Power generation and waste heat utilization coupling system based on nuclear reactor and fused salt energy storage

Abstract

The invention discloses a nuclear reactor and fused salt energy storage-based power generation and waste heat utilization coupling system, which comprises a nuclear energy side power generation device, a fused salt energy storage device and a waste heat refrigeration device, and is characterized in that 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 return pipeline, the fourth-generation nuclear reactor adopts supercritical carbon dioxide as a heat absorption medium, 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 the supercritical carbon dioxide to the first power generation device to do work and generate power, and then the supercritical carbon dioxide after doing work is conveyed to the pretreatment return pipeline containing the cooler. Therefore, redundant heat sources generated in the power generation process can be recycled, waste of resources is reduced, refrigeration is driven through waste heat recovery while the power generation efficiency is guaranteed, dual-function output of power generation and refrigeration is achieved, and compared with a single power generation mode, the comprehensive utilization rate of energy is increased.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of waste heat recycling, and in particular to a power generation and waste heat utilization coupling system based on a nuclear reactor and molten salt energy storage. 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 by the turbine, thereby generating high-temperature steam, which is then transported to another turbine for power generation. In addition, there is a scheme for 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, there is a waste of excess heat resources. For example, after the medium branched from the nuclear reactor to heat the molten salt energy storage is used to complete the power generation, the current processing method is usually to directly discharge it or transmit it back to the nuclear reactor. However, this process does not fully consider the recycling of waste heat, thereby causing waste of resources, and the single power generation mode has a low comprehensive energy utilization rate. 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 power generation and waste heat utilization coupling system based on a nuclear reactor and molten salt energy storage, which can recycle the excess heat generated during power generation, reduce resource waste, and while ensuring power generation efficiency, drive refrigeration through waste heat recycling to realize "power generation + refrigeration" dual-function output, thereby improving the comprehensive energy utilization rate compared to the single power generation mode.

[0006] To achieve the above object, the present application provides a power generation and waste heat utilization coupling system based on a nuclear reactor and molten salt energy storage, comprising a nuclear energy side power generation device, a molten salt energy storage device, and a waste heat refrigeration device, wherein, 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 return pipeline, wherein the fourth generation nuclear reactor uses supercritical carbon dioxide as a heat absorption medium, an output end 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 device to generate power, and then transports the supercritical carbon dioxide after work to the pretreatment return pipeline containing a cooler, the pretreatment return pipeline is connected with the fourth generation nuclear reactor in communication, and the branch flow path is connected with the molten salt energy storage device, the second power generation device, the waste heat refrigeration device and the pretreatment return pipeline in series communication. The supercritical carbon dioxide flowing out of the second power generation device is supplied as a first heat source into the waste heat refrigeration device. The cooler is connected with the waste heat refrigeration device in communication, cooling water in the cooler exchanges heat with supercritical carbon dioxide flowing through the cooler, and the cooling water after heating is supplied as a second heat source into the waste heat refrigeration device. The refrigeration medium of an external demand device flows through the waste heat refrigeration device and is cooled in the waste heat refrigeration device.

[0007] The nuclear reactor and molten salt energy storage based power generation and waste heat utilization coupling system of the application realizes efficient recycling of multi-source waste heat resources (a first heat source and a second heat source) generated in the nuclear energy side power generation process by integrating and coupling the nuclear energy side power generation device and the waste heat refrigeration device, reduces resource waste, ensures power generation efficiency, drives refrigeration through waste heat recovery, realizes dual function output of power generation and refrigeration, provides refrigeration services for external demand devices, and improves overall economic efficiency and energy comprehensive utilization rate compared with a single power generation mode.

[0008] In addition, the nuclear reactor and molten salt energy storage based power generation and waste heat utilization coupling system according to the above applicationapplicationhave the following additional technical features: Specifically, the waste heat refrigeration device comprises an absorber, a first regenerative heat exchanger, a second regenerative heat exchanger, a high-temperature generator, a first heat exchanger, a low-temperature generator, a condenser and an evaporator, wherein the absorber is in bidirectional communication with the first regenerative heat exchanger, the first regenerative heat exchanger is in communication with the second regenerative heat exchanger, the second regenerative heat exchanger is in bidirectional communication with the high-temperature generator, the high-temperature generator is in circulation communication with the first heat exchanger, and the shunt circuit is in communication with the first heat exchanger; the low-temperature generator is in communication with the high-temperature generator, the second regenerative heat exchanger, the first regenerative heat exchanger and the condenser respectively, the cooling water outlet is in communication with the low-temperature generator, the cooling water is discharged after heat exchange in the low-temperature generator, the condenser is in communication with the evaporator, the refrigeration medium of the external demand equipment flows through the evaporator for cooling, and the evaporator is in communication with the absorber.

[0009] Specifically, the outlet of the absorber is in communication with a solution pump, and the outlet of the solution pump is in communication with the first regenerative heat exchanger.

