Advanced high-temperature reactor coupling Brayton cycle power generation system

Abstract

The invention belongs to the technical field of nuclear energy power generation, and discloses an advanced high-temperature reactor coupled Brayton cycle power generation system which comprises an advanced high-temperature reactor subsystem and a Brayton cycle subsystem, the advanced high-temperature reactor subsystem comprises an advanced high-temperature reactor, the outlet temperature of helium is 750-1000 DEG C, and the outlet temperature of nitrogen is 750-1000 DEG C; the Brayton cycle subsystem comprises a compression device, a heat regeneration device, a turbine device and a cooling device, the temperature of carbon dioxide fluid at an inlet of the turbine device is 500-700 DEG C, the optimal operation state of the Brayton cycle subsystem can be achieved, the heat-work conversion efficiency is improved, and even if carbon dioxide enters a reactor core of an advanced high-temperature reactor due to leakage of a heat exchanger, the carbon dioxide can be recycled. And moreover, the supercritical fluid does not generate phase change in the heat exchanger, so that the operation safety is improved.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of nuclear power generation, in particular to an advanced high temperature reactor coupled with a Brayton cycle power generation system. BACKGROUND

[0002] The advanced high temperature reactor is a general term of the pebble-bed modular high temperature gas-cooled reactor, the prismatic modular high temperature gas-cooled reactor and the very high temperature reactor. The advanced high temperature reactor is an advanced nuclear reactor with inherent safety characteristics, which uses graphite as a moderator, helium as a coolant, adopts a ceramic core structure and full ceramic coated particle fuel elements. The advanced high temperature reactor can be applied to a wide range of fields such as nuclear heat high-temperature hydrogen production, coal-fired unit replacement, cogeneration, petroleum and chemical industry, coal chemical industry, heavy oil thermal recovery, oil shale refining, seawater desalination and regional heating for urban residents.

[0003] The current advanced high temperature reactor is often coupled with a steam Rankine cycle system, which uses the coolant of the advanced high temperature reactor to provide heat source for the steam Rankine cycle system to realize power generation. However, the heat power conversion rate of the advanced high temperature reactor coupled with the steam Rankine cycle system is low, and there are many defects. On the one hand, the occupation area is wide, resulting in high cost and operation cost. On the other hand, if the heat transfer pipe of the steam generator leaks or breaks, the in-vessel components of the nuclear reactor and the graphite of the nuclear fuel will be corroded by the steam, which is low in operation safety. SUMMARY

[0004] The purpose of the present application is to provide an advanced high temperature reactor coupled with a Brayton cycle power generation system, which can improve the operation safety and the heat power conversion efficiency.

[0005] To achieve this purpose, the present application adopts the following technical solutions:

[0006] An advanced high temperature reactor coupled with a Brayton cycle power generation system, comprising:

[0007] An advanced high temperature reactor subsystem, which comprises an advanced high temperature reactor and at least one heat exchanger, the coolant outlet of the advanced high temperature reactor is connected with the first inlet of the heat exchanger, the first outlet of the heat exchanger is connected with the coolant inlet of the advanced high temperature reactor, and the outlet temperature of the helium is 750-1000℃;

[0008] The Brayton cycle subsystem has an internal working medium of carbon dioxide fluid, and comprises a compression device, a regenerative device, a turbine device and a cooling device. The outlet of the compression device, the low-temperature inlet of the regenerative device, the second inlet of the heat exchanger and the inlet of the turbine device are sequentially communicated, and the temperature of the carbon dioxide fluid at the inlet of the turbine device is 500-700℃. The outlet of the turbine device, the high-temperature inlet of the regenerative device, the inlet of the cooling device and the inlet of the compression device are sequentially communicated. The compression device pressurizes the carbon dioxide fluid into a high-pressure fluid, the regenerative device preheats the high-pressure fluid into a supercritical fluid, the heat exchanger heats the supercritical fluid, the supercritical fluid enters the turbine device to do work, the exhaust steam enters the regenerative device to preheat the high-pressure fluid, and the cooling device is configured to liquefy the exhaust steam into carbon dioxide fluid.

