Air-cooled nuclear reactor system for series thermal ionization magnetohydrodynamic power generation

Abstract

The invention relates to the technical field of nuclear reactor design, in particular to an air-cooled nuclear reactor system for series thermal ionization magnetohydrodynamic power generation. Comprising a reactor core which comprises a fuel grid which is formed by a plurality of grid unit plates which are crossed transversely and longitudinally; each grid unit plate is made of sheet-shaped fuel; the thermal ionization magnetohydrodynamic power generation element is arranged outside the reactor core and is used for providing a magnetic field for the fuel grid; the cooling system is used for providing rare gas for the reactor core and is configured to enable the rare gas to exchange heat with the fuel grid and to be converted into conductive fluid in a generated magnetic field, and the conductive fluid flows in the generated magnetic field to generate induced electromotive force so as to realize thermoelectric conversion. While high thermoelectric conversion efficiency is ensured, the engineering feasibility of an air-cooled nuclear reactor system is improved, and the problems that gaseous nuclear fuel is prone to corrode structural materials, prone to leakage and large in aftertreatment difficulty are solved.

Description

Technical Field

[0001] The invention relates to the technical field of nuclear reactor design, and in particular to an air-cooled nuclear reactor system for series thermal ionization magnetic fluid power generation. Background Art

[0002] With the continuous growth of energy demand and the improvement of environmental protection requirements, it is crucial to explore more efficient, safe and environmentally friendly nuclear power generation technology. In the traditional water-cooled reactor power generation mode, there are often harsh thermal hydraulic requirements. For example, the primary and secondary circuits of the pressurized water reactor and the circuit of the boiling water reactor are in a high temperature and high pressure working environment for a long time. Due to the need to maintain a high temperature and high pressure environment, the equipment structure is complex, the engineering cost is high, and there are high safety risks. The design and application of high-temperature gas-cooled nuclear reactor systems is one of the breakthrough points of the traditional water-cooled reactor power generation mode. The high-temperature gas-cooled nuclear reactor system uses gas as a cooling medium to effectively reduce the pressure and temperature inside the reactor, thereby improving the safety and reliability of the system.

[0003] In the 1960s, the academic community proposed a gas-cooled nuclear reactor system with a nuclear reactor in series with a magnetohydrodynamic generator. This system achieves efficient energy conversion by converting the heat energy generated by the nuclear reactor into electrical energy in the magnetohydrodynamic generator. Since the gas-cooled nuclear reactor system with a nuclear reactor in series with a magnetohydrodynamic generator was proposed, most of the related research and theoretical calculations have adopted the design of gaseous cores, such as UF4 and UF6. Although the gaseous core design has certain advantages in theory, it faces many challenges in practical applications. For example, gaseous nuclear fuel is prone to chemical reactions with the structural materials inside the reactor, resulting in corrosion and wear of the structural materials, thereby affecting the life and reliability of the reactor. Gaseous nuclear fuel is also prone to leakage during the flow process, which not only causes environmental pollution, but also may pose a threat to the safety of workers. In addition, the post-processing process of gaseous nuclear fuel is also relatively complicated, and special technologies and equipment are required to separate and recover the useful components in the nuclear fuel. Therefore, for safety reasons, fluid nuclear fuels such as gaseous nuclear fuel lack engineering feasibility in engineering applications.

[0004] Based on this, it is necessary to propose a high conversion efficiency air-cooled nuclear reactor system with a series thermal ionization magnetohydrodynamic power generation. While ensuring that this air-cooled nuclear reactor system has a high thermal-to-electric conversion efficiency, it improves the shortcomings of gaseous nuclear fuel that is easy to corrode structural materials, easy to leak, and difficult to post-process, thereby improving the engineering feasibility of the air-cooled nuclear reactor system with a nuclear reactor in series with a magnetohydrodynamic generator. Summary of the invention

[0005] In order to solve the problems that gaseous nuclear fuel is easy to corrode structural materials, easy to leak, and difficult to post-process, the purpose of the present invention is to provide a high conversion efficiency gas-cooled nuclear reactor system with series thermal ionization magnetic fluid power generation, while ensuring high thermoelectric conversion efficiency, while improving the engineering feasibility of the gas-cooled nuclear reactor system.

