Nuclear power source

Abstract

The embodiment of the present application provides a nuclear power source, comprising: a core, the core comprising a plurality of thermionic fuel elements, each of the thermionic fuel elements internally forming a first coolant channel for flowing a first coolant; a first collecting cavity and a second collecting cavity, the first coolant flowing from the first collecting cavity, through the thermionic fuel elements, and into the second collecting cavity; at least one heat exchanger, each of the heat exchangers having a first coolant flow channel and a second coolant flow channel capable of heat exchange; a first coolant loop for receiving the first coolant from the second collecting cavity and returning the first coolant to the first collecting cavity after the first coolant flows through the first coolant flow channel; at least one second coolant loop for circulating a second coolant, the second coolant in each of the second coolant loops being capable of flowing through one of the second coolant flow channels; and at least one thermoelectric conversion element for converting heat of one of the second coolant loops into electric energy.

Description

Technical Field

[0001] The embodiments of this application relate to the field of nuclear reactor technology, specifically to a nuclear power source. Background Technology

[0002] Nuclear power can be applied in the aerospace field. Nuclear power generates heat energy through the core of a nuclear reactor and converts the heat energy into electrical energy to power spacecraft, freeing spacecraft from their dependence on solar energy.

[0003] In nuclear power sources, only one thermoelectric conversion element is typically used to convert the heat in the reactor core into electrical energy, resulting in low power output. Summary of the Invention

[0004] To address the aforementioned technical problems, embodiments of this application provide a nuclear power source.

[0005] The nuclear power source of this application embodiment includes: a reactor core for providing heat, the reactor core including a plurality of thermionic fuel elements, each thermionic fuel element having a first coolant channel formed inside for supplying the first coolant flow; a first collector cavity and a second collector cavity, the first coolant flowing from the first collector cavity through the plurality of thermionic fuel elements and then into the second collector cavity; at least one heat exchanger, each heat exchanger having a first coolant channel and a second coolant channel capable of heat exchange; a first coolant circuit for receiving the first coolant from the second collector cavity and returning the first coolant to the first collector cavity after flowing through the first coolant channel of at least one heat exchanger; at least one second coolant circuit for supplying second coolant for circulation, the second coolant in each second coolant circuit being capable of flowing through the second coolant channel of a heat exchanger to exchange heat with the first coolant; and at least one thermoelectric conversion element, each thermoelectric conversion element being connected to a second coolant circuit for converting the heat of a second coolant circuit into electrical energy.

[0006] The embodiments of this application utilize a first coolant circuit to remove heat from the thermionic fuel element from the reactor, a second coolant circuit to exchange heat with the first coolant circuit, and a thermoelectric conversion element to convert the heat from the second coolant circuit into electrical energy. This allows the reactor to simultaneously employ thermionic conversion and other thermoelectric conversions, which can significantly improve the thermoelectric conversion efficiency of the reactor power supply. Attached Figure Description

[0007] Other objects and advantages of the invention will become apparent from the following description of the invention with reference to the accompanying drawings, and will help to provide a comprehensive understanding of the invention.

[0008] Figure 1 This is a schematic diagram of a nuclear power source according to an embodiment of the present invention;

[0009] Figure 2 This is a schematic diagram of the structure of a nuclear power source according to an embodiment of the present invention;

[0010] Figure 3 yes Figure 2 A partially enlarged schematic diagram of the nuclear power source shown.

[0011] Figure 4 yes Figure 3 A partially enlarged schematic diagram of the nuclear power source shown.

[0012] Figure 5 yes Figure 2 A partial front view of the nuclear power source shown;

[0013] Figure 6 A partial schematic diagram of a nuclear power source in another embodiment is shown;

[0014] Figure 7 It shows Figure 6 A partially enlarged schematic diagram of the nuclear power source shown.

[0015] Figure 8 This is a schematic cross-sectional view of the core of a nuclear power source according to an embodiment of this application;

[0016] Figure 9 This is a schematic diagram of a nuclear power source installed in a lunar crater according to an embodiment of this application.

[0017] It should be noted that the accompanying drawings are not necessarily drawn to scale, but are shown only in a schematic manner without affecting the reader's understanding.