[0010] Specifically, the pre-treatment return pipeline comprises a regenerative heat exchanger, a compressor and the cooler, wherein, The regenerative heat exchanger is in communication with the main circuit, the cooler, the compressor and the fourth generation nuclear reactor respectively, and the compressor and the cooler are in communication, wherein the supercritical carbon dioxide after power generation of the first power generation device flows through the regenerative heat exchanger, the cooler, the compressor and the regenerative heat exchanger in sequence and returns to the fourth generation nuclear reactor to complete closed-loop flow; the pipeline in communication with the regenerative heat exchanger and the cooler after the shunt circuit is in communication with the first heat exchanger is in communication with the pipeline between the regenerative heat exchanger and the cooler, and is used for conveying the supercritical carbon dioxide flowing through the first heat exchanger to the cooler, and flowing through the cooler, the compressor and the regenerative heat exchanger in sequence and returning to the fourth generation nuclear reactor to complete closed-loop flow.

[0011] 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 fluoride molten salt, the low-temperature molten salt tank is in communication with 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 shunt circuit sequentially communicates the second heat exchanger and the second power generation device; the high-temperature molten salt tank is in communication with the second heat exchanger and the third heat exchanger respectively, 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 for storing the fluoride molten salt in a high-temperature state after heat exchange in the second heat exchanger; and the third heat exchanger is in communication with the low-temperature molten salt tank.

[0012] Specifically, the energy storage side power generation device is further included, which comprises an energy storage side pipeline and a third power generation device, wherein one end of the energy storage side pipeline is connected with the third heat exchanger, and the other end of the energy storage side pipeline is connected with a communication pipeline which communicates between the regenerator and the fourth generation nuclear reactor; The third power generation device is connected with the third heat exchanger and the main flow path respectively, and the supercritical carbon dioxide in the energy storage side pipeline is used to exchange heat with the fluoride molten salt which has completed heat storage in the third heat exchanger, and the supercritical carbon dioxide after heat exchange is supplied into the third power generation device to drive the third power generation device to generate electricity.

[0013] Specifically, the first power generation device, the second power generation device and the third power generation device each comprise a turbine and a generator, and the turbine is connected with the generator, wherein, The turbine in the first power generation device is connected in series on the main flow path; The turbine in the second power generation device is connected in series on the branch flow path; The turbine in the third power generation device is connected with the third heat exchanger and the main flow path respectively.

[0014] Specifically, a first regulating valve is arranged on the branch flow path.

[0015] Specifically, a second regulating valve is arranged on the energy storage side pipeline, and the second regulating valve is arranged near the fourth generation nuclear reactor. Specifically, an input pipeline, a connecting pipeline and an output pipeline are further included, wherein the input pipeline, the absorber, the connecting pipeline, the condenser and the output pipeline are connected in series. BRIEF DESCRIPTION OF DRAWINGS

[0016] The accompanying drawings incorporated in and forming a part of the specification, illustrate embodiments consistent with the present application and, together with the description, serve to explain the principles of the application.

[0017] 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 as follows. Obviously, for those of ordinary skill in the art, other drawings can also be obtained based on these drawings without any creative work.

[0018] Figure 1 The structure diagram of the nuclear reactor and molten salt energy storage based power generation and waste heat utilization coupling system according to an embodiment of the present application.

[0019] As shown in the figure: 10, fourth generation nuclear reactor; 11, main flow path; 12, branch flow path; 13, first power generation device; 14, second power generation device; 15, pretreatment return pipeline; 16, first regulating valve; 130, turbine; 131, generator; 150, regenerator; 151, cooler; 152, compressor; 20, low-temperature molten salt tank; 21, first delivery pump; 22, second heat exchanger; 23, high-temperature molten salt tank; 24, second delivery pump; 25, third heat exchanger; 30, absorber; 31, first regeneration heat exchanger; 32, second regeneration heat exchanger; 33, high-temperature generator; 34, first heat exchanger; 35, low-temperature generator; 36, condenser; 37, evaporator; 38, solution pump; 40, energy storage side pipeline; 41, third power generation device; 42, second regulating valve; A, input pipeline; B, connecting pipe; C, output pipeline. DETAILED DESCRIPTION

[0020] In order to enable the above-mentioned objects, features and advantages of the present application to be more clearly understood, the following will further describe the solutions of the present application. It should be noted that the embodiments of the present application and the features in the embodiments can be combined with each other without conflict.

[0021] In the following description, many specific details are set forth in order to provide a thorough understanding of the present application, but the present application can also be implemented in other ways different from those described herein; obviously, the embodiments in the description are only some of the embodiments of the present application, not all the embodiments.

[0022] The nuclear reactor and molten salt energy storage based power generation and waste heat utilization coupling system according to the embodiments of the present application will be described below in combination with the accompanying drawings.

[0023] As Figure 1 shown, the nuclear reactor and molten salt energy storage based power generation and waste heat utilization coupling system according to the embodiments of the present application can include a nuclear energy side power generation device, a molten salt energy storage device and a waste heat refrigeration device.

