Nuclear power source

Abstract

The embodiment of the present application provides a nuclear power source. The nuclear power source comprises: a reactor core for providing heat; a plurality of heat pipes, an evaporation section of each heat pipe being inserted into the reactor core, and a condensation section of each heat pipe extending out of the reactor core; a thermoelectric conversion module arranged outside the reactor core, the thermoelectric conversion module comprising a plurality of first thermoelectric conversion elements, each first thermoelectric conversion element having a ring structure, wherein each first thermoelectric conversion element is sleeved on the condensation section of one heat pipe, and the first thermoelectric conversion element is in thermal connection with the condensation section; a first cooling cavity for flowing of a coolant, the first cooling cavity being arranged outside the reactor core and being arranged in a spaced mode with the reactor core, and the plurality of first thermoelectric conversion elements being arranged in the first cooling cavity; a first coolant inlet in communication with the first cooling cavity; and a first coolant outlet in communication with the first cooling cavity. The nuclear power source provided by the embodiment of the present application can enable the thermoelectric conversion elements to work stably for a longer time.

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 plants, thermal energy can be converted into electrical energy using a free-piston Stirling generator. The Stirling generator is a dynamic conversion technology with high energy conversion efficiency. However, because the Stirling generator generates electricity by driving a linear generator through the high-frequency reciprocating motion of a piston, its performance becomes unstable after prolonged operation, resulting in fluctuations in power output and making it difficult to achieve stable power supply over extended periods. Summary of the Invention

[0004] In view of the above problems, this application provides a nuclear power source. The nuclear power source includes: a reactor core for providing heat; multiple heat pipes, each heat pipe having an evaporation section inserted into the reactor core and a condensation section extending outward from the reactor core; a thermoelectric conversion module disposed outside the reactor core, the thermoelectric conversion module including multiple first thermoelectric conversion elements, each first thermoelectric conversion element having a ring structure, wherein each first thermoelectric conversion element is sleeved on the condensation section of a heat pipe and is thermally connected to the condensation section to convert the heat transmitted by the heat pipe into electrical energy; a first cooling chamber for supplying coolant flow, the first cooling chamber being disposed outside the reactor core and spaced apart from the reactor core, the multiple first thermoelectric conversion elements being located inside the first cooling chamber to be cooled by the coolant inside the first cooling chamber; a first coolant inlet communicating with the first cooling chamber for introducing coolant into the first cooling chamber; and a first coolant outlet communicating with the first cooling chamber for drawing out the coolant from the first cooling chamber.

[0005] The nuclear power source provided in this application embodiment extracts heat from the reactor core via heat pipes. Simultaneously, the thermoelectric conversion element has a ring structure that can be fitted onto the condensation section of the heat pipe, thereby increasing the connection strength and thermal conductivity area between the thermoelectric conversion element and the heat pipe, enabling the thermoelectric conversion element to operate stably and efficiently for a longer period. Furthermore, the nuclear power source is equipped with a cooling chamber, through which flowing coolant extracts excess heat from the thermoelectric conversion element, further ensuring the stability of the thermoelectric conversion element during long-term operation. Attached Figure Description

[0006] The above and / or additional aspects and advantages of this application will become apparent and readily understood from the description of the embodiments taken in conjunction with the following drawings, wherein:

[0007] Figure 1This is a schematic diagram of the nuclear power source according to an embodiment of this application;

[0008] Figure 2 This is a schematic diagram of the structure of a nuclear power source according to an embodiment of this application;

[0009] Figure 3 This is a cross-sectional schematic diagram of a nuclear power source according to an embodiment of this application;

[0010] Figure 4 This is a cross-sectional schematic diagram of a partial structure of a nuclear power source according to an embodiment of this application;

[0011] Figure 5 This is a cross-sectional schematic diagram of the core of a nuclear power source according to an embodiment of this application;

[0012] Figure 6 This is a cross-sectional schematic diagram of the cooling chamber of a nuclear power source according to an embodiment of this application;

[0013] Figure 7 This is a schematic diagram of the cooling chamber of the nuclear power source according to an embodiment of this application;

[0014] Figure 8 for Figure 7 A cross-sectional schematic diagram of the cooling cavity shown;

[0015] Figure 9 This is a cross-sectional schematic diagram of the assembly of the cooling chamber and heat pipes of the nuclear power source according to an embodiment of this application.