[0018] Explanation of reference numerals in the attached figures:

[0019] 10. Core; 11. Thermoion fuel element; 12. First collector cavity; 13. Second collector cavity; 14. Shielding body; 141. First shield; 142. Second shield; 15. Control drum drive mechanism; 16. Control drum; 17. Radial reflector layer; 18. Solid moderator;

[0020] 20. First coolant circuit; 21. First pump; 22. First volume compensator; 201. Coolant inlet pipe; 202. Coolant outlet pipe; 203. First branch; 204. Second branch;

[0021] 30. Heat exchanger;

[0022] 40. Second coolant circuit; 41. Second pump; 42. Second volume compensator; 401. Flexible bellows section;

[0023] 50. Thermoelectric conversion element;

[0024] 60. Third coolant circuit; 61. Third pump; 62. Third volume compensator; 601. Flexible bellows section;

[0025] 70. Radiator;

[0026] 800. Lunar soil; 810. Lunar crater; 820. Lunar surface. Detailed Implementation

[0027] To make the objectives, technical solutions, and advantages of this invention clearer, the technical solutions of this invention will be clearly and completely described below with reference to the accompanying drawings of the embodiments of this invention. Obviously, the described embodiments are one embodiment of this invention, and not all embodiments. Based on the described embodiments of this invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of this invention.

[0028] It should be noted that, unless otherwise defined, the technical or scientific terms used in this application shall have the ordinary meaning as understood by one of ordinary skill in the art to which this invention pertains.

[0029] In the description of the embodiments of the present invention, "multiple" means at least two, such as two, three, etc., unless otherwise explicitly specified.

[0030] The structure of a thermionic fuel cell is extremely precise. From the inside out, the thermionic fuel cell consists of: fuel, emitter, generator gap, receiver, electrical insulation, helium chamber, stainless steel inner tube wall, primary coolant, and stainless steel outer tube wall. The primary coolant is typically a sodium-potassium alloy. During operation, the emitter temperature reaches approximately 1800 K, far exceeding the receiver temperature. Electrons are released from the emitter surface and directed towards the receiver, thus generating electrical energy.

[0031] The first coolant in the thermionic fuel element is used for waste heat discharge. The inventors of this application have discovered that the outlet temperature of the first coolant is very high, reaching 843-873 K, which is still suitable as the hot-end input temperature for certain thermoelectric conversion elements (such as free-piston Stirling generators). Combining the thermionic reactor with other thermoelectric conversion technologies, enabling the reactor to simultaneously employ thermionic conversion and other thermoelectric conversions, can significantly improve the thermoelectric conversion efficiency of the reactor power source.

[0032] In related technologies, the thermionic thermoelectric conversion element consists of a linear heat pipe encased within the reactor core, with one end extending outside the core and directly connected to the heat exchanger. The Stirling generator is also directly connected to the heat exchanger. While the linear heat pipe offers good thermal conductivity, its rigid structure, coupled with the vibrations generated by the Stirling generator during operation, transmits these vibrations to the thermionic thermoelectric conversion element. Since the thermionic thermoelectric conversion element has a structure similar to that of thermionic fuel elements and is highly precise, the vibrations transmitted from the Stirling generator can shorten its lifespan and significantly reduce power supply reliability.

[0033] To address this technical problem, embodiments of the present invention provide a novel nuclear power source structure.

[0034] See Figure 1 and Figure 2 The nuclear power source provided in this embodiment of the invention includes: a reactor core 10, a first coolant collection chamber 12 and a second coolant collection chamber 13, at least one heat exchanger 30, a first coolant circuit 20, at least one second coolant circuit 40, and at least one thermoelectric conversion element 50.

[0035] The reactor core 10 is used to provide heat. The reactor core 10 includes multiple thermionic fuel elements 11, each with a first coolant channel for coolant flow. The first coolant flows from a first collector chamber 12 through each thermionic fuel element 11 and then into a second collector chamber 13. The first collector chamber 12 and the second collector chamber 13 can be located at the top and bottom of the reactor core 10, respectively.