[0024] The nuclear energy side power generation device includes a fourth generation nuclear reactor 10, a first power generation device 13, a second power generation device 14 and a pretreatment return pipeline 15.

[0025] The fourth generation nuclear reactor 10 uses supercritical carbon dioxide as the heat absorption medium.

[0026] It should be noted that the fourth generation nuclear reactor 10 is selected, and supercritical carbon dioxide is used as the heat absorption medium, and the Brayton cycle based on the fourth generation nuclear reactor 10 is successfully realized. This design raises the temperature of supercritical carbon dioxide to 950℃, which significantly improves the upper limit of thermal energy compared to the traditional nuclear reactor using steam as the circulating medium, laying a foundation for the subsequent utilization of waste heat.

[0027] The output end of the fourth generation nuclear reactor 10 is divided into a main flow path 11 and a branch flow path 12. The main flow path 11 transports supercritical carbon dioxide to the first power generation device 13 for work and power generation, and then transports the supercritical carbon dioxide after work to the pretreatment return pipeline 15 containing the cooler 151. The pretreatment return pipeline 15 is in communication with the fourth generation nuclear reactor 10. The high-temperature supercritical carbon dioxide flowing out of the fourth generation nuclear reactor 10 is returned to the fourth generation nuclear reactor 10 through the main flow path 11, the first power generation device 13, and the pretreatment return pipeline 15 to form a closed loop flow.

[0028] The branch flow path 12 is in series communication with the molten salt energy storage device, the second power generation device 14, the waste heat refrigeration device, and the pretreatment return pipeline 15. When the supercritical carbon dioxide in the branch flow path 12 flows through the molten salt energy storage device, heat exchange is performed in the molten salt energy storage device, and the molten salt energy storage device stores heat energy. When the supercritical carbon dioxide flows through the second power generation device 14, the second power generation device 14 can be driven to operate and generate power. When the supercritical carbon dioxide flows through the waste heat refrigeration device, it can be supplied as a first heat source into the waste heat refrigeration device for heat exchange. Finally, the supercritical carbon dioxide flows into the pretreatment return pipeline 15 and is returned to the fourth generation nuclear reactor 10 after treatment to form a closed loop flow.

[0029] The supercritical carbon dioxide flowing out of the second power generation device 14 is supplied as a first heat source into the waste heat refrigeration device, that is, the supercritical carbon dioxide after work and power generation can be recycled and reused. Compared with the existing technology of directly discharging or transferring back to the nuclear reactor, the waste and loss of resources are avoided.

[0030] The outlet of the cooler 151 is in communication with the waste heat refrigeration device. The cooling water in the cooler 151 exchanges heat with the supercritical carbon dioxide flowing through the cooler 151, and the heated cooling water is supplied as a second heat source into the waste heat refrigeration device. That is, the heat dissipated by the cooler 151 is additionally considered, the heat of the cooling water outlet of the cooler 151 is separately led out, and the heat released by the supercritical carbon dioxide in the cooler 151 during return is reasonably utilized. The part of the heat is supplied as a second heat source into the waste heat refrigeration device for recycling and reuse, further avoiding the waste of resources.

[0031] The refrigeration medium of the external demand equipment flows through the waste heat refrigeration device and is cooled in the waste heat refrigeration device.

[0032] It should be noted that the external demand equipment can be selected according to the demand, which is not limited here. For example, the external demand equipment can be the air conditioning system (control room / equipment room cooling) of the nuclear power plant itself, which replaces the original refrigeration unit to reduce the plant power consumption, wherein the refrigeration medium can be cold coal water.

[0033] Specifically, after the supercritical carbon dioxide is heated to about 950℃ in the fourth generation nuclear reactor 10, it is divided into two paths, the main flow path 11 and the branch flow path 12. The main flow path 11 transports the high-temperature and high-pressure supercritical carbon dioxide to the first power generation device 13 to drive its operation and power generation through expansion work; the supercritical carbon dioxide after work is treated by the pretreatment return pipeline 15 and then returns to the fourth generation nuclear reactor 10 to form a closed loop cycle of the main flow path 11.

[0034] The branch flow path 12 introduces the supercritical carbon dioxide at 950℃ into the molten salt energy storage device for heat exchange, and the molten salt energy storage device stores heat energy by absorbing part of the heat energy; after heat exchange, the supercritical carbon dioxide is cooled to about 450℃ and is transported to the second power generation device 14 to drive its work and power generation. The supercritical carbon dioxide after work is further cooled to about 250℃ and then is supplied as a first heat source into the waste heat refrigeration device for heat exchange, and the waste heat refrigeration device recycles the waste heat carried by it. The supercritical carbon dioxide after heat exchange in the waste heat refrigeration device enters the pretreatment return pipeline 15 for treatment and finally returns to the fourth generation nuclear reactor 10 to complete the closed loop cycle of the branch flow path 12.