[0006] To achieve the above objectives, the technical solution of the present invention is as follows.

[0007] The present invention provides a series-connected hot ionization magnetic fluid power generation gas-cooled nuclear reactor system, comprising:

[0008] The reactor core includes a fuel grid, wherein the fuel grid is formed by a plurality of grid unit plates intersecting horizontally and vertically; each of the grid unit plates is a thin plate-shaped fuel;

[0009] A thermal ionization magnetohydrodynamic power generation element is arranged outside the reactor core and is used to provide a magnetic field to the fuel grid;

[0010] A cooling system for supplying rare gas to the reactor core, configured so that the rare gas exchanges heat with the fuel grid and is converted into a conductive fluid in the magnetic field generated by the thermal ionization magnetofluid power generation element. The conductive fluid flows in the magnetic field generated by the thermal ionization magnetofluid power generation element to generate an induced electromotive force to achieve thermoelectric conversion.

[0011] Preferably, the thin plate fuel is UO2 thin plate nuclear fuel.

[0012] The present invention uses a fuel grid formed by UO2 thin plate fuels crossing horizontally and vertically as a solid nuclear fission reactor core to replace the existing gaseous nuclear fuel; at the same time, the nuclear reactor core and the magnetohydrodynamic generator are designed as an integrated whole, so that the rare gas passes through the core and the magnetohydrodynamic power generation element is thermally ionized to achieve thermoelectric conversion. The system structure of the present invention adopts an integrated design, which reduces the overall volume and can maintain a high thermoelectric conversion efficiency, thereby improving the engineering feasibility of the gas-cooled nuclear reactor system of the nuclear reactor connected in series with the magnetohydrodynamic generator.

[0013] Preferably, the thickness of the thin sheet fuel is 0.05mm-0.3mm, and the spacing between two adjacent parallel thin sheet fuels is 0.5mm-3mm. More preferably, the thickness of the thin sheet fuel is 0.1mm-0.2mm, and the spacing between two adjacent parallel thin sheet fuels is 1mm-1.5mm. More preferably, the thickness of the thin sheet fuel is 0.2mm, and the spacing between two adjacent parallel thin sheet fuels is 1mm.

[0014] In the present invention, the dimensional design of the thin plate fuel thickness of 0.2mm and the spacing between two adjacent parallel thin plate fuels of 1mm has certain advantages in terms of heat exchange efficiency, flow resistance and structural compactness. Among them, the 0.2mm thin plate fuel can respond to temperature changes more quickly, making it easier for heat to be transferred between the plates; if the thickness of the thin plate fuel is too large, it is easy for the temperature in the central area of ​​the thin plate fuel to be too high, which makes the thin plate fuel melt during operation and is not conducive to the heat exchange between the thin plate fuel and the rare gas. The 1mm spacing of the thin plate fuel allows the coolant to flow smoothly between the plates on the basis of reducing the overall volume, reducing flow resistance and improving cooling efficiency; while too large a spacing may cause the coolant to form eddies or uneven flow when flowing between the plates, increase flow resistance and reduce cooling efficiency; too small a spacing may easily cause impurities or particulate matter in the coolant to accumulate between the plates, causing a risk of blockage.

[0015] Preferably, the fuel grid has a plurality of channels; the rare gas flows along the plurality of channels. The fuel grid formed by the UO2 thin plate fuel crossing horizontally and vertically avoids the shortcomings of the gas nuclear fuel design, such as easy corrosion of structural materials, easy leakage, and difficulty in post-processing. By designing a suitable size, it helps the smooth flow of the coolant, realizes heat exchange between the coolant and the fuel grid, and also helps thermoelectric conversion.

