Nuclear power source with various thermoelectric power generation systems

Abstract

The embodiment of the invention relates to the technical field of nuclear reactors, in particular to a nuclear power source with various thermoelectric power generation systems. The nuclear power source comprises a reactor core, a Stirling power generation system and a static thermoelectric power generation system. The reactor core is used for providing heat; the Stirling power generation system and the static thermoelectric power generation system are both used for converting heat of the reactor core into electric energy. The Stirling power generation system comprises a plurality of first heat transfer pieces and a plurality of Stirling generators, and each first heat transfer piece is in heat conduction connection with the reactor core and is used for transferring heat of the reactor core to the Stirling generators; the static thermoelectric power generation system comprises a second heat transfer part and a plurality of static thermoelectric power generation elements, and the second heat transfer part is in heat conduction connection with each first heat transfer part and each static thermoelectric power generation element and used for transferring heat of the first heat transfer parts to the static thermoelectric power generation elements. According to the nuclear power supply provided by the embodiment of the invention, in the early stage of a deep space exploration task, even if an individual Stirling generator breaks down, the nuclear power supply can still provide relatively high power generation power.

Description

Technical Field

[0001] The embodiments of the present application relate to the field of nuclear reactor technology, and in particular to a nuclear power source having multiple temperature difference power generation systems. Background Art

[0002] This section of content merely provides background information related to the present application and does not necessarily constitute prior art.

[0003] Deep space exploration missions beyond Jupiter require a stable and continuous energy system for deep space probes to complete their exploration missions. Due to the low energy density of sunlight, solar cells cannot be used for deep space exploration missions. In view of the severe environmental conditions of interstellar space and its requirements for power stability and durability, nuclear power is the best energy choice.

[0004] At present, the existing nuclear power sources still have many problems and are difficult to meet the needs of deep space exploration missions. Summary of the invention

[0005] A brief overview of the present application is provided below in order to provide a basic understanding of certain aspects of the present application. It should be understood that this overview is not an exhaustive overview of the present application. It is not intended to identify the key or important parts of the present application, nor is it intended to limit the scope of the present application. Its purpose is merely to present certain concepts in a simplified form as a prelude to a more detailed description discussed later.

[0006] In view of the above technical problems, an embodiment of the present application provides a nuclear power source with multiple thermoelectric power generation systems, which may include a core, a Stirling power generation system, and a static thermoelectric power generation system. The core is used to provide heat. The Stirling power generation system and the static thermoelectric power generation system are used to convert the heat of the core into electrical energy. Among them, the Stirling power generation system includes a plurality of first heat transfer members and a plurality of Stirling generators, each of which is thermally connected to the core for transferring the heat of the core to the Stirling generator; the static thermoelectric power generation system includes a second heat transfer member and a plurality of static thermoelectric power generation elements, and the second heat transfer member is thermally connected to each first heat transfer member and each static thermoelectric power generation element for transferring the heat of the first heat transfer member to each static thermoelectric power generation element.

[0007] The nuclear power supply provided by the embodiment of the present application is provided with a static temperature difference power generation system, and its second heat transfer element is respectively connected to each first heat transfer element and each static temperature difference power generation element by heat conduction, so that the heat transferred from the core by the first heat transfer element can be used by the Stirling generator and the static temperature difference power generation element at the same time. In the early stage of the ultra-deep space exploration mission, even if an individual Stirling generator fails, since the first heat transfer element connected to the Stirling generator is connected to the second heat transfer element by heat conduction, the thermal power can be transferred to the temperature difference power generation element and the remaining first heat transfer elements through the second heat transfer element. Therefore, the core fuel temperature distribution will not change basically, and the nuclear power supply power will only change slightly, so that in the early stage of the mission, a larger power generation power can be provided, which can be used for the detector to carry out long-term electric propulsion acceleration, thereby greatly shortening the mission time or greatly widening the distance range of the mission.