[0016] Figure 10 for Figure 9 A cross-sectional view of the intermediate cooling chamber and heat pipes along plane AA;

[0017] Figure 11 This is a cross-sectional schematic diagram of another partial structure of the nuclear power source according to an embodiment of this application;

[0018] Figure 12 This is a schematic diagram of the structure of the second heat sink of the nuclear power source according to an embodiment of this application;

[0019] Figure 13 This is a schematic diagram of the structure of the first heat sink of the nuclear power source according to an embodiment of this application.

[0020] It should be noted that the accompanying drawings are not necessarily drawn to scale, but are shown only in a schematic manner that does not affect the understanding of those skilled in the art.

[0021] Explanation of reference numerals in the attached figures:

[0022] 10. Core; 11. Fuel Block; 12. Radial Reflector Layer; 13. Axial Reflector Layer; 14. Control Drum; 15. Safety Rod Channel; 20. Heat Pipe; 21. Evaporation Section; 22. Condensation Section; 30. Thermoelectric Conversion Module; 31. First Thermoelectric Conversion Element; 32. Second Thermoelectric Conversion Element; 41. First Cooling Chamber; 411. First Coolant Inlet; 412. First Coolant Outlet; 413. Second Annular Collector Chamber; 414. First Annular Collector Chamber; 415. Receiving Chamber; 416. 42. First connecting channel; 51. Second cooling chamber; 51. First radiator; 511. First collector ring; 512. Second collector ring; 513. First connecting pipe; 514. First heat sink; 515. First volume compensator; 52. Second radiator; 521. Third collector ring; 522. Fourth collector ring; 523. Second connecting pipe; 524. Second heat sink; 525. Second volume compensator; 60. Shielding body; 61. Control drum drive mechanism; 71. First pump; 72. Second pump. Detailed Implementation

[0023] The technical solutions of the embodiments of this application will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of this application, and not all embodiments. Based on the embodiments of this application, all other embodiments obtained by those of ordinary skill in the art without creative effort are within the scope of protection of this application. It should also be noted that, without conflict, the embodiments and features in the embodiments of this application can be combined with each other to obtain new embodiments.

[0024] This application provides a nuclear power source. The nuclear power source in this embodiment can convert thermal energy into electrical energy through a thermoelectric conversion module.

[0025] like Figure 1 , Figure 2 and Figure 4 As shown, a nuclear power source may include a reactor core, heat pipes 20, thermoelectric conversion module 30, a first cooling chamber 41, a first coolant inlet 411, and a first coolant outlet 412.

[0026] The reactor core is used to provide heat. Fuel blocks 11 may be placed within the core; these fuel blocks 11 undergo fission reactions to generate heat, thus enabling the core to provide heat. The heat generated by the fuel blocks 11 can be converted into electrical energy through a thermoelectric conversion module 30. In some embodiments, the fuel blocks 11 may be made of a uranium-molybdenum alloy (U-8%Mo). Uranium-molybdenum alloys are readily available, operate at lower temperatures, have lower requirements for the coolant circuit, reducing development difficulty, and also have a larger thermal safety margin, which is beneficial to improving the safety and reliability of the system.

[0027] Heat pipes 20 are used to transfer heat from the reactor core to the thermoelectric conversion module 30. There can be multiple heat pipes 20; the evaporation section 21 of each heat pipe 20 is inserted into the reactor core, and the condensation section 22 of each heat pipe 20 extends outward from the reactor core. Figure 3 As shown, each heat pipe 20 may include an evaporation section 21 and a condensation section 22. The heat pipe 20 contains a working medium. In the evaporation section 21, the working medium absorbs heat and evaporates. The evaporated working medium then moves to the condensation section 22, where it releases heat and condenses, thus completing the heat transfer. The condensed working medium in the condensation section 22 can return to the evaporation section 21, thus completing the circulation of the working medium. In this embodiment, the working medium in the heat pipe 20 may be potassium, and the shell and wick of the heat pipe 20 may be made of 316L stainless steel.