[0016] Preferably, the reactor core has a first end and a second end, the first end is configured as a gas inlet, and the second end is configured as a gas outlet.

[0017] Further preferably, the noble gas is argon; the flow rate of the noble gas at the gas inlet is 60 m / s. Subsequent test results show that when the noble gas inlet velocity is 60 m / s and the core power density is 10 MW / m 3 Under the condition of , the total power of the system reached 3.57MW, and the system's thermal-electric conversion efficiency reached 14.64%. This ensures that the air-cooled nuclear reactor system has a high thermal-electric conversion efficiency, while improving the shortcomings of gaseous fuel in the air-cooled nuclear reactor system, such as easy corrosion of structural materials, easy leakage, and difficulty in post-processing, and improving the engineering feasibility of the air-cooled nuclear reactor system with a nuclear reactor in series with a magnetohydrodynamic generator.

[0018] Preferably, the thermal ionization magnetohydrodynamic power generation element is a thermal ionization Hall magnetohydrodynamic generator. According to literature research, the Hall parameter β of the plasma in the gas-cooled nuclear reactor system is relatively large, so the thermal ionization Hall magnetohydrodynamic generator is selected.

[0019] Preferably, the thermal ionization magnetohydrodynamic power generation element includes two electrode plates, which are respectively arranged on both sides of the reactor core; each of the electrode plates has multiple insulating layers to form multiple magnetic field zones in the reactor core. A magnetic field zone is formed between the two electrode plates arranged opposite to each other, thereby, the electrode plates are separated into multiple sections by multiple insulating layers, so that multiple magnetic field zones can be formed in the reactor core.

[0020] In the present invention, the setting of multiple magnetic field zones can make the magnetic fluid power generation process more stable, and can also disperse the influence of the magnetic field on the electrode plate, which helps to extend the service life of the electrode plate. For example, when the conductive fluid in a certain magnetic field zone is disturbed or fluctuated, the conductive fluid in other magnetic field zones can still perform the power generation process normally, thereby maintaining the stability of the entire system.

[0021] Further preferably, the electrode plate is made of conductive material.

[0022] Further preferably, the insulating layer is made of insulating material.

[0023] Beneficial effects of the present invention:

[0024] 1. The present invention utilizes a fuel grid formed by the cross-section and vertical intersection of UO2 thin plate fuel and connects it in series with a thermal ionization magnetohydrodynamic generator to form a high conversion efficiency gas-cooled nuclear reactor system. On the basis of maintaining a high thermal-electric conversion efficiency, the present invention improves the shortcomings of the gas nuclear fuel design in the previous gas-cooled nuclear reactor system of the nuclear reactor connected in series with the magnetohydrodynamic generator, such as easy corrosion of structural materials, easy leakage, and great difficulty in post-processing, thereby improving the engineering feasibility of the gas-cooled nuclear reactor system of the nuclear reactor connected in series with the magnetohydrodynamic generator. BRIEF DESCRIPTION OF THE DRAWINGS

[0025] Figure 1 A schematic structural diagram of an air-cooled nuclear reactor system for series thermal ionization magnetic fluid power generation provided in one embodiment of the present invention.

[0026] Figure 2 A schematic structural diagram of a reactor core provided in accordance with one embodiment of the present invention.

[0027] Figure 3 for Figure 2 A partial enlarged schematic diagram of the reactor core along a cross-section perpendicular to the direction of rare gas flow.

[0028] Figure 4 The power and efficiency curves of the gas-cooled nuclear reactor system at different initial speeds.

[0029] In the figure, 1, reactor core; 11, fuel grid; 12, grid unit plate; 13, first end; 14, second end; 2, thermal ionization magnetohydrodynamic power generation element; 21, electrode plate; 22, insulation layer; 3, protective shell. DETAILED DESCRIPTION

[0030] In order to make the purpose, technical solution and advantages of the present invention more clearly understood, the present invention is further described in detail below in conjunction with the embodiments. It should be understood that the specific embodiments described herein are only used to explain the present invention and are not used to limit the present invention.