[0008] These and other advantages of the present application will become more apparent through the following detailed description of the preferred embodiments of the present application in conjunction with the accompanying drawings. BRIEF DESCRIPTION OF THE DRAWINGS

[0009] In order to further illustrate the above and other advantages and features of the present application, the specific embodiments of the present application are further described in detail below in conjunction with the accompanying drawings. The accompanying drawings together with the following detailed description are included in this specification and form a part of this specification. Elements with the same function and structure are represented by the same reference numerals. It should be understood that these drawings only describe typical examples of the present application and should not be regarded as limiting the scope of the present application.

[0010] Figure 1 is a schematic structural diagram of a nuclear power supply according to an embodiment of the present application;

[0011] Figure 2 yes Figure 1 A schematic front view of the nuclear power source shown;

[0012] Figure 3 yes Figure 1 A schematic cross-sectional view of the main part of the nuclear power source shown;

[0013] Figure 4 is a structural schematic diagram of a static temperature difference power generation system according to an embodiment of the present application;

[0014] Figure 5 yes Figure 4 A top view of the static temperature difference power generation system shown;

[0015] Figure 6 yes Figure 4 A cross-sectional view of the static temperature difference power generation system shown;

[0016] Figure 7is a cross-sectional view of a core according to an embodiment of the present application.

[0017] It should be noted that the drawings are not necessarily drawn to scale, but are merely shown in a schematic manner that does not affect the reader's understanding.

[0018] Description of reference numerals:

[0019] 10. Reactor core; 11. Fuel; 12. Radial reflector; 13. First axial reflector; 14. Second axial reflector; 15. Safety rod channel; 16. Control drum;

[0020] 20. Stirling power generation system; 21. Stirling generator; 22. heat dissipation heat pipe; 23. radiation fin; 24. first heat transfer element; 241. first mounting seat; 25. vibration absorber;

[0021] 30. Static temperature difference power generation system; 31. Static temperature difference power generation element; 32. Heat dissipation structure; 33. Second heat transfer element; 331. Heat transfer through hole;

[0022] 40. Shielding body;

[0023] 50. Control drum drive mechanism. DETAILED DESCRIPTION

[0024] Exemplary embodiments of the present application will be described below in conjunction with the accompanying drawings. For the sake of clarity and conciseness, not all features of the actual implementation are described in the specification. However, it should be understood that many implementation-specific decisions must be made in the process of developing any such actual implementation in order to achieve the developer's specific goals, such as meeting those constraints related to the system and business, and these constraints may vary from implementation to implementation. In addition, it should be understood that although the development work may be very complex and time-consuming, it is only a routine task for those skilled in the art who benefit from the content of this application.

[0025] It is also necessary to explain here that, in order to avoid obscuring the present application due to unnecessary details, only the device structure and / or processing steps closely related to the scheme according to the present application are shown in the accompanying drawings, while other details that are not very relevant to the present application are omitted.

[0026] It should be noted that, unless otherwise defined, the technical terms or scientific terms used in this application should have the common meanings understood by persons with ordinary skills in the field to which this application belongs.

[0027] In the description of the embodiments of the present application, “plurality” means at least two, such as two, three, etc., unless otherwise clearly and specifically defined.

[0028] Deep space exploration missions require power sources to have an extremely long service life. Taking the solar system edge exploration mission as an example, the lifespan requirement for the power source is even more than 20 years. At present, for existing space heat pipe reactors, the factor limiting their lifespan is mainly the Stirling generator, which belongs to the dynamic conversion mode, has a high thermoelectric conversion efficiency (up to more than 25%), and has a theoretically long lifespan (15 years). However, for ultra-distant deep space missions such as the solar system edge exploration mission, its mission cycle (more than 20 years) even exceeds the theoretical design lifespan of the Stirling generator. Therefore, it is impossible to completely rely on the Stirling generator as the conversion method of nuclear power for deep space exploration.

[0029] Compared with Stirling generators, the advantages of static thermoelectric power generation elements are pure static vibration-free, high reliability, and long-life stable operation performance that has been fully verified. The disadvantage of static thermoelectric power generation elements is low conversion efficiency, which is only about one-fourth of Stirling power generation.