[0036] Each heat exchanger 30 has a first coolant flow channel and a second coolant flow channel for heat exchange. A first coolant circuit 20 receives first coolant from a second manifold 13 and returns the first coolant to the first manifold 12 after flowing through the first coolant flow channel of the heat exchanger 30. A second coolant circuit 40 is used for circulating second coolant. The second coolant in each second coolant circuit 40 can flow through the second coolant flow channel of a heat exchanger 30 to exchange heat with the first coolant. Each thermoelectric conversion element 50 is connected to a second coolant circuit 40 for converting the heat from the second coolant circuit 40 into electrical energy.

[0037] In this embodiment, the heat from the thermionic fuel element 11 is discharged from the reactor using the first coolant circuit 20, and the heat is exchanged between the second coolant circuit 40 and the first coolant circuit 20. Then, the heat from the second coolant circuit 40 is converted into electrical energy using the thermoelectric conversion element 50. This allows the reactor to simultaneously employ thermionic conversion and other thermoelectric conversions, which can significantly improve the thermoelectric conversion efficiency of the reactor power supply.

[0038] In this embodiment, the heat from the thermionic fuel element 11 is discharged from the reactor using the first coolant circuit 20, and the thermoelectric conversion element 50 is connected to the second coolant circuit 40. Therefore, the thermoelectric conversion element 50 and the thermionic fuel element 11 are no longer rigidly connected by a straight heat pipe and heat exchanger 30. When the thermoelectric conversion element 50 vibrates, it will not be transmitted to the thermionic fuel element 11, thereby avoiding adverse effects on the thermionic fuel element 11 due to the vibration of the thermoelectric conversion element 50.

[0039] See Figure 3 and Figure 4 In some embodiments, the number of heat exchangers 30, the second coolant circuit 40, and the thermoelectric conversion element 50 are two each. The first coolant circuit 20 further includes: a coolant inlet pipe 201, a coolant outlet pipe 202, and a first branch 203 and a second branch 204 connected in parallel. The coolant inlet pipe 201 is connected to the first manifold 12 for returning the first coolant to the first manifold 12. The coolant outlet pipe 202 is connected to the second manifold 13 for allowing the first coolant to flow out of the second manifold 13. The two heat exchangers 30 are respectively disposed on the first branch 203 and the second branch 204. The coolant inlet pipe 201 and the coolant outlet pipe 202 are connected through the parallel first branch 203 and the second branch 204. In such an embodiment, the nuclear power source includes two independent second coolant loops 40, thermoelectric conversion elements 50, and heat exchangers 30, thereby providing redundancy to the nuclear power source. Even if a single device fails, the system can still continue to operate and output a certain amount of electrical power, which is beneficial to the safety of the lunar base.

[0040] In some embodiments, the first coolant circuit 20, two heat exchangers 30, two second coolant circuits 40, and two thermoelectric conversion elements 50 are arranged symmetrically with respect to the vertical bisector of the reactor core 10. The vertical bisector can be understood as a vertical plane passing through the axis of the reactor core 10, with the portions of the reactor core 10 located on either side of this vertical bisector symmetrically with respect to it. The symmetrical arrangement of the first coolant circuit 20, two heat exchangers 30, and two second coolant circuits 40 with respect to the vertical bisector of the reactor core 10 means that the first branch 203 and the second branch 204 are also arranged symmetrically with respect to the vertical bisector of the reactor core 10. This arrangement facilitates the complete symmetry of the flow paths of the first coolant in the two branches and the second coolant in the two circuits, thereby ensuring that the second coolant in the two second coolant circuits 40 maintains the same flow rate and temperature. This, in turn, helps to ensure that the two thermoelectric conversion elements 50 operate in essentially the same environment, guaranteeing stable nuclear power output.

[0041] See Figure 5In some embodiments, the axes of the coolant inlet pipe 201 and the coolant outlet pipe 202 are both located within the vertical bisecting plane. Such embodiments facilitate the symmetrical arrangement of the aforementioned components and pipes, thereby achieving complete symmetry of the nuclear power source as a whole.

[0042] In some embodiments, the first branch 203 and the second branch 204 are located on opposite sides of the vertical bisecting plane, which is more conducive to achieving a symmetrical arrangement of the above-mentioned components and pipelines.