[0031] Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without making any creative work shall fall within the scope of protection of the present invention.

[0032] Since the gas-cooled nuclear reactor system with a nuclear reactor in series with a magnetohydrodynamic generator was proposed, most of the related research and theoretical calculations have adopted the design of a gaseous core. Gaseous nuclear fuel has the characteristics of easily corroded structural materials, easy leakage, and difficult post-processing. For safety reasons, gaseous nuclear fuel and other fluid nuclear fuels lack engineering feasibility in engineering applications. Replacing the gaseous core with a fuel grid made of UO2 thin plate fuels crossed horizontally and vertically can ensure that this gas-cooled nuclear reactor system has a high thermoelectric conversion efficiency while improving the shortcomings of gaseous nuclear fuels, such as easily corroded structural materials, easy leakage, and difficult post-processing.

[0033] Based on this, the present invention proposes a high conversion efficiency gas-cooled nuclear reactor system in series with thermal ionization magnetohydrodynamic power generation. The present invention mainly utilizes a fuel grid formed by the cross-section and vertical section of UO2 thin plate fuel in series with a thermal ionization magnetohydrodynamic generator to form a high conversion efficiency gas-cooled nuclear reactor system. On the basis of maintaining high thermal-electric conversion efficiency, the present invention improves the shortcomings of the gas nuclear fuel design in the gas-cooled nuclear reactor system in which the nuclear reactor is connected in series with the magnetohydrodynamic generator, such as easy corrosion of structural materials, easy leakage, and great difficulty in post-processing, thereby improving the engineering feasibility of the gas-cooled nuclear reactor system in which the nuclear reactor is connected in series with the magnetohydrodynamic generator.

[0034] like Figure 1 , a gas-cooled nuclear reactor system for series thermal ionization magnetofluid power generation, comprising a reactor core 1, a thermal ionization magnetofluid power generation element 2 and a cooling system.

[0035] The reactor core 1 includes a fuel grid 11, which is formed by a plurality of grid unit plates 12 intersecting horizontally and vertically; each grid unit plate 12 is a thin plate fuel. Preferably, the thin plate fuel is UO2 thin plate nuclear fuel; the fuel grid 11 has a total volume of 2×1.9992×1.9992m 3 The UO2 fuel grid.

[0036] In one embodiment of the present invention, the thickness of the thin plate fuel is 0.2 mm, and the spacing between two adjacent parallel thin plate fuels is 1 mm. The 0.2 mm thick UO2 thin plate nuclear fuel is assembled horizontally and vertically with a plate spacing of 1 mm to form 2*1.9998*1.9998m 3 The fuel grid is formed into a solid nuclear fission reactor core, which improves the inherent problems of easy corrosion of structural materials, easy leakage and difficult post-processing in the gas-cooled nuclear reactor system with gaseous nuclear fuel as the core.

[0037] In the present invention, the dimensional design of the thin plate fuel thickness of 0.2mm and the spacing between two adjacent parallel thin plate fuels of 1mm has certain advantages in terms of heat exchange efficiency, flow resistance and structural compactness. Among them, the 0.2mm thin plate fuel can respond to temperature changes more quickly, making it easier for heat to be transferred between the plates; if the thickness of the thin plate fuel is too large, it is easy for the temperature in the central area of ​​the thin plate fuel to be too high, which makes the thin plate fuel melt during operation and is not conducive to the heat exchange between the thin plate fuel and the rare gas. The 1mm spacing of the thin plate fuel allows the coolant to flow smoothly between the plates on the basis of reducing the overall volume, reducing flow resistance and improving cooling efficiency; while too large a spacing may cause the coolant to form eddies or uneven flow when flowing between the plates, increase flow resistance and reduce cooling efficiency; too small a spacing may easily cause impurities or particulate matter in the coolant to accumulate between the plates, causing a risk of blockage.