[0009] Preferably, the compression device comprises a main compressor and a re-compressor, the regenerative device comprises a low-temperature regenerator and a high-temperature regenerator, the outlet of the cooling device is communicated with the inlet of the main compressor, the outlet of the main compressor is communicated with the low-temperature inlet of the low-temperature regenerator, the low-temperature outlet of the low-temperature regenerator, the low-temperature inlet of the high-temperature regenerator and the second inlet of the heat exchanger are sequentially communicated, the second outlet of the heat exchanger is communicated with the inlet of the turbine device, the outlet of the turbine device, the high-temperature inlet of the high-temperature regenerator and the high-temperature inlet of the low-temperature regenerator are sequentially communicated, and the low-temperature outlet of the low-temperature regenerator is divided into two streams, one of which is communicated with the low-temperature inlet of the high-temperature regenerator, and the other of which is communicated with the inlet of the re-compressor. The outlet of the re-compressor is communicated with the low-temperature inlet of the high-temperature regenerator.

[0010] Preferably, the turbine device comprises a power generation turbine and a drag turbine, the second outlet of the heat exchanger is communicated with the inlet of the power generation turbine and the inlet of the drag turbine respectively, and the outlet of the power generation turbine and the outlet of the drag turbine are both communicated with the high-temperature inlet of the high-temperature regenerator.

[0011] Preferably, the Brayton cycle subsystem further comprises a generator and a magnetic suspension bearing, the rotor of the generator is coaxially connected to the rotor of the power generation turbine, and the magnetic suspension bearing is configured to support the rotor of the generator and the rotor of the power generation turbine.

[0012] Preferably, the cooling device comprises an air cooler configured to provide cold air to cool the carbon dioxide fluid, or

[0013] The cooling device comprises a water cooling structure configured to provide seawater to cool the carbon dioxide fluid.

[0014] As preferred, the low-temperature recuperator and the high-temperature recuperator are both printed circuit board heat exchangers.

[0015] As preferred, the main compressor is a centrifugal compressor, the temperature of the carbon dioxide fluid at the inlet of the main compressor is not less than 30℃; the re-compressor is a multi-stage axial flow re-compressor, the temperature of the carbon dioxide fluid at the inlet of the re-compressor is not less than 80℃.

[0016] As preferred, the heat exchanger is a tube heat exchanger, the helium gas flows in the heat transfer tube of the tube heat exchanger, the heat transfer tube is made of nickel-iron-chromium alloy;

[0017] Alternatively, the heat exchanger is a PCHE heat exchanger, the helium gas flows in the PCHE microchannel of the PCHE heat exchanger, the metal material forming the PCHE microchannel is made of nickel-iron-chromium alloy.

[0018] As preferred, the advanced high-temperature reactor subsystem further comprises at least one main helium blower, the main helium blower corresponds to the heat exchanger one by one, and the main helium blower is arranged between the coolant inlet of the advanced high-temperature reactor and the first outlet of the heat exchanger, and is configured to drive the helium gas to flow.

[0019] As preferred, 1-6 advanced high-temperature reactor subsystems and 1-6 Brayton cycle subsystems are included, the advanced high-temperature reactor subsystems are installed in the same nuclear safety class nuclear reactor plant, and the Brayton cycle subsystems are installed in the same non-nuclear safety class auxiliary plant.

[0020] The beneficial effects of the present application are as follows:

[0021] This invention provides an advanced high-temperature reactor coupled with a Brayton cycle power generation system, comprising an advanced high-temperature reactor subsystem and a Brayton cycle subsystem. The advanced high-temperature reactor subsystem includes an advanced high-temperature reactor and at least one heat exchanger. The coolant outlet of the advanced high-temperature reactor is connected to the first inlet of the heat exchanger, and the first outlet of the heat exchanger is connected to the coolant inlet of the advanced high-temperature reactor. The helium outlet temperature is 750-1000℃. The Brayton cycle subsystem includes a compression unit, a regeneration unit, a turbine unit, and a cooling unit. The outlet of the compression unit, the low-temperature inlet of the regeneration unit, the second inlet of the heat exchanger, and the inlet of the turbine unit are sequentially connected. The temperature of the carbon dioxide fluid at the inlet of the turbine unit is 500-700℃. The outlet of the turbine unit, the high-temperature inlet of the regeneration unit, the inlet of the cooling unit, and the inlet of the compression unit are sequentially connected. The compression unit pressurizes the carbon dioxide fluid... The invention utilizes a regenerator to preheat the high-pressure fluid into a supercritical fluid, a heat exchanger to heat the supercritical fluid, and the supercritical fluid to perform work in a turbine. Exhaust steam enters the regenerator to preheat the high-pressure fluid, and a cooling device is used to liquefy the exhaust steam into carbon dioxide. This invention can maintain the inlet temperature of the carbon dioxide-driven power generation system at 650°C, thereby achieving the optimal operating state of the Brayton cycle subsystem and significantly improving the heat-to-work conversion efficiency. Even if a leak occurs in the heat exchanger, causing carbon dioxide to enter the core of the advanced high-temperature reactor, it will not lead to corrosion of the reactor internals or the graphite of the nuclear fuel, thus improving safety performance. The supercritical fluid does not undergo a phase change during heat exchange with helium in the heat exchanger, thereby reducing heat transfer losses and avoiding risks such as flow instability that may result from liquid-gas phase changes, further improving heat-to-work conversion efficiency and operational safety. Attached Figure Description

[0022] Figure 1 This is a schematic diagram of an advanced high-temperature reactor-coupled Brayton cycle power generation system provided in an embodiment of the present invention;

[0023] Figure 2 This is a temperature entropy diagram of carbon dioxide fluid during the operation of the Brayton cycle subsystem provided in this embodiment of the invention.

[0024] In the picture:

[0025] 1. Advanced High Temperature Reactor Subsystem; 11. Advanced High Temperature Reactor; 111. Coolant Outlet; 112. Coolant Inlet; 12. Heat Exchanger; 121. First Inlet; 122. First Outlet; 123. Second Inlet; 124. Second Outlet; 13. Main Helium Blower; 2. Brayton Cycle Subsystem; 21. Compression Unit; 211. Main Compressor; 212. Recompressor; 22. Regenerator; 221. Cryogenic Regenerator; 222. High Temperature Regenerator; 23. Turbine Unit; 231. Power Generation Turbine; 232. Drive Turbine; 233. Generator; 24. Cooling Unit. DETAILED DESCRIPTION

[0026] The application will be further described below in conjunction with the drawings and embodiments. It should be understood that the specific embodiments described herein are intended to be merely illustrative of the application and not in limitation thereof. It should also be understood that, for the purpose of clarity, only those structures of the application that are relevant to the present application have been shown in the drawings.

[0027] In the description of the present application, unless otherwise explicitly specified and limited, the terms "connected", "connected", "fixed" should be understood broadly, for example, it can be fixedly connected, or detachably connected, or integrated; it can be mechanically connected, or electrically connected; it can be directly connected, or indirectly connected through an intermediate medium, or it can be the internal communication of two elements or the interaction relationship between two elements. For those skilled in the art, the specific meaning of the above terms in the present application can be understood according to the specific circumstances.

[0028] In the present application, unless otherwise explicitly specified and limited, the first feature "on" or "under" the second feature can include that the first and second features are in direct contact, or that the first and second features are not in direct contact but are in contact through another feature between them. Moreover, the first feature "on", "above" and "above" the second feature includes that the first feature is directly above and obliquely above the second feature, or only indicates that the horizontal height of the first feature is higher than that of the second feature. The first feature "under", "below" and "below" the second feature includes that the first feature is directly below and obliquely below the second feature, or only indicates that the horizontal height of the first feature is less than that of the second feature.

[0029] In the description of the present embodiment, the terms "up", "down", "right", and other orientation or position relationships are based on the orientation or position relationship shown in the drawings, and are only for the purpose of description and simplification of operation, and do not indicate or imply that the device or element referred to must have a particular orientation, be constructed and operated in a particular orientation, and therefore cannot be understood as a limitation on the present application. In addition, the terms "first" and "second" are only used to distinguish in the description and have no special meaning.

[0030] The present embodiment provides an advanced high temperature reactor coupled with a Brayton cycle power generation system, which improves the operation safety and stability, and greatly improves the thermal power conversion efficiency.

