A gas-cooled nuclear reactor system with series thermal ionization magnetic fluid power generation

Abstract

The present invention relates to the technical field of nuclear reactor design, and specifically to a gas-cooled nuclear reactor system with series thermal ionization magnetofluid power generation. The system comprises: a reactor core, including 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 of fuel; a thermal ionization magnetofluid power generation element, arranged outside the reactor core, for providing a magnetic field to the fuel grid; and a cooling system, for providing a 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 generated magnetic field. The conductive fluid flows in the generated magnetic field, generating an induced electromotive force to achieve thermoelectric conversion. While ensuring high thermoelectric conversion efficiency, the present invention improves the engineering feasibility of the gas-cooled nuclear reactor system and solves the problems of gaseous nuclear fuel being prone to corrosion of structural materials, prone to leakage, and difficult post-processing.

Description

Technical Field

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

[0002] With the continuous growth of energy demand and the increasing requirements for environmental protection, it is crucial to explore more efficient, safe, and environmentally friendly nuclear power generation technologies. In the traditional water-cooled reactor power generation model, there are often stringent 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. The need to maintain a high-temperature and high-pressure environment leads to complex equipment structure, high engineering costs, and high safety risks. The design and application of high-temperature gas-cooled nuclear reactor systems is one of the breakthroughs in the traditional water-cooled reactor power generation model. 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, a gas-cooled nuclear reactor system, combining a nuclear reactor with a magnetohydrodynamic generator (MHDG), was proposed. This system achieves efficient energy conversion by converting the heat generated by the nuclear reactor into electricity in the MHDG. Since its introduction, most related research and theoretical calculations have employed gaseous cores, such as UF4 and UF6. While this gaseous core design offers certain theoretical advantages, it faces numerous challenges in practical application. For example, gaseous nuclear fuel easily reacts chemically with structural materials within the reactor, causing corrosion and wear, thereby impacting the reactor's lifespan and reliability. Gaseous nuclear fuel is also prone to leakage during flow, which not only pollutes the environment but also poses a threat to worker safety. Furthermore, the reprocessing of gaseous nuclear fuel is relatively complex, requiring specialized techniques and equipment to separate and recover the useful components within the fuel. Therefore, due to safety concerns, gaseous nuclear fuel and other liquid nuclear fuels lack engineering feasibility.

[0004] Based on this, it is necessary to propose a high conversion efficiency gas-cooled nuclear reactor system with series thermal ionization magnetohydrodynamic power generation. While ensuring that this gas-cooled nuclear reactor system has high thermal-to-electricity conversion efficiency, it is necessary to improve 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 gas-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 of gaseous nuclear fuel being prone to corrosion of 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 and improving the engineering feasibility of the gas-cooled nuclear reactor system.

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

[0007] The present invention provides a gas-cooled nuclear reactor system for series thermal ionization magnetic fluid power generation, 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 of fuel;

[0009] a thermal ionization magnetohydrodynamic power generation element, disposed outside the reactor core and configured to provide a magnetic field to the fuel grid;

[0010] A cooling system for supplying a 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] This invention utilizes a fuel grid composed of interlaced UO2 thin sheets as a solid-state nuclear fission reactor core, replacing existing gaseous nuclear fuel. The reactor core and magnetohydrodynamic generator are integrated into a single design, allowing rare gas to flow through the core while thermally ionizing the magnetohydrodynamic generator elements, achieving thermoelectric conversion. This integrated system architecture reduces overall volume while maintaining high thermoelectric conversion efficiency, improving the engineering feasibility of a gas-cooled nuclear reactor system combining a nuclear reactor and a magnetohydrodynamic generator.

[0013] Preferably, the thickness of the thin sheet fuel is 0.05mm to 0.3mm, and the spacing between two adjacent parallel thin sheets of fuel is 0.5mm to 3mm. Further preferably, the thickness of the thin sheet fuel is 0.1mm to 0.2mm, and the spacing between two adjacent parallel thin sheets of fuel is 1mm to 1.5mm. Even more preferably, the thickness of the thin sheet fuel is 0.2mm, and the spacing between two adjacent parallel thin sheets of fuel is 1mm.