[0035] In addition, when the supercritical carbon dioxide flows through the cooler 151, it exchanges heat with the cooling medium (such as cooling water) in the cooler 151: the supercritical carbon dioxide is cooled, and the cooling medium is heated. The heated cooling medium is introduced into the waste heat refrigeration device as a second heat source for further heat exchange; the waste heat refrigeration device recycles this part of the heat source. At the same time, when the refrigeration medium of the external demand equipment flows through the waste heat refrigeration device, it will be cooled to meet the external refrigeration demand.

[0036] By integrating and coupling the nuclear energy side power generation device and the waste heat refrigeration device, the multi-source waste heat resources (first heat source and second heat source) generated in the nuclear energy side power generation process are recycled and utilized efficiently, reducing resource waste. While ensuring power generation efficiency, the waste heat is recycled to drive refrigeration, realizing the dual functions of "power generation + refrigeration" and providing refrigeration services for external demand equipment, which improves the overall economy and energy utilization rate of the project compared to the single power generation mode.

[0037] Further, as shown in Figure 1 the waste heat refrigeration device includes an absorber 30, a first regenerative heat exchanger 31, a second regenerative heat exchanger 32, a high-temperature generator 33, a first heat exchanger 34, a low-temperature generator 35, a condenser 36, and an evaporator 37.

[0038] The absorber 30 is in bidirectional communication with the first regenerative heat exchanger 31, wherein the medium in the absorber 30 can flow into the first regenerative heat exchanger 31, and the medium in the first regenerative heat exchanger 31 can also flow into the absorber 30.

[0039] The first regenerative heat exchanger 31 is in communication with the second regenerative heat exchanger 32, the second regenerative heat exchanger 32 is in bidirectional communication with the high-temperature generator 33, the high-temperature generator 33 is in circulation communication with the first heat exchanger 34, and the first heat exchanger 34 is in communication with the split flow path 12; the low-temperature generator 35 is in communication with the high-temperature generator 33, the second regenerative heat exchanger 32, the first regenerative heat exchanger 31, and the condenser 36, respectively; the cooling water outlet is in communication with the low-temperature generator 35, the cooling water is discharged after heat exchange in the low-temperature generator 35, the condenser 36 is in communication with the evaporator 37, the refrigerant of the external demand equipment flows through the evaporator 37 to be cooled, and the evaporator 37 is in communication with the absorber 30.

[0040] Specifically, the intermediate heat source flowing through the first heat exchanger 34 exchanges heat with the supercritical carbon dioxide in the split flow path 12, the intermediate heat source absorbs heat and returns to the high-temperature generator 33 to release heat, and then enters the first heat exchanger 34 again to absorb heat, thereby forming a circulating flow.

[0041] The intermediate heat source can be water, the water temperature at the inlet of the first heat exchanger 34 is 70℃, and after heat exchange with the supercritical carbon dioxide in the split flow path 12, the water temperature at the outlet of the first heat exchanger 34 can reach 180℃.

[0042] The lithium bromide dilute solution is stored in the absorber 30, the lithium bromide dilute solution first enters the first regenerative heat exchanger 31 to absorb heat, and completes the first heating. Then, the lithium bromide dilute solution after the first heating enters the second regenerative heat exchanger 32 to absorb heat again. Then, the lithium bromide dilute solution after the heating of the second regenerative heat exchanger 32 enters the high-temperature generator 33 to exchange heat with the intermediate heat source, and realizes the third heating. After the three heating processes, the lithium bromide dilute solution is converted into the first lithium bromide concentrated solution and the first water vapor in the high-temperature generator 33.

[0043] The first lithium bromide concentrated solution flows from the high-temperature generator 33 into the second regenerative heat exchanger 32 to release heat, and heats the lithium bromide dilute solution flowing through the second regenerative heat exchanger 32. The first lithium bromide concentrated solution after releasing heat enters the low-temperature generator 35 to absorb heat. At the same time, the first water vapor also enters the low-temperature generator 35 to release heat, and the heat released is absorbed by the first lithium bromide concentrated solution flowing through. In addition, the cooling water after absorbing heat in the cooler 151 also enters the low-temperature generator 35 to provide the second heat source for the first lithium bromide concentrated solution. The cooling water after releasing heat is led out of the low-temperature generator 35.

[0044] The first lithium bromide concentrated solution is heated again in the low-temperature generator 35, and a small amount of moisture is converted into water vapor, and the first lithium bromide concentrated solution is thus changed into a second lithium bromide concentrated solution and second water vapor. The second lithium bromide concentrated solution enters the first regenerative heat exchanger 31 to release heat, and then enters the absorber 30. The second water vapor and the first water vapor enter the condenser 36 through different connecting pipes and are mixed therein. The mixed water vapor is changed into liquid water in the condenser 36, and the liquid water enters the evaporator 37 to absorb heat of the refrigerant flowing through the external demand equipment, so that the refrigerant is cooled to achieve the refrigeration effect. The liquid water is changed into water vapor after absorbing heat in the evaporator 37, and enters the absorber 30 to be mixed with the second lithium bromide concentrated solution flowing back to the absorber 30 from the first regenerative heat exchanger 31. The second lithium bromide concentrated solution is changed into a lithium bromide dilute solution after absorbing the water vapor, and thus a complete cycle is formed, which is completed through multi-stage heat exchange to improve the overall refrigeration performance.