[0030] For ultra-deep space exploration missions, if the nuclear power supply uses both Stirling generators and static temperature difference power generation elements to generate electricity, then in the early stages of the mission (such as the first 15 years), the Stirling generator can achieve higher conversion efficiency and greater power generation. The larger power generation combined with electric thrusters can enable the probe to be continuously accelerated, thereby significantly shortening the mission time or significantly widening the distance range of the mission; in the later stages of the mission (after 15 years), even if all Stirling generators stop running, the thermoelectric power generation system can still continue to output a certain amount of electrical power to meet the signal transmission needs of the probe.

[0031] However, the inventor of the present application has found that in the related art, for nuclear power sources that use Stirling generators and static temperature difference power generation elements to generate electricity at the same time, there is a problem in some cases that the electric power is too small to meet the use requirements. Specifically, in the related art, each Stirling generator and each static temperature difference power generation element are respectively connected to the core through heat pipes for thermal conduction. In the early stage of the mission, if a Stirling generator is damaged, all the heat pipes connected to it will fail, so that the temperature of the core area corresponding to these heat pipes is easy to exceed the limit, because the thermal power of this area can only be transferred to the fuel area corresponding to other heat pipes in the form of solid heat conduction. If the temperature of the fuel and structural materials in this area is not to exceed the limit, the core thermal power must be greatly reduced, and the remaining electric power of the system will also be greatly reduced; and in the later stage of the mission, all Stirling generators stop running, and the corresponding heat pipes are all ineffective. In order to prevent the temperature of the core fuel and structural materials from exceeding the limit, the corresponding core thermal power and system electric power will become insignificant.

[0032] In order to solve the above technical problems, an embodiment of the present application provides a nuclear power source having multiple temperature difference power generation systems.

[0033] See also Figures 1 to 3 , Figure 1 is a schematic structural diagram of a nuclear power supply according to an embodiment of the present application; Figure 2 yes Figure 1 A schematic front view of the nuclear power source shown; Figure 3 yes Figure 1 The cross-sectional schematic diagram of the main part of the nuclear power source is shown. The nuclear power source of the embodiment of the present application may include a core 10, a Stirling power generation system 20, and a static temperature difference power generation system 30. The core 10 is used to provide heat.

[0034] In some embodiments, the core 10 may include a fuel 11. In some embodiments, the fuel 11 may be in a block shape, which may be made of a uranium-molybdenum alloy to efficiently generate heat.

[0035] The Stirling power generation system 20 and the static temperature difference power generation system 30 are both used to convert the heat of the core 10 into electrical energy. The Stirling power generation system 20 includes a plurality of first heat transfer members 24 and a plurality of Stirling generators 21, each of which is thermally connected to the core 10 and is used to transfer the heat of the core 10 to the Stirling generator 21; the static temperature difference power generation system 30 includes a second heat transfer member 33 and a plurality of static temperature difference power generation elements 31, the second heat transfer member 33 is thermally connected to each first heat transfer member 24 and each static temperature difference power generation element 31, and is used to transfer the heat of the first heat transfer member 24 to each static temperature difference power generation element 31.

[0036] The nuclear power supply provided by the embodiment of the present application is achieved by setting up a static temperature difference power generation system 30, and making its second heat transfer element 33 thermally connected to each first heat transfer element 24 and each static temperature difference power generation element 31 respectively, so that the heat transferred from the core 10 by the first heat transfer element 24 can be used by the Stirling generator 21 and the static temperature difference power generation element 31 at the same time.

[0037] In the early stage of the ultra-deep space exploration mission, even if an individual Stirling generator 21 fails, since the first heat transfer member 24 connected to the Stirling generator 21 is connected to the second heat transfer member 33, the thermal power can be transferred to the thermoelectric power generation element and the remaining first heat transfer members 24 through the second heat transfer member 33. Therefore, the temperature distribution of the fuel 11 in the core 10 will not change basically, and the power of the nuclear power source will only change slightly, so that in the early stage of the mission, a larger power generation power can be provided, which can be used for the detector to perform long-term electric propulsion acceleration, thereby greatly shortening the mission time or greatly widening the distance range of the mission.