[0031] Please refer to Figure 1The advanced high temperature reactor coupled with the Brayton cycle power generation system comprises an advanced high temperature reactor subsystem 1 and a Brayton cycle subsystem 2, the coolant of the advanced high temperature reactor subsystem 1 is helium, and the internal working medium of the Brayton cycle subsystem 2 is carbon dioxide fluid, the helium is heated by absorbing the internal heat of the advanced high temperature reactor subsystem 1 and serves as the heat source of the Brayton cycle subsystem 2, the carbon dioxide fluid is heated and pressurized to reach a supercritical state, and finally drives power generation.

[0032] The advanced high temperature reactor subsystem 1 in the embodiment adopts graphite as a moderator and helium as a coolant, adopts the HTR-PM and its improved type with a ceramic core structure and full-ceramic coated particle fuel elements, and maintains inherent safety. In addition, the embodiment adopts a single-module nuclear reactor, compared with the current double-module nuclear reactor, the outlet temperature of the coolant helium in the embodiment is 750-1000℃, so that the carbon dioxide fluid in the Brayton cycle subsystem 2 can be heated to 500-700℃, the inlet temperature of the carbon dioxide fluid driving power generation is improved, the heat conversion efficiency is effectively improved, the inlet temperature of the carbon dioxide fluid driving power generation is maintained at 650℃, the optimal operating state of the Brayton cycle subsystem 2 can be reached, the heat conversion efficiency can reach 50%, and the technical economy is greatly improved, which creates conditions for the popularization and application of the HTR-PM and its improved type.

[0033] Further, by setting carbon dioxide as the working medium for transferring heat energy, since the viscosity coefficient of carbon dioxide is close to that of gas, and the density of supercritical carbon dioxide is 1.4 times that of supercritical water, the carbon dioxide has flexible power supply load adjustment performance.

[0034] Specifically, please continue to refer to Figure 1The advanced high temperature reactor subsystem 1 comprises an advanced high temperature reactor 11, at least one heat exchanger 12 and at least one main helium blower 13, the coolant outlet 111 of the advanced high temperature reactor 11 is connected with the first inlet 121 of the heat exchanger 12, the first outlet 122 of the heat exchanger 12 is connected with the coolant inlet 112 of the advanced high temperature reactor 11, the main helium blower 13 corresponds to the heat exchanger 12 one by one, and the main helium blower 13 is arranged between the coolant inlet 112 of the advanced high temperature reactor 11 and the first outlet 122 of the heat exchanger 12. The thermal power of the advanced high temperature reactor 11 is 150-300 MWt, the flow pressure of helium in the core of the advanced high temperature reactor 11 is between 6.0-7.0 MPa, after absorbing the internal heat of the core, the helium enters the first inlet 121 of the heat exchanger 12 through the coolant outlet 111 of the advanced high temperature reactor 11, at this time the temperature of the helium is 750-1000℃, the pressure is between 10.0-15.0 MPa, the helium releases heat in the heat exchanger 12 and then returns to the coolant inlet 112 of the advanced high temperature reactor 11 through the first outlet 122 of the heat exchanger 12, at this time the temperature of the helium is 250-500℃, the pressure is between 6.0-7.0 MPa, and the main helium blower 13 drives the helium to flow from the first inlet 121 of the heat exchanger 12 to the first outlet 122 of the heat exchanger 12 in the process.

[0035] Optionally, the heat exchanger 12 is a tube heat exchanger, and the helium flows in the heat transfer tube of the tube heat exchanger. The heat transfer tube is made of nickel-iron-chromium alloy, which has good high-temperature resistance and corrosion resistance to adapt to the high-temperature helium flowing out of the coolant outlet 111 of the advanced high temperature reactor 11.

[0036] Optionally, the heat exchanger 12 is a PCHE heat exchanger, and the helium flows in the PCHE microchannel of the PCHE heat exchanger. The metal material forming the PCHE microchannel is also made of nickel-iron-chromium alloy, which has good high-temperature resistance and corrosion resistance to adapt to the high-temperature helium flowing out of the coolant outlet 111 of the advanced high temperature reactor 11.

[0037] The advanced high temperature reactor coupled with the Brayton cycle power generation system provided in the embodiment can exchange heat between the helium and the carbon dioxide fluid in the heat exchanger 12. By selecting carbon dioxide as the working medium for transferring heat energy, even if a leakage event occurs in the heat exchanger 12 and the core of the advanced high temperature reactor 11 enters the carbon dioxide, the graphite of the in-core components and the nuclear fuel of the advanced high temperature reactor 11 will not be corroded, and the safety performance is further improved.