[0038] The thermal ionization magnetofluid power generation element 2 is arranged outside the reactor core 1 and is used to provide a magnetic field to the fuel grid 11. In the embodiment of the present invention, a fuel grid formed by the cross-section of UO2 thin plate fuel is used as a solid nuclear fission reactor core to replace the existing gaseous nuclear fuel; at the same time, the nuclear reactor core and the magnetofluid generator are designed as an integrated whole, so that the rare gas passes through the core and realizes thermoelectric conversion through the thermal ionization magnetofluid power generation element. The system structure of the present invention adopts an integrated design to reduce the overall volume, and can maintain a high thermoelectric conversion efficiency, thereby improving the engineering feasibility of the gas-cooled nuclear reactor system in which the nuclear reactor is connected in series with the magnetofluid generator. Preferably, the thermal ionization magnetofluid power generation element 2 is a thermal ionization Hall magnetofluid generator. According to literature research, the Hall parameter β of the plasma in the gas-cooled nuclear reactor system is relatively large, so a thermal ionization Hall magnetofluid generator is selected. It is mainly a device that generates electricity by using the induced electromotive force generated when a conductive fluid, such as a heated rare gas, flows in a magnetic field. When the heated rare gas passes through the magnetic field, the ions in the rare gas are deflected by the Lorentz force, thereby generating a potential difference at both ends of the conductive fluid, which is the induced electromotive force. This can drive the current in the external circuit and realize thermoelectric conversion.

[0039] The cooling system is used to provide a rare gas to the reactor core 1, and is configured so that the rare gas exchanges heat with the fuel grid 11 and is converted into a conductive fluid in the magnetic field generated by the thermal ionization magnetofluid power generation element 2. The conductive fluid flows in the magnetic field generated by the thermal ionization magnetofluid power generation element 2 to generate an induced electromotive force to achieve thermoelectric conversion. Preferably, the rare gas is argon.

[0040] The specific principle is: the cooling system is designed to provide rare gases to the reactor core 1. When these rare gases flow through the reactor core 1, they exchange heat with the fuel grid 11, thereby absorbing the heat generated by the reactor core 1 and being heated. When the heated rare gases reach a sufficiently high temperature, they undergo thermal ionization in a specific area inside or near the thermal ionization magnetofluid power generation element 2 and are transformed into a conductive fluid, that is, plasma. Subsequently, the conductive fluid flows in the strong magnetic field generated by the thermal ionization magnetofluid power generation element 2. Under the action of the magnetic field, the charged particles in the conductive fluid, such as ions and electrons, are affected by the Lorentz force and move along a specific path. The interaction between this movement and the magnetic field leads to the occurrence of electromagnetic induction, which in turn generates an induced electromotive force in the circuit of the thermal ionization magnetofluid power generation element 2. Finally, by collecting and utilizing the generated induced electromotive force, the purpose of converting the thermal energy generated by the reactor core into electrical energy is achieved, that is, the thermoelectric conversion process is completed.

[0041] In one embodiment of the present invention, by designing the geometric structure of the nuclear reactor core and selecting the type of magnetohydrodynamic generator, the nuclear reactor core and the magnetohydrodynamic generator are integrated into one design, so that the rare gas passes through the core and the magnetohydrodynamic power generation element 2 is thermally ionized to achieve thermoelectric conversion.

[0042] Preferably, the fuel grid 11 has a plurality of channels; the rare gas flows along the plurality of channels. The fuel grid formed by the UO2 thin plate fuel crossing horizontally and vertically avoids the shortcomings of the gas nuclear fuel design, such as easy corrosion of structural materials, easy leakage, and difficulty in post-processing. By designing a suitable size, it helps the smooth flow of the coolant, realizes heat exchange between the coolant and the fuel grid, and also helps thermoelectric conversion.