[0043] In this embodiment, the thermoelectric conversion element 50 is a Stirling generator. Because the first coolant circuit 20 is used to remove heat from the thermionic fuel element 11 from the reactor, and the Stirling generator is connected to the second coolant circuit 40, the connection between the Stirling generator and the thermionic fuel element 11 is no longer rigid. Therefore, when the Stirling generator vibrates, the vibration is essentially not transmitted to the thermionic fuel element 11, thus avoiding adverse effects on the thermionic fuel element 11 due to the vibration of the Stirling generator. In particular, the addition of a first collector cavity 12 and a second collector cavity 13 further reduces the impact of the Stirling generator vibration on the thermionic fuel element 11.

[0044] Furthermore, the thermoelectric conversion element 50 can be a opposed Stirling generator to further reduce vibration. A set of two opposed Stirling generators is arranged in each second coolant loop 40. The Stirling generators are positioned as far away from the reactor as possible to minimize their radiation dose.

[0045] See Figure 6 and Figure 7 In some embodiments, the second coolant circuit 40 includes a flexible bellows section 401 for absorbing vibrations from the Stirling generator and isolating the vibrations of the Stirling generator from other components of the system.

[0046] The second coolant circuit 40 may include two flexible bellows sections 401, each close to a Stirling generator. That is, the two flexible bellows sections 401 are located close to the points where the second coolant circuit 40 is connected to the Stirling generator.

[0047] In some embodiments, a vibration damping device may be installed around the Stirling generator to reduce vibration of the Stirling generator.

[0048] In some embodiments, the nuclear power source further includes at least one third coolant circuit 60 and at least one set of radiators 70.

[0049] The third coolant circuit 60 is used to circulate the third coolant, which is used to dissipate heat from the thermoelectric conversion element 50. Each radiator 70 is thermally connected to one third coolant circuit 60 to dissipate heat from the third coolant in the third coolant circuit 60. The number of third coolant circuits 60 is the same as the number of thermoelectric conversion elements 50. When there are two thermoelectric conversion elements 50, there are also two third coolant circuits 60, and two sets of radiators 70.

[0050] In some embodiments, the third coolant circuit 60 may also include a flexible bellows section 601, which absorbs vibrations from the Stirling generator and isolates the vibrations from other components of the system. The third coolant circuit 60 may include two flexible bellows sections 601, each located close to the Stirling generator. That is, the two flexible bellows sections 601 are located close to the connection points between the third coolant circuit 60 and the Stirling generator. Thus, all four pipes connected to the four coolant ports of the Stirling generator are equipped with flexible bellows sections 601, further reducing the impact of the Stirling generator's vibrations on other components of the system.

[0051] In some embodiments, each circuit may also be provided with a volume compensator for compensating the volume of the coolant flowing in each circuit. Specifically, the first coolant circuit 20 is provided with a first volume compensator 22, the second coolant circuit 40 is provided with a second volume compensator 42, and the third coolant circuit 60 is provided with a third volume compensator 62.

[0052] In some embodiments, each circuit may also be equipped with a pump to drive the flow of coolant in the circuit. Specifically, the first coolant circuit 20 is equipped with a first pump 21, the second coolant circuit 40 is equipped with a second pump 41, and the third coolant circuit 60 is equipped with a third pump 61.

[0053] The first pump 21 is installed in the coolant inlet pipe 201, and the first volume compensator 22 is installed in the coolant outlet pipe 202. The second pump 41 and the second volume compensator 42 are respectively arranged on the cooling medium outlet side and the cooling medium inlet side of the heat exchanger 30. The third pump 61 and the third volume compensator 62 are respectively arranged on the cooling medium outlet side and the cooling medium inlet side of the thermoelectric conversion element 50.

[0054] In this embodiment, the first and second coolants can be sodium-potassium working fluids, and the third coolant can be water. The first pump 21 and the second pump 41 can be electromagnetic pumps, and the third pump 61 can be a water pump.

[0055] See Figure 2Each radiator group 70 includes multiple heat pipes and fins to achieve better heat dissipation performance. When the third coolant is water, the heat pipes can be water heat pipes (i.e., the working fluid inside the heat pipes is water).

