connected in series in the pipeline between the vacuum deaerator and the first heat exchanger.

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