[0038] In the later stage of the ultra-deep space exploration mission, although all Stirling generators 21 stop running, all first heat transfer elements 24 can still derive the thermal power of the fuel 11 through the static temperature difference power generation system 30, and the temperature distribution of the fuel 11 is still relatively uniform, so that the power generation of the nuclear power supply is higher than the technical solution of using both Stirling generators 21 and static temperature difference power generation elements 31 for power generation in the related art, and the nuclear power supply can still output enough power for the detector to transmit signals. Since the static temperature difference power generation element 31 has a long service life (the longest service life exceeds 50 years), the nuclear power supply provided by the embodiment of the present application can greatly broaden the detection distance of the mission.

[0039] Therefore, compared with the technical solution in the related art of simultaneously using a Stirling generator 21 and a static temperature difference power generation element 31 to generate electricity, the nuclear power supply provided by the embodiment of the present application can operate at a much higher thermal power and generate much greater electrical power.

[0040] See also Figures 4 to 6 , Figure 4 is a structural schematic diagram of a static temperature difference power generation system 30 according to an embodiment of the present application; Figure 5 yes Figure 4 A top view of the static temperature difference power generation system 30 is shown; Figure 6 yes Figure 4 A cross-sectional view of a static temperature difference power generation system 30 is shown.

[0041] In some embodiments, the second heat transfer member 33 may be a special-shaped heat pipe, and each static temperature difference power generation element 31 is disposed on the outer surface of the special-shaped heat pipe and is thermally connected to the outer surface. The special-shaped heat pipe has a good heat transfer effect through the phase change heat transfer of the internal coolant; at the same time, the special-shaped heat pipe is also conducive to thermal connection with the static temperature difference power generation element 31, so as to be more conducive to transferring the heat of each first heat transfer member 24 to each static temperature difference power generation element 31.

[0042] In some embodiments, the shape of the special-shaped heat pipe can be annular or cylindrical. The special-shaped heat pipe forms a plurality of heat transfer holes 331 that penetrate along its axial direction. Each first heat transfer member 24 is connected to a corresponding Stirling generator 21 through the heat transfer hole 331 by heat conduction, and each first heat transfer member 24 is connected to the hole wall of the heat transfer hole 331 by heat conduction. Since each first heat transfer member 24 passes through the special-shaped heat pipe, the heat from the core 10 is transferred to the Stirling power generation system 20 through the plurality of first heat transfer members 24, and is also transferred to the special-shaped heat pipe through the hole wall of the heat transfer hole 331, and the heat is transferred to the static temperature difference power generation element 31 through the special-shaped heat pipe, so that the heat transferred from the core 10 by the first heat transfer member 24 can be effectively utilized by the Stirling generator 21 and the static temperature difference power generation element 31 at the same time.

[0043] In some embodiments, the heat transfer holes 331 are evenly spaced along the circumferential direction of the special-shaped heat pipe, so that the heat from the core 10 can be more evenly dispersed into the heat transfer holes 331, thereby facilitating the first heat transfer element 24 running through the heat transfer holes 331 to evenly transfer heat to the Stirling generator 21 and the static temperature difference power generation element 31, thereby reducing the risk of local overheating caused by heat concentration.

[0044] In some embodiments, the fuel 11 forms a plurality of fuel channels penetrating along the axial direction thereof. The first heat transfer member 24 enters the fuel channels to conduct heat away from the fuel 11 .

[0045] Each fuel channel has substantially the same cross-sectional size as each heat transfer through hole 331. After passing through the fuel channel, each first heat transfer member 24 is heat-conductingly connected to the Stirling generator 21 via the heat transfer through hole 331. In this arrangement, the first heat transfer member 24 can transfer the heat of the core 10 to the Stirling generator 21.