[0028] The thermoelectric conversion module 30 is used to convert the heat transferred by the heat pipe 20 into electrical energy. The thermoelectric conversion module 30 is disposed outside the reactor core and includes multiple first thermoelectric conversion elements 31. Each first thermoelectric conversion element 31 has a ring structure, wherein each first thermoelectric conversion element 31 is sleeved on the condenser section 22 of a heat pipe 20, and the first thermoelectric conversion element 31 and the condenser section 22 are thermally connected, meaning that the first thermoelectric conversion element 31 and the condenser section 22 are connected in a heat-exchangeable manner to transfer the heat transferred by the heat pipe 20 to the thermoelectric conversion module 30, where it is converted into electrical energy. For example, the thermoelectric conversion module 30 can be a thermoelectric generator, a thermionic conversion element, etc.

[0029] The first cooling chamber 41 is used for coolant flow. The first cooling chamber 41 is located outside the reactor core and spaced apart from it. Multiple first thermoelectric conversion elements 31 are located inside the first cooling chamber 41, with the coolant within the first cooling chamber 41 cooling the first thermoelectric conversion elements 31. It is understood that the heat transferred from the condensation section 22 of the heat pipe 20 to the first thermoelectric conversion elements 31 cannot be fully utilized by the first thermoelectric conversion elements 31; some heat remains and accumulates, causing the temperature of the first thermoelectric conversion elements 31 and the condensation section 22 of the heat pipe 20 to continuously rise. To prevent heat accumulation, in this embodiment, the first cooling chamber 41 is provided outside the multiple first thermoelectric conversion elements 31 and multiple heat pipes 20. By allowing coolant to flow through the first cooling chamber 41, the heat accumulated around the first thermoelectric conversion elements 31 and the condensation section 22 of the heat pipe 20 can be carried away, enabling the first thermoelectric conversion elements 31 and the condensation section 22 of the heat pipe 20 to operate continuously and stably.

[0030] The first coolant inlet 411 is connected to the first cooling chamber 41 and is used to introduce coolant into the first cooling chamber 41; the first coolant outlet 412 is connected to the first cooling chamber 41 and is used to draw out the coolant from the first cooling chamber 41. The coolant circulates within the first cooling chamber 41 through the first coolant inlet 411 and the first coolant outlet 412. The coolant can be a sodium-potassium alloy.

[0031] The nuclear power source provided in this application embodiment extracts heat from the reactor core via heat pipe 20. Simultaneously, the thermoelectric conversion element has a ring structure that can be fitted onto the condensation section 22 of the heat pipe 20, thereby increasing the connection strength and thermal conductivity area between the thermoelectric conversion element and the heat pipe 20, enabling the thermoelectric conversion element to operate stably and efficiently for a longer period. Furthermore, the nuclear power source is also equipped with a cooling chamber, through which flowing coolant extracts excess heat from the thermoelectric conversion element, further ensuring the stability of the thermoelectric conversion element during long-term operation.

[0032] In some embodiments, the first thermoelectric conversion element 31 is a thermoelectric power generation element, with its hot end and cold end located radially inner and radially outer sides of the annular structure, respectively. The hot end of the thermoelectric power generation element is thermally connected to the condensation section 22, and the coolant in the first cooling chamber 41 cools the cold end of the thermoelectric power generation element. Exemplarily, the thermoelectric power generation element can specifically be a lead telluride (PbTe) thermoelectric power generation element. When the thermoelectric power generation element is operating, the hot end temperature is approximately 525 degrees Celsius, and the cold end temperature is approximately 210 degrees Celsius.

[0033] In this embodiment, the thermoelectric generator generates electricity through the temperature difference between its hot and cold ends. The thermoelectric generator is a static generator, meaning there are no moving parts in the entire nuclear power source, thus ensuring stable performance and enabling it to provide stable power for extended periods. The hot and cold ends of the thermoelectric generator are radially distributed along the annular structure of the generator. The inner radial side of the thermoelectric generator is connected to the condenser section 22 of the heat pipe 20, receiving heat released from the condenser section 22, thus serving as the hot end of the thermoelectric generator. The outer radial side of the thermoelectric generator is connected to the first cooling chamber 41, being cooled by the coolant in the first cooling chamber 41, thus serving as the cold end of the thermoelectric generator. In this embodiment, the thermoelectric generator is annular, with its interior thermally connected to the condenser section 22 of the heat pipe 20 and its exterior in contact with the coolant; this design provides better thermoelectric conversion efficiency.