[0056] As shown in the figure, the third coolant circuit 60 may include a U-shaped pipe, with the opening of the U-shaped pipe facing the heat exchanger 30. Each heat dissipation heat pipe is thermally connected to the U-shaped pipe. Each heat sink can be welded to a heat dissipation heat pipe for heat dissipation. The heat sink can increase the heat dissipation area and improve the heat dissipation effect. The heat dissipation heat pipe can transfer heat from the coolant to the heat sink, so that the heat is dissipated by the heat sink.

[0057] The U-shaped pipeline includes a first horizontal section and a second horizontal section that are parallel to each other, and a vertical section connecting the first horizontal section and the second horizontal section. One end of each heat pipe is thermally connected to either the first or second horizontal section, and the other end extends along the axis of the core 10 in a direction away from the core 10. This arrangement allows the heat pipes to be perpendicular to the direction of gravity, thereby improving their thermal conductivity.

[0058] The U-shaped pipe of the third coolant circuit 60 and the radiator 70 are located in the same vertical plane, which is also the vertical bisecting plane of the reactor, and this vertical bisecting plane is perpendicular to another vertical bisecting plane.

[0059] In some embodiments, two second coolant circuits 40 extend from two heat exchangers 30 in opposite directions, and two third coolant circuits 60 extend from two thermoelectric conversion elements 50 in opposite directions, thereby enabling the two sets of radiators 70 to be as far away from the core 10 as possible; since the axes of the heat pipes and fins of the radiators 70 are parallel to the axis of the core 10, the radiation from the core 10 to the radiators 70 can be further reduced.

[0060] See Figure 8 In some embodiments, the reactor core 10 includes a solid moderator 18, fuel elements, a control drum 16, and a radial reflector layer 17.

[0061] The solid moderator 18 forms multiple channels, and multiple thermionic fuel elements 11 are respectively arranged in the corresponding channels of the solid moderator 18. The moderator material can be zirconium hydride. A radial reflector layer 17 is formed on the radially outer side of the solid moderator 18. The radial reflector layer 17 is used to prevent radiation and heat generated by the fuel elements from leaking radially along the core 10. The radial reflector layer 17 can be made of beryllium. A control drum 16 is disposed in the radial reflector layer 17 and is used to adjust the nuclear fission reaction rate of the fuel elements to control the reactor power. The main material of the control drum 16 can be beryllium, and the neutron absorbing material of the control drum 16 can be boron carbide.

[0062] In some embodiments, the nuclear power source further includes a plurality of control drum drive mechanisms 15, which are disposed on the shield 14 and drivenly connected to the control drum 16 for driving the rotation of the control drum 16. Figure 8 In the embodiment shown, the core 10 is equipped with 37 thermionic fuel elements 11 and 12 control drums 16.

[0063] The nuclear power source in this embodiment can be located on the lunar surface to supply power to other equipment on the lunar surface. Such a nuclear power source can be called a lunar nuclear power source. The specific core 10 structure, the number of thermionic fuel elements 11, the structure of the heat exchanger 30, the rated power of the Stirling generator, the area of ​​the radiator 70, etc., can be designed according to the actual lunar reactor parameter requirements.

[0064] The thermionic reactor core 10 is arranged in a pre-dug lunar crater 810. In some embodiments, the nuclear power source may further include: a shield 14 disposed directly above the core 10 for shielding against radioactive radiation from the core 10. A heat exchanger 30 is disposed directly above the shield 14.

[0065] The shielding body 14 includes a first shield 141 located on the upper layer and a second shield 142 located on the lower layer. Both the first shield 141 and the second shield 142 are coaxial with the core 10. The radius of the first shield 141 is larger than the radius of the second shield 142 to prevent the rays from the core 10 from penetrating directly to the upper components along the gap between the shielding body 14 and the lunar soil 800.

[0066] The first manifold 12 is located below the second shield 142. The coolant inflow pipe 201 extends vertically upward from the first manifold 12 along the peripheral wall of the second shield 142 to the first shield 141, and then extends vertically upward along the peripheral wall of the first shield 141 for a predetermined distance before extending horizontally inward in the radial direction, connecting with the horizontally extending first branch 203 and second branch 204.