[0046] In some embodiments, the static thermoelectric power generation system 30 may include a heat dissipation structure 32. Each static thermoelectric power generation element 31 is arranged on the radial outer surface of the special-shaped heat pipe. The heat dissipation structure 32 is arranged on the outer side of each static thermoelectric power generation element 31 along the radial direction of the special-shaped heat pipe. By arranging the heat dissipation structure 32 on the outer side of each static thermoelectric power generation element 31, it is beneficial to dissipate the waste heat generated during the power generation process of the static thermoelectric power generation element 31 in a timely manner, thereby facilitating the stable operation of the static thermoelectric power generation element 31 and improving the power generation efficiency of the static thermoelectric power generation element 31.

[0047] In some embodiments, the heat dissipation structure 32 may include a plurality of radiation fins. The radiation fins can increase the heat dissipation area and improve the heat dissipation efficiency, thereby facilitating timely discharge of waste heat generated by the static temperature difference power generation element 31 during operation in the form of radiation. The surface of the radiation fins can be coated with a coating that can improve the radiation efficiency to improve the heat dissipation effect.

[0048] In some embodiments, the heat dissipation structure 32 may be a carbon-carbon fin.

[0049] In some embodiments, the power generation material of the static thermoelectric power generation element 31 may be half-Heusler.

[0050] In some embodiments, the hot end of the static temperature difference power generation element 31 is thermally connected to the radial outer surface of the special-shaped heat pipe, and the heat dissipation structure 32 is thermally connected to the cold end of the static temperature difference power generation element 31.

[0051] In some embodiments, the radial outer surface of the shaped heat pipe is composed of a plurality of rectangular planes along the circumferential direction of the shaped heat pipe. Each static thermoelectric power generation element 31 is arranged on the rectangular plane. This arrangement enables the static thermoelectric power generation element 31 to fit with the rectangular plane, thereby increasing the thermal contact area between the thermoelectric power generation element and the shaped heat pipe, thereby promoting more uniform heat transfer and improving the thermoelectric conversion efficiency.

[0052] In some embodiments, the first heat transfer element 24 may be a heat pipe. The second heat transfer element 33 may be the same heat pipe as the first heat transfer element 24, that is, the two use the same coolant, the same tube shell material, etc., to facilitate heat conduction between the two. Heat pipes are more reliable than coolant loops.

[0053] In some embodiments, the first heat transfer element 24 is a sodium heat pipe, the tube shell of which may be filled with a certain amount of sodium, and the inner wall of the tube shell may be provided with a capillary wick. In some embodiments, the tube shell of the first heat transfer element 24 may be made of Haynes 230 material.

[0054] In some embodiments, the special-shaped heat pipe may be a sodium special-shaped heat pipe, the tube shell of which may be filled with a certain amount of sodium, and the inner wall of the tube shell may be provided with a capillary wick. The tube shell of the sodium special-shaped heat pipe may be made of Haynes 230 material.

[0055] In some embodiments, the first heat transfer member 24 forms a first mounting seat 241 for mounting the hot end of the Stirling generator 21 and being thermally connected to the hot end of the Stirling generator 21. In some embodiments, the first mounting seat 241 may have a funnel shape.

[0056] In some embodiments, the Stirling power generation system 20 may further include a plurality of heat dissipation heat pipes 22 and a plurality of radiation fins 23. The hot end of the Stirling generator 21 is thermally connected to the first heat transfer member 24. Each heat dissipation heat pipe 22 is thermally connected to the cold end of a corresponding Stirling generator 21. Each radiation fin 23 is thermally connected to a heat dissipation heat pipe 22. In this embodiment, the hot end of the Stirling generator 21 is thermally connected to the first heat transfer member 24, which is beneficial to improving the thermoelectric conversion efficiency of the Stirling power generation system 20 and enabling the Stirling power generation system 20 to have a high-power electrical energy output; each heat dissipation heat pipe 22 is thermally connected to the cold end of a corresponding Stirling generator 21, which can effectively discharge waste heat, and the radiation fins 23 further enhance the heat dissipation effect, which is beneficial to the stable operation of the Stirling generator 21 and extends the service life of the Stirling generator 21.

[0057] In some embodiments, the heat pipe 22 is a water heat pipe.

[0058] In some embodiments, the Stirling power generation system 20 may further include a plurality of vibration absorbers 25 for respectively reducing vibration of each Stirling generator 21 .