[0034] like Figure 6 , Figure 7 and Figure 8As shown, in some embodiments, the first cooling chamber 41 includes a first annular collecting chamber 414, a second annular collecting chamber 413, and a first connecting channel 416. The second annular collecting chamber 413 is coaxially arranged with the first annular collecting chamber 414 and is closer to the reactor core. Multiple first connecting channels 416 extend axially to connect the first annular collecting chamber 414 and the second annular collecting chamber 413. Coolant enters the second annular collecting chamber 413 from the first coolant inlet 411, then flows through the multiple first connecting channels 416 to the first annular collecting chamber 414 and re-converges, finally exiting the first cooling chamber 41 from the first coolant outlet 412.

[0035] In this embodiment, the coolant is gathered by setting an annular collection cavity, and multiple first connecting channels 416 are used to cool multiple first thermoelectric conversion elements 31 respectively, so that the coolant has a better cooling effect on the first thermoelectric conversion elements 31, maintaining the temperature difference between the cold end and the hot end of the first thermoelectric conversion elements 31, and improving the thermoelectric conversion efficiency.

[0036] like Figure 9 and Figure 10 As shown, in some embodiments, the first cooling cavity 41 further includes a plurality of axially extending receiving cavities 415. Each receiving cavity 415 is formed radially inside the first connecting channel 416, and each first thermoelectric conversion element 31 is located within a receiving cavity 415. The receiving cavities 415 and the first connecting channel 416 may share the inner wall of the annular first cooling cavity 41, and the first thermoelectric conversion element 31 may be insulated from the first cooling cavity 41.

[0037] In this embodiment, the first thermoelectric conversion element 31 is disposed in the receiving cavity 415 on the radially inner side of the first connecting channel 416, which makes it easier for the first thermoelectric conversion element 31 to be cooled by the coolant in the first cooling cavity 41, and at the same time makes the first thermoelectric conversion element 31 more stable and reliable connected to the first cooling cavity 41.

[0038] In some embodiments, the cross-sectional dimensions of the first annular collecting cavity 414 and the second annular collecting cavity 413 are the same, and the annular width of the first annular collecting cavity 414 and the second annular collecting cavity 413 is greater than the diameter of the first connecting channel 416. In this embodiment, this arrangement allows the coolant to enter the second annular collecting cavity 413, flow along the second annular collecting cavity 413, and enter the first annular collecting cavity 414 through multiple connecting channels. The coolant then flows within the first annular collecting cavity 414 and exits from the outlet, resulting in a more uniform flow of coolant and a better cooling effect.

[0039] In some embodiments, the first coolant inlet 411 is connected to the second annular manifold 413, and the first coolant outlet 412 is connected to the first annular manifold 414. In this embodiment, coolant can be introduced into the second annular manifold 413 through the first coolant inlet 411, and coolant in the first annular manifold 414 can be drawn out through the first coolant outlet 412.

[0040] In some embodiments, the thermoelectric conversion module 30 further includes a second thermoelectric conversion element 32. There may be multiple second thermoelectric conversion elements 32, which are disposed outside the core and between the core and multiple first thermoelectric conversion elements 31. The second thermoelectric conversion element 32 has the same or similar structure as the first thermoelectric conversion element 31, and the second thermoelectric conversion element 32 may have a ring structure.

[0041] The connection between the second thermoelectric conversion element 32 and the heat pipe 20 can be the same as or similar to that of the first thermoelectric conversion element 31. Each second thermoelectric conversion element 32 can be fitted onto the condenser section 22 of a heat pipe 20, and the second thermoelectric conversion element 32 is thermally connected to the condenser section 22 to convert the heat transmitted by the heat pipe 20 into electrical energy.

[0042] A second thermoelectric conversion element 32 and a first thermoelectric conversion element 31 can be simultaneously mounted on the same heat pipe 20. The second thermoelectric conversion element 32 and the first thermoelectric conversion element 31 can be mounted at different positions on the same heat pipe 20. Each first thermoelectric conversion element 31 is mounted on the section of the heat pipe 20 away from the reactor core, and each second thermoelectric conversion element 32 is mounted on the section of the same heat pipe 20 closer to the reactor core.