[0043] Preferably, the reactor core 1 has a first end 13 and a second end 14, the first end 13 is configured as a gas inlet, and the second end 14 is configured as a gas outlet. Preferably, the flow rate of the noble gas at the gas inlet is 60 m / s. Subsequent test results show that when the noble gas inlet velocity is 60 m / s and the core power density is 10 MW / m 3Under the conditions of , the total power of the system reached 3.57MW, and the thermoelectric conversion efficiency of the system reached 14.64%. Thus, while ensuring that this air-cooled nuclear reactor system has a high thermoelectric conversion efficiency, it improves the shortcomings of gaseous fuel in the air-cooled nuclear reactor system, such as easy corrosion of structural materials, easy leakage, and difficulty in post-processing, and improves the engineering feasibility of the air-cooled nuclear reactor system with a nuclear reactor in series with a magnetohydrodynamic generator. Thus, the rare gas Ar is pumped into the reactor core, enters the corresponding channel along the gas inlet, flows along the channel, and is then discharged from the gas outlet. In this process, while the rare gas exchanges heat with the reactor core in the channel, it cuts the magnetic flux lines in the thermal ionization magnetohydrodynamic power generation element 2 to achieve thermoelectric conversion.

[0044] Preferably, the thermal ionization magnetohydrodynamic power generation element 2 includes two electrode plates 21, and the two electrode plates 21 are respectively arranged on both sides of the reactor core 1; each electrode plate 21 has a plurality of insulating layers 22 to form a plurality of magnetic field zones in the reactor core 1. The magnetohydrodynamic generator pole plates, insulating layers and magnets are arranged on the periphery of the fuel grid according to the pole plate connection method of the Hall generator. Preferably, the electrode plate 21 is made of a conductive material, and the conductive material can be copper, silver, gold or alloys thereof, such as copper-silver alloy, copper-nickel alloy, etc.; the insulating layer 22 is made of an insulating material, and the insulating material can be ceramic materials such as aluminum oxide and silicon nitride. Suitable conductive materials and insulating materials can be selected according to actual needs.

[0045] Preferably, the flow rate of the rare gas at the gas inlet is 60 m / s.

[0046] In order to explore the power and efficiency of the system at different initial velocities, the initial velocity of the noble gas entering the reactor core was set at 10m / s to 60m / s, specifically 10m / s, 20m / s, 30m / s, 40m / s, 50m / s, and 60m / s. The results are shown in Tables 1 and Figure 3 .

[0047] Table 1 Power and efficiency of the system at different initial speeds

[0048] V / m / s Power P / MW Efficiency η / % 10 0.71809 2.94 20 0.34658 1.42 30 0.35756 1.46 40 0.32691 1.34 50 1.1683 4.78 60 3.5764 14.64

[0049] The numerical simulation results show that when the inlet velocity of the noble gas Ar is 60m / s, the maximum temperature of the noble gas Ar in the core is 1650K, the maximum pressure is 5atm, and the maximum speed is 500m / s. The maximum temperature is lower than the melting point of UO2, and the maximum pressure is much lower than the gas loop pressure in the gas-cooled nuclear reactor system with gaseous nuclear fuel as the core. Substituting the numerical simulation results into the thermal ionization Hall magnetohydrodynamic generator power calculation model, the results are as follows Figure 2 And as shown in Table 1.

[0050] The power calculation model of the thermal ionization Hall magnetohydrodynamic generator is established based on the distribution function of the gas temperature, density, velocity, and pressure in the core and the power calculation formula of the Hall generator. The specific model construction method is the existing technology, which is integrated based on the following literature:

[0051] Document 1: Chen F F. Introduction to PlasmaPhysics and Controlled Fusion[M]. Switzerland: Springer International Publishing, 2016, 5-169.

[0052] Reference 2: Liu Jianmin. Magnetohydrodynamic generator [M]. Beijing: Mechanical Engineering Press, 1984, 154-165.