[0059] In some embodiments, there are multiple static temperature difference power generation systems 30. The second heat transfer member 33 of each static temperature difference power generation system 30 is thermally connected to each first heat transfer member 24, and is used to transfer the heat of each first heat transfer member 24 to each static temperature difference power generation element 31. In such an embodiment, when one static temperature difference power generation system 30 is damaged, other static temperature difference power generation systems 30 can still operate normally and output a certain amount of electric power, so as to improve the reliability of nuclear power generation.

[0060] In some embodiments, multiple static temperature difference power generation systems 30 are arranged at intervals along the extension direction of the first heat transfer element 24. This arrangement is conducive to transferring the heat of the first heat transfer element 24 to each second heat transfer element 33 evenly and simultaneously, and the static temperature difference power generation systems 30 do not interfere with each other. When a static temperature difference power generation system 30 fails, the heat of the first heat transfer element 24 can still be transferred to another static temperature difference power generation system 30, so as to improve the reliability of nuclear power generation.

[0061] In some embodiments, the nuclear power source may further include a shielding body 40. The shielding body 40 is disposed between the core 10 and the bottommost static temperature difference power generation system 30 to shield the radioactive radiation from the core 10. After the first heat transfer member 24 extends from the top of the core 10, it passes through the shielding body 40 and then passes through each heat transfer through hole 331 to be thermally connected to the Stirling generator 21. The first heat transfer member 24 is bent at two places in the shielding body 40 to prevent the core 10 radiation from passing through the center hole of the first heat transfer member 24 and directly penetrating the shielding body 40.

[0062] See also Figure 7 , Figure 7 1 is a cross-sectional view of a core according to an embodiment of the present application. In some embodiments, the core 10 may further include a radial reflective layer 12, a first axial reflective layer 13, and a second axial reflective layer 14. The radial reflective layer 12 is formed on the radial outer side of the fuel 11 to prevent the radiation and heat generated by the fuel 11 from leaking radially along the core 10. The first axial reflective layer 13 and the second axial reflective layer 14 are formed at both axial ends of the fuel 11 to prevent the radiation and heat generated by the fuel 11 from leaking axially along the core 10.

[0063] In some embodiments, the core 10 may further include a control drum 16 disposed in the radial reflection layer 12 for adjusting the nuclear fission reaction rate of the fuel 11 to achieve reactor power control.

[0064] In some embodiments, the core power supply may further include a plurality of control drum driving mechanisms 50 . The control drum driving mechanisms 50 are disposed on the shielding body 40 and are drivingly connected to the control drum 16 for driving the rotation of the control drum 16 .

[0065] In some embodiments, the nuclear power source may further include a safety rod and a safety rod driving mechanism. The safety rod is drivingly connected to the safety rod driving mechanism. A safety rod channel 15 is formed in the center of the fuel 11 for the safety rod to drop or be pulled out.

[0066] In some embodiments, the specific core 10 structure, the number of first heat transfer elements 24, the number of static temperature difference power generation systems 30, the second heat transfer element 33 structure, the rated power of the Stirling generator 21, the length of the heat pipe 22, the area of ​​the radiation fins, etc. can all be designed according to specific system parameter requirements.

[0067] The working principle of the nuclear power supply of the embodiment of the present application is as follows:

[0068] After the nuclear power source is successfully launched, the safety rod is pulled out from the safety rod channel 15 under the action of the safety rod driving mechanism, and the rotation angle of the control drum 16 is adjusted until the whole system reaches the rated power stable operation state.