[0043] In this embodiment, by providing a second thermoelectric conversion element 32, the second thermoelectric conversion element 32 can operate independently of the first thermoelectric conversion element 31. Even if one thermoelectric conversion element malfunctions, the others can still operate normally, avoiding single-point failure and thus increasing the reliability of the nuclear power source. It is understood that in other embodiments of this application, the nuclear power source may also include a third thermoelectric conversion element, a fourth thermoelectric conversion element, etc., with a structure and arrangement similar to the first thermoelectric conversion element 31 and the second thermoelectric conversion element 32, to further increase the reliability of the nuclear power source.

[0044] like Figure 6 , Figure 11 and Figure 12As shown, in some embodiments, the nuclear power source further includes a second cooling chamber 42. The second cooling chamber 42 is used for coolant flow and is disposed outside the reactor core and between the reactor core and a plurality of first thermoelectric conversion elements 31. The plurality of second thermoelectric conversion elements 32 are located within the second cooling chamber 42, and are cooled by the coolant within the second cooling chamber 42 as the cold end of the second thermoelectric conversion elements 32. A second coolant inlet, communicating with the second cooling chamber 42, is used to introduce coolant into the second cooling chamber 42; and a second coolant outlet, communicating with the second cooling chamber 42, is used to extract the coolant from the second cooling chamber 42.

[0045] In this embodiment, by providing a second cooling chamber 42, the second cooling chamber 42 can operate independently of the first cooling chamber 41. Even if one cooling chamber malfunctions, the others can still function normally, avoiding single-point failure and thus increasing the reliability of the nuclear power source. It is understood that in other embodiments of this application, the nuclear power source may also include a third cooling chamber, a fourth cooling chamber, etc., with a structure and arrangement similar to the first cooling chamber 41 and the second cooling chamber 42, to further increase the reliability of the nuclear power source.

[0046] like Figure 1 , Figure 3 , Figure 11 and Figure 12 As shown, in some embodiments, the nuclear power source also includes a first radiator 51, a first pump 71, a second radiator 52, and a second pump 72.

[0047] The first radiator 51 is used to dissipate heat from the coolant from the first coolant outlet 412; the first pump 71 is used to circulate the dissipated coolant back to the first coolant inlet 411; the second radiator 52 is used to dissipate heat from the coolant from the second coolant outlet; the second pump 72 is used to circulate the dissipated coolant back to the second coolant inlet, wherein the first radiator 51 and the second radiator 52 are connected, and the first radiator 51 is closer to the reactor core. Both the first pump 71 and the second pump 72 can be electromagnetic pumps to drive the coolant circulation.

[0048] In this embodiment, the first radiator 51 and the first pump 71 dissipate heat from the coolant in the first cooling chamber 41, while the second radiator 52 and the second pump 72 dissipate heat from the coolant in the second cooling chamber 42. By providing the second radiator 52 and the second pump 72, they can operate independently of the first radiator 51 and the first pump 71. If one radiator or pump fails to operate normally, the others can still function normally, avoiding single-point failure and thus increasing the reliability of the nuclear power supply.

[0049] In some embodiments, the nuclear power source further includes a first volume compensator 515 and a second volume compensator 525, which are used to compensate for the volume of the coolant in the first cooling chamber 41 and the coolant in the second cooling chamber 42, respectively.

[0050] In some embodiments, such as Figure 13 As shown, the first heat sink 51 includes a first collector ring 511, a second collector ring 512, a first connecting pipe 513, and a first heat sink 514; as Figure 12 As shown, the second heat sink 52 includes a third collector ring 521, a fourth collector ring 522, a second connecting pipe 523, and a second heat sink 524.

[0051] The first collector ring 511 is connected to the first coolant outlet 412 via a pipe; the second collector ring 512 is connected to the first coolant inlet 411 via a pipe, and the second collector ring 512 is further away from the reactor core than the first collector ring 511. There can be multiple first connecting pipes 513, which connect the first collector ring 511 and the second collector ring 512, allowing coolant in the first collector ring 511 to flow into the second collector ring 512 through the multiple first connecting pipes 513; there can also be multiple first heat sinks 514, each welded to a first connecting pipe 513 for heat dissipation from the first connecting pipe 513. The first heat sink 514 can be made of aluminum.