[0038] Please continue to refer to Figure 1, the Brayton cycle subsystem 2 comprises a compression device 21, a regenerative device 22, a turbine device 23 and a cooling device 24. Among them, the outlet of the compression device 21, the low-temperature inlet of the regenerative device 22, the second inlet 123 of the heat exchanger 12 and the inlet of the turbine device 23 are sequentially communicated, and the temperature of the carbon dioxide fluid at the inlet of the turbine device 23 is 500-700℃, the outlet of the turbine device 23, the high-temperature inlet of the regenerative device 22, the inlet of the cooling device 24 and the inlet of the compression device 21 are sequentially communicated.

[0039] Through the above setting, the compression device 21 pressurizes the carbon dioxide fluid into a high-pressure fluid, the high-pressure fluid enters the regenerative device 22 and is preheated by the exhaust steam therein into a supercritical fluid, further, the supercritical fluid is heated in the heat exchanger 12, the heated supercritical fluid enters the turbine device 23 to do work, the exhaust steam enters the regenerative device 22 to preheat the high-pressure fluid, and the cooling device 24 is used to liquefy the exhaust steam into carbon dioxide fluid.

[0040] It should be noted that the operating pressure of the carbon dioxide fluid is maintained between 20-26MPa.

[0041] In addition, through the above setting, the carbon dioxide fluid is pressurized by the compression device 21 into a high-pressure fluid, and further preheated by the regenerative device 22 to reach the critical point, the temperature exceeds 31.1℃, and the pressure exceeds 7.39MPa, forming a supercritical fluid. The supercritical fluid does not undergo phase change in the heat exchange process with helium in the heat exchanger 12, thereby reducing heat transfer loss and avoiding the risk of flow instability caused by liquid-gas phase change, improving the operation safety, stability and reliability.

[0042] Preferably, the cooling device 24 comprises an air cooler, which provides cold air to cool and liquefy the carbon dioxide fluid, and can be applied to water-deficient and arid areas; preferably, the cooling device 24 can also comprise a water cooling structure, which provides seawater to cool and liquefy the carbon dioxide fluid, and can be applied to islands.

[0043] For further utilization of heat energy and improvement of heat power conversion efficiency, please continue to refer to Figure 1The embodiment sets the compression device 21 to include a main compressor 211 and a re-compressor 212, the heat recovery device 22 to include a low-temperature heat regenerator 221 and a high-temperature heat regenerator 222, and the outlet of the cooling device 24 to be communicated with the inlet of the main compressor 211. The outlet of the main compressor 211 is communicated with the low-temperature inlet of the low-temperature heat regenerator 221. The low-temperature outlet of the low-temperature heat regenerator 221, the low-temperature inlet of the high-temperature heat regenerator 222 and the second inlet 123 of the heat exchanger 12 are communicated in sequence. The second outlet 124 of the heat exchanger 12 is communicated with the inlet of the turbine device 23. The outlet of the turbine device 23, the high-temperature inlet of the high-temperature heat regenerator 222 and the high-temperature inlet of the low-temperature heat regenerator 221 are communicated in sequence. In addition, the low-temperature outlet of the low-temperature heat regenerator 221 is divided into two streams. One of the two streams is communicated with the low-temperature inlet of the high-temperature heat regenerator 222. The other of the two streams is communicated with the inlet of the re-compressor 212. After being pressurized, the stream is communicated with the low-temperature inlet of the high-temperature heat regenerator 222 through the outlet of the re-compressor 212.

[0044] Through the above setting, the exhaust steam after releasing waste heat is liquefied into carbon dioxide fluid in the cooling device 24, and is pressurized into high-pressure fluid by the main compressor 211. The high-pressure fluid is preheated in the low-temperature heat regenerator 221. The high-pressure fluid preheated by the low-temperature heat regenerator 221 is divided into two streams. One of the two streams is directly preheated in the high-temperature heat regenerator 222. The other of the two streams is further pressurized by the re-compressor 212 and then preheated in the high-temperature heat regenerator 222.