[0045] That is, the lithium bromide dilute solution is sequentially heated through the first regenerative heat exchanger 31, the second regenerative heat exchanger 32, and the high-temperature generator 33 to realize gradient heating, fully recover the waste heat in different links of the system, and orderly gather and efficiently convert the originally dispersed and difficult-to-fully-utilize waste heat through multi-stage heat exchange, so that the heat energy utilization rate is significantly improved. A diversified heat source utilization strategy is adopted. In addition to using supercritical carbon dioxide as a first heat source to provide energy for heating the lithium bromide dilute solution, the cooling water is also innovatively introduced into the low-temperature generator 35 as a second heat source. The low-temperature waste heat carried by the cooling water is often wasted in a traditional system due to the lack of effective recovery means, but the system can realize deep recovery and reuse of the low-temperature waste heat through ingenious design. This dual-heat-source utilization mode greatly expands the range of heat energy that can be utilized by the system and effectively reduces the dependence of the waste heat refrigeration device on external heat sources.

[0046] In addition, the concentrated solution and the dilute solution realize dynamic heat exchange, which not only guarantees the heating demand of the solution, but also recovers the sensible heat of the concentrated solution and reduces energy invalid loss.

[0047] In an embodiment of the present application, as shown in Figure 1 The nuclear reactor and molten salt energy storage-based power generation and waste heat utilization coupled system further includes an input pipe A, a connecting pipe B, and an output pipe C, wherein the input pipe A, the absorber 30, the connecting pipe B, the condenser 36, and the output pipe C are sequentially and communicatively connected.

[0048] The input pipeline A serves as a channel for external water input (such as an external domestic water pipeline), and the output pipeline C is responsible for communicating with external demanders. In the absorber 30, the process of absorbing water vapor by the lithium bromide concentrated solution is an exothermic process; at the same time, in the condenser 36, the process of water vapor cooling into water is also an exothermic process. The heat generated by the two parts is effectively utilized for preheating domestic water, further avoiding waste of resources, thereby improving the resource recycling rate of the system.

[0049] As shown in the example: Figure 1 The domestic hot water flows into the absorber 30 through the input pipeline A, and in the absorber 30, the domestic hot water absorbs the heat released by the lithium bromide concentrated solution when absorbing water vapor, and the temperature rises. Subsequently, the domestic hot water enters the condenser 36 through the connecting pipe B, and again absorbs the heat released when the water vapor cools into water, and the temperature further rises. Finally, the domestic hot water after two temperature rises is led out through the output pipeline C and transported to the demander.

[0050] In an embodiment of the present application, as shown in the example: Figure 1 The outlet of the absorber 30 is communicated with the solution pump 38, and the outlet of the solution pump 38 is communicated with the first regenerative heat exchanger 31.

[0051] In the above scheme, by setting the solution pump 38, the lithium bromide dilute solution can enter the first regenerative heat exchanger 31 with stable flow rate and pressure, avoiding flow interruption or flow fluctuation caused by excessive resistance, thereby maintaining the continuity and stability of the circulation.

[0052] In an embodiment of the present application, as shown in the example: Figure 1 The pre-treatment return pipeline 15 includes a regenerator 150, a compressor 152 and a cooler 151, wherein, The regenerator 150 is communicated with the main flow path 11, the cooler 151, the compressor 152 and the fourth generation nuclear reactor 10, and the compressor 152 and the cooler 151 are communicated, wherein the supercritical carbon dioxide after the first power generation device 13 generates power does work, sequentially flows through the regenerator 150, the cooler 151, the compressor 152, the regenerator 150 and returns to the fourth generation nuclear reactor 10, completing the closed loop flow; The pipeline communicated with the first heat exchanger 34 after the shunt path 12 is communicated with the communication pipeline between the regenerator 150 and the cooler 151, for transporting the supercritical carbon dioxide flowing through the first heat exchanger 34 to the cooler 151, sequentially flowing through the cooler 151, the compressor 152, the regenerator 150 and returning to the fourth generation nuclear reactor 10, completing the closed loop flow.

[0053] In the above scheme, the supercritical carbon dioxide flowing through the pre-treatment return pipeline 15 is treated to meet the conditions for entering the fourth generation nuclear reactor 10.

[0054] Specifically, the supercritical carbon dioxide flowing out of the first power generation device 13 has a temperature of about 450℃. In view of this high temperature condition, in order to reduce heat loss, the supercritical carbon dioxide needs to first flow into the regenerator 150 to release heat, and after the temperature is adjusted to an appropriate range, the supercritical carbon dioxide can enter the cooler 151 to carry out condensation treatment, and then flow into the regenerator 150 through the compressor 152 to absorb heat, and finally flow into the fourth generation nuclear reactor 10.