[0069] When the nuclear power source is in operation, the fuel 11 in the core 10 generates thermal power, which is taken out by the first heat transfer element 24. In the early stage of the ultra-long-distance deep space exploration mission (such as the first 15 years), the first heat transfer element 24 transfers part of the heat of the core 10 to the static temperature difference power generation system 30, and the rest of the heat is transferred to the Stirling generator 21. The ratio between the two can be adjusted through specific design. Assuming that the thermal power of the core 10 is 6kW, 2kW of which is transferred to the static temperature difference power generation system 30 (conversion efficiency is about 5%), and 4kW is transferred to the Stirling generator 21 (conversion efficiency is about 25%), then the two can generate 100W and 1kW of electrical power respectively, with a total electrical power of about 1.1kW, which can be used for electric propulsion acceleration and signal transmission of the detector at the same time. At the end of the mission (after 15 years), the Stirling power generation system 20 stops operating after reaching the end of its service life, and the rotation angle of the control drum 16 is adjusted to reduce the power of the core 10 to 2kW. All of this power is transmitted to the static temperature difference power generation system 30, and generates 100W of electrical power for the detector to transmit signals.

[0070] Regarding the embodiments of the present application, it should also be noted that, in the absence of conflict, the embodiments of the present application and the features therein can be combined with each other to obtain new embodiments.

[0071] The above description is only a specific implementation manner of the present application, but the protection scope of the present application is not limited thereto. The protection scope of the present application shall be based on the protection scope of the claims.

Claims

1. A nuclear power source having multiple temperature difference power generation systems, characterized in that: include: The core, used to provide heat; A Stirling power generation system and a static temperature difference power generation system, both for converting the heat of the core into electrical energy; Wherein, the Stirling power generation system comprises a plurality of first heat transfer members and a plurality of Stirling generators, each of the first heat transfer members being heat-conductingly connected to the core to transfer the heat of the core to the Stirling generator; The static temperature difference power generation system includes a second heat transfer member and a plurality of static temperature difference power generation elements. The second heat transfer member is thermally connected to each of the first heat transfer members and each of the static temperature difference power generation elements for transferring heat from the first heat transfer member to each of the static temperature difference power generation elements.

2. The nuclear power source according to claim 1, characterized in that: The second heat transfer member is a special-shaped heat pipe, and the plurality of static temperature difference power generation elements are arranged on the outer surface of the special-shaped heat pipe and are thermally connected to the outer surface.

3. The nuclear power source according to claim 2, characterized in that: The shape of the special-shaped heat pipe is annular or cylindrical; The special-shaped heat pipe forms a plurality of heat transfer through holes penetrating along the axial direction thereof; Each of the first heat transfer members is thermally connected to a corresponding one of the Stirling generators through the heat transfer through hole, and each of the first heat transfer members is thermally connected to the hole wall of the heat transfer through hole.

4. The nuclear power source according to claim 3, characterized in that: The plurality of heat transfer through holes are distributed at equal intervals along the circumferential direction of the special-shaped heat pipe.

5. The nuclear power source according to claim 3, characterized in that: The static temperature difference power generation system also includes a heat dissipation structure; The plurality of static temperature difference power generation elements are arranged on the radial outer surface of the special-shaped heat pipe; The heat dissipation structure is arranged outside the plurality of static temperature difference power generation elements along the radial direction of the special-shaped heat pipe.

6. The nuclear power source according to claim 5, characterized in that: The heat dissipation structure includes a plurality of radiation fins.

7. The nuclear power source according to claim 6, characterized in that: The radial outer surface of the special-shaped heat pipe is composed of a plurality of rectangular planes arranged along the circumferential direction of the special-shaped heat pipe; The plurality of static temperature difference power generation elements are disposed on the plurality of rectangular planes.

8. The nuclear power source according to any one of claims 1 to 7, characterized in that: The Stirling power generation system further comprises: A plurality of heat pipes for heat dissipation, each heat pipe being heat-conductively connected to a cold end of a corresponding Stirling generator; A plurality of radiation fins, each of the radiation fins is thermally connected to one of the heat pipes.

9. The nuclear power source according to any one of claims 1 to 7, characterized in that: The number of the static temperature difference power generation systems is multiple; The second heat transfer element of each of the static temperature difference power generation systems is thermally connected to each of the first heat transfer elements, and is used to transfer the heat of the first heat transfer element to the static temperature difference power generation element.

10. The nuclear power source according to claim 9, characterized in that: The plurality of static temperature difference power generation systems are arranged at intervals along the extension direction of the first heat transfer element.

Images