[0014] In the present invention, the design of a thin-plate fuel with a thickness of 0.2mm and a spacing of 1mm between two adjacent parallel thin-plate fuels has certain advantages in terms of heat exchange efficiency, flow resistance, and structural compactness. Specifically, the 0.2mm thin-plate fuel can respond to temperature changes more quickly, making heat transfer between the plates easier. If the thickness of the thin-plate fuel is too large, the temperature in the center of the thin-plate fuel will easily become too high, which will increase the risk of melting the thin-plate fuel during operation and hinder the heat exchange between the thin-plate fuel and the rare gas. A spacing of 1mm between the thin-plate fuels reduces the overall volume while allowing the coolant to flow smoothly between the plates, reducing flow resistance and improving cooling efficiency. However, a spacing that is too large may cause the coolant to form eddies or uneven flow when flowing between the plates, increasing flow resistance and reducing cooling efficiency. A spacing that is too small may easily cause impurities or particulate matter in the coolant to accumulate between the plates, creating a risk of blockage.

[0015] Preferably, the fuel grid has multiple channels along which the noble gas flows. The fuel grid, formed by the cross-section of UO2 thin-sheet fuel, avoids the drawbacks of gaseous nuclear fuel design, such as the proneness to corrosion of structural materials, leakage, and difficulty in post-processing. Furthermore, through appropriate design dimensions, it facilitates the smooth flow of coolant, enabling heat exchange between the coolant and the fuel grid while also facilitating 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 these conditions, the system's total power reached 3.57MW, and its thermal-to-electric conversion efficiency reached 14.64%. This ensured the high thermal-to-electric conversion efficiency of this gas-cooled nuclear reactor system while also overcoming the shortcomings of gaseous fuel in gas-cooled nuclear reactor systems, such as the susceptibility of gaseous fuel to corrosion of structural materials, leakage, and difficulty in post-processing. This also improved the engineering feasibility of a gas-cooled nuclear reactor system with a series 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, one disposed on either side of the reactor core; each electrode plate has multiple insulating layers to form multiple magnetic field zones within the reactor core. A magnetic field zone is formed between the two opposing electrode plates. Thus, by separating the electrode plates into multiple sections through the multiple insulating layers, multiple magnetic field zones can be formed within the reactor core.

[0020] In the present invention, the provision of multiple magnetic field zones can further stabilize the magnetohydrodynamic power generation process and disperse the effects of the magnetic field on the electrode plates, helping to extend the service life of the electrode plates. For example, when the conductive fluid in one magnetic field zone is disturbed or fluctuates, the conductive fluid in other magnetic fields can still generate electricity normally, thus 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 crisscrossing UO2 thin plate-shaped fuel in series with a thermal ionization magnetohydrodynamic generator to form a high-conversion-efficiency gas-cooled nuclear reactor system. While maintaining high thermoelectric conversion efficiency, the present invention improves the shortcomings of conventional gas-cooled nuclear reactor systems in which the nuclear reactor is connected in series with a magnetohydrodynamic generator, such as the easy corrosion of structural materials by the gas nuclear fuel design, easy leakage, and difficulty in post-processing. This improves the engineering feasibility of the gas-cooled nuclear reactor system in which the nuclear reactor is connected in series with a magnetohydrodynamic generator. BRIEF DESCRIPTION OF THE DRAWINGS

[0025] Figure 1 This is a schematic structural diagram of a gas-cooled nuclear reactor system for series thermal ionization magnetic fluid power generation provided by one embodiment of the present invention.

[0026] Figure 2 A schematic structural diagram of a reactor core provided in 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 solutions 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 intended 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 introduction of a gas-cooled nuclear reactor system featuring a nuclear reactor in series with a magnetohydrodynamic generator (MHDG), most related research and theoretical calculations have employed a gaseous core design. Gaseous nuclear fuel is susceptible to corrosion of structural materials, is prone to leakage, and presents significant challenges in post-processing. Due to safety concerns, gaseous nuclear fuel and other liquid nuclear fuels lack engineering feasibility in engineering applications. Replacing the gaseous core with a fuel grid composed of intersecting UO2 thin sheets can maintain the high thermal-to-electricity conversion efficiency of this gas-cooled nuclear reactor system while addressing the drawbacks of gaseous nuclear fuel, such as its prone to corrosion of structural materials, leakage, and difficulty in post-processing.