[0067] The coolant outlet pipe 202 extends vertically upward from the second manifold 13 to the second shield 142, continues vertically upward along the periphery of the second shield 142 to the first shield 141, then extends vertically upward along the periphery of the first shield 141 for a predetermined distance, and then extends horizontally inward in the radial direction, connecting with the horizontally extending first branch 203 and second branch 204. The inlet and outlet of the first coolant flow channel of the heat exchanger 30 are located on both axial sides of the heat exchanger 30, and the inlet and outlet of the second coolant flow channel are located on the upper and lower sides, respectively.

[0068] The second coolant circuit 40, each pump, each volume compensator, thermoelectric conversion element 50, the third coolant circuit 60, and the radiator 70 are all higher than the shield 14. On the one hand, this can reduce the radiation dose received by these components, and on the other hand, it can reduce the level of activation of the coolant working fluid in the second coolant circuit 40 by radiation from the reactor core 10, thereby reducing the radiation dose of the activated coolant working fluid acting on the thermoelectric conversion element 50.

[0069] See Figure 9 In this embodiment of the application, the nuclear power plant core 10 and shield 14 are placed in the lunar crater 810. Since the lunar soil 800 can provide good circumferential shielding, the radiation impact of the core 10 on the radiator 70, pump, control drum drive mechanism 15, etc. is small.

[0070] The shield 14 is configured to enclose the lunar crater 810. The shield 14 and the lunar soil 800 surrounding the lunar crater 810 form a closed radiation shielding container to prevent the radioactive radiation generated by the reactor core 10 from leaking to the outside of the lunar crater 810.

[0071] In this embodiment, the nuclear power source is symmetrically arranged, which makes the weight distribution more uniform when the nuclear power source is placed in the lunar crater 810, thereby increasing the stability of the nuclear power source; at the same time, the two sets of heat sinks 70 are arranged on both sides of the shield 14, so that the two sets of heat sinks 70 are not directly above the core 10, thereby further reducing the radiation from the core 10 received by the two sets of heat sinks 70.

[0072] After the nuclear power source is successfully launched to lunar surface 820, the reactor core 10 and shield 14 are first installed in lunar crater 810 by astronauts or robots. Then, under the action of the control drum drive mechanism 15, the reactor core 10 and the control drum 16 absorber are slowly turned away from the fuel elements until the reactor core 10 reaches a stable operating state at rated power.

[0073] When the core 10 is running, the fuel elements generate heat, which is carried out by the first coolant and transferred to the heat exchanger 30. The second coolant then transfers the heat to the thermoelectric conversion element 50 to generate electrical energy. The cold end of the thermoelectric conversion element 50 is cooled by water. Driven by a water pump, the water transfers the waste heat to the radiator 70 on the lunar surface 820, where it is emitted by radiation.

[0074] The working principle of a nuclear power source is explained below using Topaz-II thermionic reactor core 10 as an example.

[0075] After the nuclear power source is launched and successfully lands, the reactor core 10 is placed in the pre-dug lunar crater 810. Under the action of the control drum drive mechanism 15, the control drum 16 absorber is slowly turned away from the active area of ​​the core 10 until the reactor reaches the rated power stable operation state.

[0076] During reactor operation, the fuel generates 115 kWt of thermal power, with an emitter temperature of approximately 1800 K. The 37 thermionic fuel elements 11 generate approximately 5 kWe of electrical power. The sodium-potassium primary loop carries the remaining approximately 110 kWt of thermal power to the outside of the reactor, with an outlet temperature of approximately 850 K. This thermal power is then transferred to the sodium-potassium secondary loop in heat exchanger 30. The outlet temperature of heat exchanger 30 in the sodium-potassium secondary loop is approximately 824 K. The sodium-potassium secondary loop then transfers this thermal power to the Stirling generator. The hothead temperature of the Stirling generator is approximately 778 K, and the coldhead temperature is approximately 425 K. Its thermoelectric conversion efficiency is approximately 26%. The two opposed Stirling generators (equivalent to four Stirling generators) can generate approximately 28 kWe of electrical power. Combined with the electrical power generated by the thermionic fuel elements 11 (5 kWe), the total electrical power of the system reaches approximately 33 kWe, corresponding to a system thermoelectric conversion efficiency of approximately 30%. The waste heat from the Stirling generator is carried out by the water loop and discharged to the lunar surface and outer space via radiators.