[0045] Optionally, the main compressor 211 is a centrifugal compressor. The temperature of the carbon dioxide fluid at the inlet of the main compressor 211 is not less than 30℃. The re-compressor 212 is a multi-stage axial re-compressor 212. The temperature of the carbon dioxide fluid at the inlet of the re-compressor 212 is not less than 80℃. That is, the carbon dioxide fluid can reach the critical point and form a supercritical fluid after being pressurized by the main compressor 211 and preheated by the low-temperature heat regenerator 221.

[0046] Optionally, the low-temperature heat regenerator 221 and the high-temperature heat regenerator 222 are both printed circuit board heat exchangers, which have high compactness and high high-pressure bearing capacity.

[0047] Further, please continue to refer to Figure 1 The embodiment sets the turbine device 23 to include a power turbine 231 and a drag turbine 232. The second outlet 124 of the heat exchanger 12 is respectively communicated with the inlet of the power turbine 231 and the inlet of the drag turbine 232. The outlet of the power turbine 231 and the outlet of the drag turbine 232 are both communicated with the high-temperature inlet of the high-temperature heat regenerator 222. Through the above setting, the power turbine 231 directly drives heat energy to be converted into electric energy, and the drag turbine 232 drives heat energy to be converted into mechanical energy.

[0048] Further, the Brayton cycle subsystem 2 further comprises a generator 233, the generator 233 and the power generation turbine 231 constitute a direct connection rotor system, the rotor of the generator 233 is directly coaxially connected to the rotor of the power generation turbine 231, the rotor of the power generation turbine 231 can directly drive the rotor of the generator 233 without passing through a complex speed change mechanism, which simplifies the energy transmission path, reduces the energy loss of the intermediate transmission link, and improves the overall energy conversion efficiency.

[0049] Further, the Brayton cycle subsystem 2 further comprises a magnetic suspension bearing, the magnetic suspension bearing is used to support the rotor of the generator 233 and the rotor of the power generation turbine 231, the rotor of the generator 233 and the rotor of the power generation turbine 231 are accurately supported by electromagnetic force, and there is no physical contact between the magnetic suspension bearing and the rotor of the generator 233 and the rotor of the power generation turbine 231 during operation, which reduces the friction loss energy, thereby improving the overall energy conversion efficiency.

[0050] The advanced high temperature reactor coupled Brayton cycle power generation system provided by the embodiment comprises 1-6 advanced high temperature reactor subsystems 1 and 1-6 Brayton cycle subsystems 2, the 1-6 advanced high temperature reactor subsystems 1 are installed in the same nuclear safety level nuclear reactor plant, and the 1-6 Brayton cycle subsystems 2 are installed in the same non-nuclear safety level auxiliary plant, which is compact in arrangement and does not need to be provided with a conventional island, thereby saving the floor area and reducing the cost of the nuclear power plant.

[0051] In addition, it should be noted that the size of the turbine device 23 (steam turbine) of the Brayton cycle power generation system is only 1 / 10-1 / 30 of that of the Rankine cycle power generation system, which further saves the floor area and greatly reduces the cost of the nuclear power plant.

[0052] Please refer to Figure 1 and Figure 2 , Figure 2 The temperature-entropy diagram of the carbon dioxide fluid in the working process of the Brayton cycle subsystem provided by the embodiment can directly show the state change of the carbon dioxide fluid in the working process of the Brayton cycle subsystem 2:

[0053] The node a-b, after being pressurized by the main compressor 211, the temperature of the carbon dioxide fluid is increased, and in actuality, the entropy is increased;

[0054] The node b-c, after being preheated by the low-temperature regenerator 221, the temperature of the carbon dioxide fluid is increased, and the entropy is increased, at this time, the carbon dioxide fluid has reached a supercritical state;

[0055] The node c-d, after being preheated again by the high-temperature regenerator 222, the temperature of the supercritical fluid is increased, and the entropy is increased;

[0056] Node d-e, after the supercritical fluid exchanges heat with the helium in the heat exchanger 12, the temperature can be increased to 500-700℃, and the entropy is increased;

[0057] Node e-f, after the supercritical fluid expands and does work in the power generation turbine 231 and the drag turbine 232, the temperature decreases, and in practice, the entropy increases;

[0058] Node f-g, the exhaust steam enters the high-temperature regenerator 222 to release heat for preheating, the temperature decreases, and the entropy decreases;

[0059] Node g-h, the exhaust steam enters the cooling device 24 to release heat, the temperature decreases, and the entropy decreases.