[0055] The supercritical carbon dioxide flowing out of the second power generation device 14 has a lower temperature because it has been subjected to heat exchange in the second heat exchanger 22, and has released part of the energy during driving work and after heat exchange in the first heat exchanger 34. Based on this lower temperature, the supercritical carbon dioxide does not need to first flow into the regenerator 150 to release heat, but can be directly transported to the cooler 151 to carry out condensation treatment, and then flow into the fourth generation nuclear reactor 10 through the compressor 152 and the regenerator 150, to form a closed loop flow.

[0056] In one embodiment of the present application, as shown in Figure 1 The molten salt energy storage device further includes a low-temperature molten salt tank 20, a first delivery pump 21, a second heat exchanger 22, a high-temperature molten salt tank 23, a second delivery pump 24, and a third heat exchanger 25.

[0057] The low-temperature molten salt tank 20 stores fluoride molten salt, and is in communication with the second heat exchanger 22. The communication pipeline between the low-temperature molten salt tank 20 and the second heat exchanger 22 is provided with the first delivery pump 21. The shunt pipeline 12 is in communication with the second heat exchanger 22 and the second power generation device 14 in sequence. The high-temperature molten salt tank 23 is in communication with the second heat exchanger 22 and the third heat exchanger 25, and the communication pipeline between the high-temperature molten salt tank 23 and the third heat exchanger 25 is provided with the second delivery pump 24. The high-temperature molten salt tank 23 is used to store fluoride molten salt in a high-temperature state after heat exchange in the second heat exchanger 22. The third heat exchanger 25 is in communication with the low-temperature molten salt tank 20.

[0058] It should be noted that the first delivery pump 21 is used to deliver the fluoride molten salt in a low temperature state, and the second delivery pump 24 is used to deliver the fluoride molten salt in a high temperature heat storage state, so in the selection of the delivery pump, the first delivery pump 21 can be selected as a low temperature molten salt pump, and the second delivery pump 24 can be selected as a high temperature molten salt pump, wherein the fluoride molten salt as a circulating heat storage working medium can be heated to 900℃, breaking the traditional temperature upper limit (nitrate 600℃) of molten salt heat storage, significantly improving the energy storage efficiency, and the outlet temperature of the fourth generation nuclear reactor 10 can reach 950℃, the fluoride molten salt has high temperature resistance, and is highly consistent with the heat output characteristics of the fourth generation nuclear reactor 10, eliminating the temperature limitation of traditional working medium. In addition, the heat storage density of the fluoride molten salt is higher, which is about one time higher than that of the nitrate.

[0059] Specifically, the first delivery pump 21 can be controlled to extract the fluoride molten salt stored in the low temperature molten salt tank 20 and deliver it to the second heat exchanger 22 to exchange heat with the high temperature supercritical carbon dioxide flowing in the branch flow path 12, and the fluoride molten salt absorbing and storing heat is transferred to the high temperature molten salt tank 23 for storage. At this time, the temperature of the fluoride molten salt in the high temperature molten salt tank 23 is about 900℃, wherein the high temperature molten salt tank 23 is a special container for storing high temperature molten salt, and 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 23 can ensure that the stored heat meets the use requirements for a long time.

[0060] If it is needed to use according to the actual situation, the second delivery pump 24 can be controlled to extract the fluoride molten salt in the high temperature molten salt tank 23 and deliver it to the third heat exchanger 25 to heat the medium (supercritical carbon dioxide in the energy storage side power generation device) flowing in the third heat exchanger 25, and the fluoride molten salt after heat exchange in the third heat exchanger 25 flows out and is stored in the low temperature molten salt tank 20 to form a closed loop circulation.

[0061] In an embodiment of the present application, as shown in Figure 1 The power generation and waste heat utilization coupling system based on the nuclear reactor and the molten salt energy storage further includes an energy storage side power generation device, the energy storage side power generation device includes an energy storage side pipeline 40 and a third power generation device 41, wherein one end of the energy storage side pipeline 40 is connected with the third heat exchanger 25, the other end of the energy storage side pipeline 40 is connected with a communication pipeline between the communication regenerator 150 and the fourth generation nuclear reactor 10, the third power generation device 41 is connected with the third heat exchanger 25 and the main flow path 11 respectively, the supercritical carbon dioxide in the energy storage side pipeline 40 is used to exchange heat with the fluoride molten salt for heat storage in the third heat exchanger 25, and the supercritical carbon dioxide after heat exchange is supplied into the third power generation device 41 to drive the third power generation device 41 to generate power.