[0033] Based on this, the present invention proposes a high-conversion-efficiency gas-cooled nuclear reactor system in series with a thermal ionization magnetohydrodynamic generator. This system utilizes a fuel grid formed by interlacing thin UO2 fuel sheets in a horizontal and vertical manner, connected in series with a thermal ionization magnetohydrodynamic generator to form a high-conversion-efficiency gas-cooled nuclear reactor system. While maintaining high thermal-to-electricity conversion efficiency, this system overcomes the shortcomings of conventional gas-cooled nuclear reactor systems in which the gaseous nuclear fuel is easily corroded by structural materials, leaks easily, and is difficult to post-process. This improves the engineering feasibility of this gas-cooled nuclear reactor system in series with a nuclear reactor and a magnetohydrodynamic generator.

[0034] like Figure 1 A gas-cooled nuclear reactor system with series thermal ionization magnetohydrodynamic power generation includes a reactor core 1, a thermal ionization magnetohydrodynamic 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 a UO2 thin plate nuclear fuel. The fuel grid 11 has a total volume of 2×1.9992×1.9992m 3 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. 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-to-corrode structural materials, easy leakage and difficult post-processing in gas-cooled nuclear reactor systems with gaseous nuclear fuel as the core.

[0037] In the present invention, the design of a thin-plate fuel with a thickness of 0.2mm and a spacing of 1mm between two adjacent parallel thin-plate fuels has certain advantages in terms of heat exchange efficiency, flow resistance, and structural compactness. Specifically, the 0.2mm thin-plate fuel can respond to temperature changes more quickly, making heat transfer between the plates easier. If the thickness of the thin-plate fuel is too large, the temperature in the center of the thin-plate fuel will easily become too high, which will increase the risk of melting the thin-plate fuel during operation and hinder the heat exchange between the thin-plate fuel and the rare gas. A spacing of 1mm between the thin-plate fuels reduces the overall volume while allowing the coolant to flow smoothly between the plates, reducing flow resistance and improving cooling efficiency. However, a spacing that is too large may cause the coolant to form eddies or uneven flow when flowing between the plates, increasing flow resistance and reducing cooling efficiency. A spacing that is too small may easily cause impurities or particulate matter in the coolant to accumulate between the plates, creating a risk of blockage.

[0038] The thermal ionization magnetohydrodynamic generator element 2 is positioned outside the reactor core 1 and is used to provide a magnetic field to the fuel grid 11. In this embodiment of the present invention, a fuel grid formed by interlacing thin UO2 fuel sheets horizontally and vertically serves as the core of a solid-state nuclear fission reactor, replacing existing gaseous nuclear fuel. The nuclear reactor core and magnetohydrodynamic generator are integrated into a design, allowing the noble gas to flow through the core while simultaneously passing through the thermal ionization magnetohydrodynamic generator element, achieving thermal-to-electric conversion. The system architecture of the present invention, due to its integrated design, reduces the overall volume while maintaining high thermal-to-electric conversion efficiency, improving the engineering feasibility of a gas-cooled nuclear reactor system incorporating a nuclear reactor and magnetohydrodynamic generator in series. Preferably, the thermal ionization magnetohydrodynamic generator element 2 is a thermal ionization Hall magnetohydrodynamic generator. Literature research indicates that the Hall parameter β of plasma in gas-cooled nuclear reactor systems is relatively large, therefore, a thermal ionization Hall magnetohydrodynamic generator is selected. This device primarily generates electricity by utilizing the induced electromotive force generated by a conductive fluid, such as heated noble gas, flowing in a magnetic field. When the heated rare gas passes through a magnetic field, the ions in the rare gas are deflected by the Lorentz force, thereby generating an electric potential difference at both ends of the conductive fluid, which is called induced electromotive force. This can drive the current in the external circuit and realize thermoelectric conversion.

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

[0040] The specific principle is as follows: The cooling system is designed to supply noble gases to the reactor core 1. As these noble gases flow through the reactor core 1, they exchange heat with the fuel grid 11, absorbing heat generated by the reactor core 1 and heating themselves. When the heated noble gases reach a sufficiently high temperature, they undergo thermal ionization in specific areas within or near the thermal ionization magnetohydrodynamic power generation element 2, transforming into a conductive fluid, or plasma. The conductive fluid then flows within the strong magnetic field generated by the thermal ionization magnetohydrodynamic power generation element 2. Under the influence of the magnetic field, charged particles in the conductive fluid, such as ions and electrons, are acted upon by the Lorentz force, causing them to move along a specific path. The interaction between this movement and the magnetic field causes electromagnetic induction, which in turn generates an induced electromotive force in the circuit of the thermal ionization magnetohydrodynamic power generation element 2. Ultimately, by collecting and utilizing the generated induced electromotive force, the thermal energy generated by the reactor core is converted into electrical energy, completing the thermoelectric conversion process.