[0053] Calculation results show that under the conditions of a rare gas inlet velocity of 60m / s and a core power density of 10MW / s, the total power of the system reaches 3.57MW and the thermoelectric conversion efficiency of the system reaches 14.64%.

[0054] The above results show that by replacing the gaseous fuel with a fuel grid made of UO2 thin plate fuels crossed horizontally and vertically, the high thermoelectric conversion efficiency of this gas-cooled nuclear reactor system can be ensured while improving the shortcomings of the gaseous fuel in the gas-cooled nuclear reactor system, such as easy corrosion of structural materials, easy leakage, and difficulty in post-processing.

[0055] The above are only preferred embodiments of the present invention and are not intended to limit the present invention. Any modifications, equivalent substitutions and improvements made within the spirit and principles of the present invention should be included in the protection scope of the present invention.

Claims

1. A series-connected hot ionization magnetic fluid power generation gas-cooled nuclear reactor system, characterized in that: include: A reactor core (1) comprises a fuel grid (11), wherein the fuel grid (11) is formed by a plurality of grid unit plates (12) intersecting horizontally and vertically; each of the grid unit plates (12) is a thin plate-shaped fuel; A thermal ionization magnetohydrodynamic power generation element (2) is arranged outside the reactor core (1) and is used to provide a magnetic field to the fuel grid (11); A cooling system is used to supply rare gas to the reactor core (1), and is configured so that the rare gas exchanges heat with the fuel grid (11) and is converted into a conductive fluid in the magnetic field generated by the thermal ionization magnetofluid power generation element (2). The conductive fluid flows in the magnetic field generated by the thermal ionization magnetofluid power generation element (2) to generate an induced electromotive force to achieve thermoelectric conversion.

2. The air-cooled nuclear reactor system for series thermal ionization magnetic fluid power generation according to claim 1 is characterized in that: The thin plate fuel is UO2 thin plate nuclear fuel.

3. The air-cooled nuclear reactor system for series thermal ionization magnetic fluid power generation according to claim 1 is characterized in that: The thickness of the thin plate fuel is 0.05 mm to 0.3 mm; The distance between two adjacent parallel thin-plate fuels is 0.5 mm to 3 mm.

4. The air-cooled nuclear reactor system for series thermal ionization magnetic fluid power generation according to claim 1, characterized in that: The fuel grid (11) has a plurality of channels; the rare gas flows along the plurality of channels.

5. The air-cooled nuclear reactor system for series thermal ionization magnetic fluid power generation according to claim 1, characterized in that: The reactor core (1) has a first end (13) and a second end (14), wherein the first end (13) is configured as a gas inlet and the second end (14) is configured as a gas outlet.

6. The air-cooled nuclear reactor system for series thermal ionization magnetic fluid power generation according to claim 5, characterized in that: The rare gas is argon; the flow rate of the rare gas at the gas inlet is 60 m / s.

7. The air-cooled nuclear reactor system for series thermal ionization magnetic fluid power generation according to claim 1, characterized in that: The thermal ionization magnetofluid power generation element (2) is a thermal ionization Hall magnetofluid generator.

8. The air-cooled nuclear reactor system for series thermal ionization magnetic fluid power generation according to claim 1, characterized in that: The thermal ionization magnetic fluid power generation element (2) comprises two electrode plates (21), and the two electrode plates (21) are respectively arranged on both sides of the reactor core (1); Each of the electrode plates (21) has a plurality of insulating layers (22) thereon, so as to form a plurality of magnetic field regions in the reactor core (1).

9. The air-cooled nuclear reactor system for series thermal ionization magnetic fluid power generation according to claim 8, characterized in that: The electrode plate (21) is made of conductive material.

10. The air-cooled nuclear reactor system for series thermal ionization magnetic fluid power generation according to claim 8, characterized in that: The insulating layer (22) is made of insulating material.

Images