[0060] The advanced high temperature reactor coupled with the Brayton cycle power generation system provided in the embodiment has the following technical effects:

[0061] The advanced high temperature reactor subsystem 1 in the embodiment uses graphite as a moderator and helium as a coolant, adopts a ceramic core structure, and uses the HTR-PM and its improved version of the full-ceramic coated particle fuel element, thereby maintaining inherent safety;

[0062] The single-module nuclear reactor is adopted in the embodiment, and the outlet temperature of the helium coolant is 750-1000℃, so that the carbon dioxide fluid in the Brayton cycle subsystem 2 can be heated to 500-700℃, the inlet temperature of the carbon dioxide fluid for power generation is increased, the thermal power conversion efficiency is effectively improved, the inlet temperature of the carbon dioxide fluid for power generation is maintained at 650℃, the optimal operating state of the Brayton cycle subsystem 2 is achieved, the thermal power conversion efficiency reaches 50%, and the technical economy is greatly improved, thereby creating conditions for the scale application and popularization of the HTR-PM and its improved version;

[0063] In the embodiment, the carbon dioxide is used as the working medium for transferring heat energy, and the power supply load adjustment performance is flexible. Even if the core of the advanced high temperature reactor 11 enters the carbon dioxide due to a leakage event in the heat exchanger 12, the graphite of the in-core components and the nuclear fuel of the advanced high temperature reactor 11 will not be corroded, and the safety performance is improved;

[0064] In the embodiment, the heat exchange process between the carbon dioxide and the helium in the heat exchanger 12 does not cause phase change, thereby reducing heat transfer loss and avoiding the risk of flow instability caused by liquid-gas phase change, and further improving the operation safety, stability and reliability;

[0065] The embodiment realizes zero carbon emission.

[0066] Obviously, the above embodiments of the present application are merely exemplary but not intended to limit the embodiments of the present application. Various obvious changes, re-adjustments and substitutions can be made by those skilled in the art without departing from the scope of the present application. It is not necessary or possible to enumerate all the embodiments. Any modification, equivalent replacement and improvement made within the spirit and principle of the present application shall be included in the protection scope of the claims of the present application.

Claims

1. An advanced high-temperature reactor-coupled Brayton cycle power generation system, characterized in that, include: An advanced high-temperature reactor subsystem (1) includes an advanced high-temperature reactor (11) and at least one heat exchanger (12). The coolant outlet (111) of the advanced high-temperature reactor (11) is connected to the first inlet (121) of the heat exchanger (12), and the first outlet (122) of the heat exchanger (12) is connected to the coolant inlet (112) of the advanced high-temperature reactor (11). The outlet temperature of helium is 750-1000℃. A Brayton cycle subsystem (2) is provided, wherein the internal working fluid of the Brayton cycle subsystem (2) is carbon dioxide fluid. The Brayton cycle subsystem (2) includes a compression device (21), a regeneration device (22), a turbine device (23), and a cooling device (24). The outlet of the compression device (21), the low-temperature inlet of the regeneration device (22), the second inlet (123) of the heat exchanger (12), and the inlet of the turbine device (23) are connected in sequence. The temperature of the carbon dioxide fluid at the inlet of the turbine device (23) is 500-700°C. The outlet of the device (23), the high-temperature inlet of the regenerating device (22), the inlet of the cooling device (24) and the inlet of the compression device (21) are connected in sequence; the compression device (21) pressurizes the carbon dioxide fluid into a high-pressure fluid, the regenerating device (22) preheats the high-pressure fluid into a supercritical fluid, the heat exchanger (12) heats the supercritical fluid, the supercritical fluid enters the turbine device (23) to do work, the exhaust steam enters the regenerating device (22) to preheat the high-pressure fluid, and the cooling device (24) is configured to liquefy the exhaust steam into a carbon dioxide fluid.