[0052] The third collector ring 521 is connected to the second coolant outlet via a pipe; the fourth collector ring 522 is connected to the second coolant inlet via a pipe, and the fourth collector ring 522 is further away from the reactor core than the third collector ring 521; there can be multiple second connecting pipes 523, which are used to connect the third collector ring 521 and the fourth collector ring 522, and the coolant in the third collector ring 521 flows into the fourth collector ring 522 through the multiple second connecting pipes 523; there can be multiple second heat sinks 524, each of which is welded to a second connecting pipe 523 for heat dissipation of the second connecting pipe 523. The material of the second heat sink 524 can be aluminum.

[0053] In this embodiment, each radiator includes two collector rings connected by multiple connecting pipes. The working medium in one collector ring of each radiator can flow to the other collector ring through the connecting pipes, thereby achieving the circulation of the working medium. Each connecting pipe is welded with a heat sink, through which heat can be discharged into outer space. The heat sink increases the heat dissipation area of ​​the connecting pipe, allowing more heat to be dissipated as the working medium flows through the connecting pipe, thus achieving the cooling of the coolant.

[0054] In some embodiments, the third current collector 521 is connected to the second current collector 512, and the first heat sink 51 and the second heat sink 52 are generally in the shape of a frustum, with the thermoelectric conversion module 30 disposed radially inside the frustum structure. This arrangement allows the nuclear power supply to be more compact, reducing its overall size.

[0055] In some embodiments, the nuclear power source further includes a shield 60. The shield 60 is disposed between the reactor core and the thermoelectric conversion module 30, and multiple heat pipes 20 extend through the shield 60 toward the thermoelectric conversion module 30. The reactor core generates nuclear radiation during operation; to prevent damage to the thermoelectric conversion module 30 from nuclear radiation, a shield 60 is provided between the reactor core and the thermoelectric conversion module 30. Multiple heat pipes 20 can extend from the reactor core, pass through the shield 60, and continue toward the thermoelectric conversion module 30 to transfer heat to the thermoelectric conversion module 30.

[0056] See Figure 4 In some embodiments, the condensing sections 22 of multiple heat pipes 20 are all located on a first cylindrical surface, and the evaporating sections 21 of multiple heat pipes 20 are all located on a second cylindrical surface. The diameter of the second cylindrical surface is smaller than the diameter of the first cylindrical surface, meaning that the evaporating sections 21 and condensing sections 22 of the heat pipes 20 are not on the same axis. The smaller diameter of the second cylindrical surface compared to the first cylindrical surface facilitates the installation of the evaporating sections 21 in the reactor core.

[0057] The heat pipe 20 located within the shield 60 includes: a first straight pipe section coaxial with the evaporation section 21, a second straight pipe section coaxial with the condensation section 22, and a third straight pipe section connecting the first and second straight pipe sections, wherein the axis of the third straight pipe section forms an angle with the axis of the first straight pipe section.

[0058] It is understood that the cavity of the heat pipe 20 cannot shield nuclear radiation. Therefore, in this embodiment, the heat pipe 20 is divided into three sections within the shielding body 60. The first straight section can be arranged parallel to but not collinear with the second straight section. The axis of the third straight section forms an angle with the axes of the first and second straight sections. In this way, the heat pipe 20 forms two bends with a certain angle within the shielding body 60. The nuclear radiation generated by the reactor core cannot reach the thermoelectric conversion module 30 through the cavity of the heat pipe 20, thereby extending the service life of the thermoelectric conversion module 30.

[0059] like Figure 5 As shown, in some embodiments, the reactor core includes a fuel block 11, a radial reflector layer 12, a control drum 14, and an axial reflector layer 13.

[0060] The fuel block 11 has multiple slots extending axially, which are distributed around the axis of the fuel block 11. The slots are used to install the evaporation section 21 of the heat pipe 20.

[0061] A safety rod channel 15 can also be formed in the middle of the fuel block 11. The safety rod channel 15 is used to install safety rods. The safety rods can be made of boron carbide and are used to ensure that the reactor remains in a subcritical safety state in the event of a launch fall accident.