[0077] Therefore, this application embodiment, based on the existing thermionic reactor, introduces a Stirling generator through a loop, which significantly improves the system's thermoelectric conversion efficiency from less than 5% to approximately 30%. This application embodiment also employs two thermoelectric conversion methods, enabling the lunar nuclear power source to significantly improve its thermoelectric conversion efficiency without significantly increasing the development difficulty.

[0078] In related technologies, heat pipes are used to remove heat from the reactor core in order to improve the thermoelectric conversion efficiency of nuclear power sources. However, the embodiments of this application use a loop to remove heat, which can still significantly improve the thermoelectric conversion efficiency of nuclear power sources, while avoiding adverse effects on the thermal ion fuel element 11 and shortening the service life of the thermal ion fuel element 11.

[0079] Regarding the embodiments of the present invention, it should also be noted that, without conflict, the embodiments of the present invention and the features in the embodiments can be combined with each other to obtain new embodiments.

[0080] The above are merely specific embodiments of the present invention, but the scope of protection of the present invention is not limited thereto. The scope of protection of the present invention should be determined by the scope of the claims.

Claims

1. A nuclear power source, comprising: The reactor core is used to provide heat, and the reactor core includes a plurality of thermionic fuel elements, each of which forms a first coolant channel for the flow of the first coolant. The first collector cavity and the second collector cavity, wherein the first coolant flows from the first collector cavity through the plurality of thermionic fuel elements and then flows into the second collector cavity; At least one heat exchanger, each heat exchanger having a first coolant flow channel and a second coolant flow channel capable of heat exchange; A first coolant circuit is used to receive the first coolant from the second manifold and to allow the first coolant to flow through the first coolant channel of the at least one heat exchanger and then return to the first manifold. At least one second coolant circuit is provided for the circulation of a second coolant, wherein the second coolant in each second coolant circuit is capable of flowing through a second coolant passage of the heat exchanger to exchange heat with the first coolant; as well as At least one thermoelectric conversion element, each of the thermoelectric conversion elements being connected to a second coolant circuit for converting heat from a second coolant circuit into electrical energy; The thermoelectric conversion element is a Stirling generator.

2. The nuclear power source according to claim 1, wherein, The number of the heat exchanger, the second coolant circuit, and the thermoelectric conversion element are all two. The first coolant circuit also includes: A coolant inflow pipe is connected to the first manifold, which is used to allow the first coolant to return to the first manifold. A coolant outlet pipe, connected to the second manifold, is used to allow the first coolant to flow out of the second manifold; and The first and second branches are connected in parallel, and the two heat exchangers are respectively installed on the first branch and the second branch; The coolant inflow pipe and the coolant outflow pipe are connected by a first branch and a second branch connected in parallel.

3. The nuclear power source according to claim 2, wherein, The first coolant circuit, the two heat exchangers, the two second coolant circuits, and the two thermoelectric conversion elements are arranged symmetrically with respect to the vertical bisecting plane of the reactor core.

4. The nuclear power source according to claim 3, wherein, The axes of both the coolant inlet pipe and the coolant outlet pipe are located within the vertical bisecting plane.

5. The nuclear power source according to claim 3, wherein, The first branch and the second branch are located on opposite sides of the vertical bisecting plane.

6. The nuclear power source according to claim 1, wherein, The second coolant circuit includes a flexible bellows section.

7. The nuclear power source according to claim 1, further comprising: At least one third coolant circuit is provided for circulating a third coolant, which is used to dissipate heat from the thermoelectric conversion element; and At least one set of radiators, each set of radiators being thermally connected to one of the third coolant circuits, for dissipating heat from the third coolant in the third coolant circuit.

8. The nuclear power source according to claim 7, wherein, The third coolant circuit includes a flexible bellows section.

9. The nuclear power source according to claim 1, further comprising: A shielding body is positioned directly above the reactor core to shield it from radioactive radiation. The at least one heat exchanger is positioned directly above the shield.

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