[0062] In the above scheme, by designing the energy storage side power generation device, the heat energy stored by the molten salt is reasonably utilized, the high efficient power generation capacity of the supercritical carbon dioxide Brayton cycle is combined with the flexible peak shaving characteristics of the molten salt energy storage device, the flexibility of the overall nuclear power system is increased, for example, when the energy storage side power generation device needs to be started according to the electricity demand, the fluoride molten salt in the high-temperature molten salt tank 23 is extracted by the second delivery pump 24 and delivered to the third heat exchanger 25 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.

[0063] At the same time, the energy storage side power generation device is partially coupled with the nuclear energy side power generation device, that is, the energy storage side power generation device shares the pre-treatment return pipeline 15 in the nuclear energy side power generation device, and under the condition that the thermodynamic parameters do not conflict, the system cost is saved to a certain extent.

[0064] In addition, the supercritical carbon dioxide heated by the regenerator 150 flows into the fourth generation nuclear reactor 10 in a large part, and flows into the third heat exchanger 25 in another part to be heated by the fluoride molten salt. At the same time, when the fourth generation nuclear reactor 10 needs to be overhauled, the heat energy delivery function can be completely taken over by adjusting the shunt ratio. This cross backup mechanism reduces the unplanned downtime, significantly improves the availability of the system, and ensures the power generation demand.

[0065] In an embodiment of the present application, as shown in Figure 1 The first power generation device 13, the second power generation device 14 and the third power generation device 41 each include a turbine 130 and a generator 131, and the turbine 130 is connected with the generator 131.

[0066] The turbine 130 in the first power generation device 13 is connected in series on the main flow path 11, the turbine 130 in the second power generation device 14 is connected in series on the shunt flow path 12, and the turbine 130 in the third power generation device 41 is connected with the third heat exchanger 25 and the main flow path 11 respectively.

[0067] Specifically, the high-temperature and high-pressure supercritical carbon dioxide enters the turbine 130, the supercritical carbon dioxide expands to do work, pushes the turbine 130 blades to rotate, converts the heat energy into the rotating mechanical energy of the turbine 130, the turbine 130 operates to drive the generator 131 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.

[0068] In an embodiment of the present application, as shown in Figure 1 The first adjusting valve 16 is arranged on the shunt flow path 12.

[0069] In the above scheme, the flow in the shunt path 12 can be regulated or closed by the first regulating valve 16, and by regulating the supercritical carbon dioxide flow in the shunt path 12, the main and secondary power generation power ratio can be quickly adjusted. For example, when the demand of the power grid decreases, the shunt path 12 flow is increased, and more heat is stored; when the demand increases, the shunt path 12 flow is reduced, and the power generation output on the main path 11 is preferentially ensured to meet the demand of the power grid.

[0070] In one embodiment of the present application, as shown in Figure 1 The second regulating valve 42 is arranged on the energy storage side pipeline 40, and the second regulating valve 42 is arranged near the fourth generation nuclear reactor 10.

[0071] In the above scheme, by adjusting the opening degree of the second regulating valve 42, the supercritical carbon dioxide flow entering the energy storage side power generation device can be accurately controlled, and then the ratio of the energy storage side power generation power to the nuclear energy side power generation power is adjusted.

[0072] It should be noted that the connection between the components in the above-mentioned nuclear reactor and molten salt energy storage-based power generation and waste heat utilization coupled system is all sealed and connected through pipelines, for example, the regenerator 150 and the cooler 151 are sealed and connected through a pipeline, and for example, the cooler 151 and the compressor 152 are sealed and connected through a pipeline.

[0073] It should be noted that in this paper, relational 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 that there is 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 equipment 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 equipment. Without more limitations, the element defined by the statement "including a" does not exclude the presence of another identical element in the process, method, article or equipment including the element.

[0074] The above is only a specific embodiment of the present application, which enables those skilled in the art to understand or implement the present application. Various modifications of 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 nuclear reactor and molten salt energy storage based power generation and waste heat utilization coupled system, characterized in that, The nuclear power side power generation device, the molten salt energy storage device and the waste heat refrigeration device, wherein, The nuclear power side power generation device comprises a fourth generation nuclear reactor, a first power generation device, a second power generation device and a pretreatment return pipeline, wherein the fourth generation nuclear reactor uses supercritical carbon dioxide as a heat absorption medium, 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 delivers supercritical carbon dioxide to the first power generation device to generate power, and then delivers the supercritical carbon dioxide after work to the pretreatment return pipeline containing a cooler, the pretreatment return pipeline is connected with the fourth generation nuclear reactor, and the branch flow path is connected with the molten salt energy storage device, the second power generation device, the waste heat refrigeration device and the pretreatment return pipeline in sequence. The supercritical carbon dioxide flowing out of the second power generation device is supplied as a first heat source into the waste heat refrigeration device. The outlet of the cooling water in the cooler is connected with the waste heat refrigeration device, the cooling water exchanges heat with the supercritical carbon dioxide flowing through the cooler in the cooler, and the cooling water after heating is supplied as a second heat source into the waste heat refrigeration device. The refrigeration medium of an external demand device flows through the waste heat refrigeration device and is cooled in the waste heat refrigeration device.