[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 a design so that rare gas passes through the core while thermally ionizing the magnetohydrodynamic power generation element 2 to achieve thermoelectric conversion.

[0042] Preferably, the fuel grid 11 has multiple channels along which the noble gas flows. The fuel grid, formed by the cross-section of UO2 thin-sheet fuel, avoids the drawbacks of gaseous nuclear fuel designs, such as the proneness to corrosion of structural materials, leakage, and difficulty in post-processing. Furthermore, by designing appropriate dimensions, it facilitates the smooth flow of coolant, enabling heat exchange between the coolant and the fuel grid while also facilitating thermoelectric conversion.

[0043] Preferably, 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. 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 these conditions, the system's total power reached 3.57MW, and the system's thermoelectric conversion efficiency reached 14.64%. This ensures the high thermoelectric conversion efficiency of this gas-cooled nuclear reactor system while also overcoming the shortcomings of gaseous fuel in gas-cooled nuclear reactor systems, such as the tendency for gaseous fuel to corrode structural materials, leak easily, and be difficult to post-process. This improves the engineering feasibility of a gas-cooled nuclear reactor system in which a nuclear reactor is connected in series with a magnetohydrodynamic generator. Thus, the noble gas Ar is pumped into the reactor core, enters the corresponding channel through the gas inlet, flows along the channel, and is then discharged through the gas outlet. During this process, the noble gas exchanges heat with the reactor core within the channel while cutting the magnetic flux lines in the thermally ionized magnetohydrodynamic generator element 2, achieving thermoelectric conversion.

[0044] Preferably, the thermal ionization magnetohydrodynamic power generation element 2 includes two electrode plates 21, which are respectively arranged on either side of the reactor core 1; each electrode plate 21 has multiple insulating layers 22 to form multiple magnetic field regions within the reactor core 1. The magnetohydrodynamic generator pole plates, insulating layers, and magnets are arranged on the periphery of the fuel grid in the same manner as the pole plates of a Hall generator. Preferably, the electrode plates 21 are made of a conductive material, which can be copper, silver, gold, or alloys thereof, such as copper-silver alloys and copper-nickel alloys; the insulating layer 22 is made of an insulating material, which can be a ceramic material such as aluminum oxide or silicon nitride. Appropriate conductive 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 under 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] 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 circuit 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 for the thermal ionization Hall magnetohydrodynamic generator is based on the distribution functions of the gas temperature, density, velocity, and pressure within the reactor core and the power calculation formula for the Hall generator. The specific model construction method is based on existing technology and 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 system's thermoelectric conversion efficiency reaches 14.64%.

[0054] The above results show that by replacing the gaseous fuel with a fuel grid made of UO2 thin plate fuel crossed horizontally and vertically, 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, can be improved while ensuring the high thermoelectric conversion efficiency of this gas-cooled nuclear reactor system.

[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 scope of protection of the present invention.

Claims

1. A gas-cooled nuclear reactor system for series thermal ionization magnetic fluid power generation, characterized in that: include: A reactor core (1) includes 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), arranged outside the reactor core (1) and used to provide a magnetic field to the fuel grid (11); A cooling system for supplying a rare gas to the reactor core (1), 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), and 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; The thickness of the thin plate fuel is 0.05mm to 0.3mm; The distance between two adjacent parallel thin-plate fuels is 0.5 mm to 3 mm; The fuel grid (11) has a plurality of channels; the rare gas flows along the plurality of channels.

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

3. The gas-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.

4. The gas-cooled nuclear reactor system for series thermal ionization magnetic fluid power generation according to claim 3, characterized in that: The rare gas is argon; the flow rate of the rare gas at the gas inlet is 60 m / s.

5. The gas-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.

6. The gas-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) 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 within the reactor core (1).

7. The gas-cooled nuclear reactor system for series thermal ionization magnetic fluid power generation according to claim 6, characterized in that: The electrode plate (21) is made of conductive material.

8. The series-connected thermal ionization magnetic fluid power generation gas-cooled nuclear reactor system according to claim 6, characterized in that: The insulating layer (22) is made of insulating material.

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