2. The advanced high-temperature reactor-coupled Brayton cycle power generation system according to claim 1, characterized in that, The compression device (21) includes a main compressor (211) and a recompressor (212). The heat recovery device (22) includes a low-temperature regenerator (221) and a high-temperature regenerator (222). The outlet of the cooling device (24) is connected to the inlet of the main compressor (211). The outlet of the main compressor (211) is connected to the low-temperature inlet of the low-temperature regenerator (221). The low-temperature outlet of the low-temperature regenerator (221), the low-temperature inlet of the high-temperature regenerator (222), and the second inlet (123) of the heat exchanger (12) are sequentially connected. The second outlet (124) of the heat exchanger (12) is connected to the inlet of the turbine device (23). The outlet of the turbine device (23), the high-temperature inlet of the high-temperature regenerator (222), and the high-temperature inlet of the low-temperature regenerator (221) are connected in sequence. The low-temperature outlet of the low-temperature regenerator (221) is divided into two streams, one of which is connected to the low-temperature inlet of the high-temperature regenerator (222), and the other is connected to the inlet of the recompressor (212). The outlet of the recompressor (212) is connected to the low-temperature inlet of the high-temperature regenerator (222).

3. The advanced high-temperature reactor-coupled Brayton cycle power generation system according to claim 2, characterized in that, The turbine device (23) includes a power generation turbine (231) and a drive turbine (232). The second outlet (124) of the heat exchanger (12) is connected to the inlet of the power generation turbine (231) and the inlet of the drive turbine (232), respectively. The outlet of the power generation turbine (231) and the outlet of the drive turbine (232) are both connected to the high-temperature inlet of the high-temperature regenerator (222).

4. An advanced high-temperature reactor-coupled Brayton cycle power generation system according to claim 3, characterized in that, The Brayton cycle subsystem (2) further includes a generator (233) and a magnetic bearing, wherein the rotor of the generator (233) is coaxially connected to the rotor of the power generation turbine (231), and the magnetic bearing is configured to support the rotor of the generator (233) and the rotor of the power generation turbine (231).

5. An advanced high-temperature reactor-coupled Brayton cycle power generation system according to any one of claims 1-4, characterized in that, The cooling device (24) includes an air cooler configured to provide cold air to cool the carbon dioxide fluid, or... The cooling device (24) includes a water-cooled structure configured to provide seawater to cool the carbon dioxide fluid.

6. An advanced high-temperature reactor-coupled Brayton cycle power generation system according to any one of claims 2-4, characterized in that, Both the low-temperature regenerator (221) and the high-temperature regenerator (222) are printed circuit board type heat exchangers.

7. An advanced high-temperature reactor-coupled Brayton cycle power generation system according to any one of claims 2-4, characterized in that, The main compressor (211) is a centrifugal compressor, and the temperature of the carbon dioxide fluid at the inlet of the main compressor (211) is not lower than 30°C; the re-compressor (212) is a multi-stage axial flow re-compressor (212), and the temperature of the carbon dioxide fluid at the inlet of the re-compressor (212) is not lower than 80°C.

8. An advanced high-temperature reactor-coupled Brayton cycle power generation system according to any one of claims 1-4, characterized in that, The heat exchanger (12) is a tubular heat exchanger, and the helium gas flows inside the heat transfer tube of the tubular heat exchanger. The heat transfer tube is made of nickel-iron-chromium alloy. Alternatively, the heat exchanger (12) is a PCHE heat exchanger, and the helium gas flows in the PCHE microchannel of the PCHE heat exchanger. The metal material forming the PCHE microchannel is a nickel-iron-chromium alloy.

9. An advanced high-temperature reactor-coupled Brayton cycle power generation system according to any one of claims 1-4, characterized in that, The advanced high temperature reactor subsystem (1) also includes at least one main helium blower (13), which corresponds one-to-one with the heat exchanger (12), and the main helium blower (13) is located between the coolant inlet (112) of the advanced high temperature reactor (11) and the first outlet (122) of the heat exchanger (12), and is configured to drive the flow of helium.

10. An advanced high-temperature reactor-coupled Brayton cycle power generation system according to any one of claims 1-4, characterized in that, It includes 1-6 advanced high temperature reactor subsystems (1) and 1-6 Brayton cycle subsystems (2), wherein the advanced high temperature reactor subsystems (1) are installed in the same nuclear safety grade nuclear reactor building, and the Brayton cycle subsystems (2) are installed in the same non-nuclear safety grade auxiliary building.

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