2. The nuclear reactor and molten salt energy storage based power generation and waste heat utilization coupled system of claim 1, wherein, The waste heat refrigeration device comprises an absorber, a first regenerative heat exchanger, a second regenerative heat exchanger, a high-temperature generator, a first heat exchanger, a low-temperature generator, a condenser and an evaporator, wherein The absorber is connected with the first regenerative heat exchanger in a bidirectional manner, the first regenerative heat exchanger is connected with the second regenerative heat exchanger, the second regenerative heat exchanger is connected with the high-temperature generator in a bidirectional manner, the high-temperature generator is connected with the first heat exchanger in a circulating manner, and the branch flow path is connected with the first heat exchanger. The low-temperature generator is connected with the high-temperature generator, the second regenerative heat exchanger, the first regenerative heat exchanger, the condenser and the evaporator in sequence, the outlet of the cooling water is connected with the low-temperature generator, the cooling water is discharged after heat exchange in the low-temperature generator, the condenser is connected with the evaporator, the refrigeration medium of the external demand device flows through the evaporator to be cooled, and the evaporator is connected with the absorber.

3. The nuclear reactor and molten salt energy storage based power generation and waste heat utilization coupled system of claim 2, wherein, The outlet of the absorber is connected with a solution pump, and the outlet of the solution pump is connected with the first regenerative heat exchanger.

4. The nuclear reactor and molten salt energy storage based power generation and waste heat utilization coupled system of claim 2, wherein, The pretreatment return pipeline comprises a regenerator, a compressor and the cooler, wherein The regenerator is connected with the main flow path, the cooler, the compressor and the fourth generation nuclear reactor in sequence, and the compressor is connected with the cooler, wherein the supercritical carbon dioxide after work of the first power generation device flows through the regenerator, the cooler, the compressor and the regenerator in sequence and returns to the fourth generation nuclear reactor to complete a closed loop flow. The pipeline communicated with the first heat exchanger after the shunt path is connected with the communication pipeline between the regenerator and the cooler, for transporting the supercritical carbon dioxide flowing through the first heat exchanger into the cooler, sequentially flowing through the cooler, the compressor and the regenerator and returning to the fourth generation nuclear reactor to complete the closed loop flow.

5. The nuclear reactor and molten salt energy storage based power generation and waste heat utilization coupled system of claim 4, wherein, The molten salt energy storage device further comprises a low-temperature molten salt tank, a first delivery pump, a second heat exchanger, a high-temperature molten salt tank, a second delivery pump and a third heat exchanger, wherein, The low-temperature molten salt tank stores fluoride molten salt, and the low-temperature molten salt tank is communicated with the second heat exchanger, and the first delivery pump is arranged on the communication pipeline between the low-temperature molten salt tank and the second heat exchanger; The shunt path is sequentially communicated with the second heat exchanger and the second power generation device; The high-temperature molten salt tank is communicated with the second heat exchanger and the third heat exchanger respectively, and the second delivery 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 for storing the fluoride molten salt in a high-temperature state after heat exchange in the second heat exchanger; The third heat exchanger is communicated with the low-temperature molten salt tank.

6. The nuclear reactor and molten salt energy storage based power generation and waste heat utilization coupled system of claim 5, wherein, Further comprising an energy storage side power generation device, 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 communicated with the third heat exchanger, and the other end of the energy storage side pipeline is communicated with the communication pipeline between the regenerator and the fourth generation nuclear reactor; The third power generation device is respectively communicated with the third heat exchanger and the main flow path, and the supercritical carbon dioxide in the energy storage side pipeline is used for heat exchange with the fluoride molten salt completing heat storage in the third heat exchanger, and the supercritical carbon dioxide after heat exchange is supplied into the third power generation device for driving the third power generation device to generate electricity.

7. The nuclear reactor and molten salt energy storage based power generation and waste heat utilization coupled system of claim 6, wherein, The first power generation device, the second power generation device and the third power generation device all comprise a turbine and a generator, and the turbine is connected with the generator, wherein, The turbine in the first power generation device is connected in series on the main flow path; The turbine in the second power generation device is connected in series on the shunt path; The turbine in the third power generation device is respectively communicated with the third heat exchanger and the main flow path. 8.The nuclear reactor and molten salt energy storage based power generation and waste heat utilization coupled system of claim 1, wherein, A first regulating valve is arranged on the shunt path. 9.The nuclear reactor and molten salt energy storage based power generation and waste heat utilization coupled system of claim 6, wherein, A second regulating valve is arranged on the energy storage side pipeline, and the second regulating valve is arranged near the fourth generation nuclear reactor.

10. The nuclear reactor and molten salt energy storage based power generation and waste heat utilization coupled system of claim 2, further comprising an input pipe, a connecting pipe and an output pipe, wherein, The input pipeline, the absorber, the connecting pipeline, the condenser and the output pipeline are sequentially connected in series.

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