[0062] A radial reflector layer 12 is disposed on the radial outer side of the fuel block 11. The radial reflector layer 12 is used to prevent radiation and heat generated by the fuel block 11 from leaking radially along the reactor core. The radial reflector layer 12 can be made of beryllium.

[0063] Multiple control drums 14 can be provided. These control drums 14 are disposed within the radial reflector layer 12. The control drums 14 are used to regulate the nuclear fission reaction rate of the fuel block 11, thereby controlling the reactor power. The main body material of the control drum 14 can be beryllium oxide, and the absorber material can be boron carbide, with an absorber angle of 120°. A control drum drive mechanism 61 can also be provided on the shield 60, which drives the control drums 14 to rotate, thereby controlling the reactor power.

[0064] There can be two axial reflector layers 13, each disposed at one end of the axial direction of the fuel block 11. The evaporation section 21 of each heat pipe 20 passes through one axial reflector layer 13 and is inserted into a slot in the fuel block 11. The axial reflector layers 13 prevent radiation and heat generated by the fuel elements from leaking along the axial direction of the reactor core. The axial reflector layers 13 can be made of beryllium.

[0065] After the nuclear power source is successfully launched, the safety rod drive mechanism ejects the safety rod from the reactor core 10. Then, under the action of the control drum drive mechanism 61, the control drum absorber is slowly turned away from the fuel block 11 until the reactor core 10 reaches the rated power stable operating state. During reactor operation, fuel block 11 generates thermal power, which is transferred to heat pipe 20 through heat conduction. Heat pipe 20 transfers the thermal power to the rear end of shield 60 through the phase change and circulation of internal potassium working fluid, and then enters the hot end of thermoelectric generator. The thermoelectric generator converts a portion of the thermal energy into electrical energy, and the remaining waste heat is transferred to the sodium-potassium working fluid in the cooling chamber through the cold end of the thermoelectric generator. Driven by an electromagnetic pump, the sodium-potassium working fluid carries the waste heat out of the cooling chamber and into the sodium-potassium working fluid pipeline and the collector ring of the radiator. The sodium-potassium working fluid enters the sodium-potassium pipeline from the collector ring, and the waste heat it carries is discharged into space through radiation by the heat sink. Then the sodium-potassium working fluid enters the collector ring at the other end of the pipeline and flows out of the collector ring into the sodium-potassium working fluid pipeline. After being pressurized by the electromagnetic pump, it re-enters the cooling chamber, and the cycle continues.

[0066] In some embodiments, the nuclear power source has a core thermal power of approximately 20 kW and an electrical power of approximately 1 kW. The maximum temperature of the bulk uranium-molybdenum alloy (U-8%Mo) is approximately 600°C, the temperature of the evaporation section of heat pipe 20 is approximately 550°C, the hot-end temperature of the thermoelectric generator is approximately 525°C, the cold-end temperature is approximately 210°C, the total area of ​​the heat sink is approximately 7 square meters, and the system conversion efficiency is conservatively estimated at approximately 5%. The electrical power of this nuclear power source is expected to be expandable to 10 kW, and the specific core dimensions, number of heat pipes 20, heat sink area, and other parameters can be designed according to actual power requirements.

[0067] In this embodiment, the sodium-potassium loop is located at the cold end of the thermoelectric element and is used to discharge waste heat. Therefore, compared with traditional loop-type space reactors (which use the sodium-potassium loop as a primary loop to remove heat from the reactor core, with an operating temperature exceeding 500°C), the sodium-potassium loop operating temperature in this scheme (approximately 200°C) is much lower, resulting in lower requirements for the electromagnetic pump. In this embodiment, the blocky uranium-molybdenum alloy (U-8%Mo) has a maximum operating temperature of approximately 600°C, thus providing a large thermal safety margin. This reduces the difficulty of material development while also contributing to the safety and reliability of the system.

[0068] The above are merely embodiments of this application and do not limit the patent scope of this application. Any equivalent structural or procedural transformations made using the content of this application's specification and drawings, or direct or indirect applications in other related technical fields, are similarly included within the patent protection scope of this application.

Claims

1. A nuclear power source, comprising: The reactor core is used to provide heat; Multiple heat pipes, with the evaporation section of each heat pipe inserted into the core and the condensation section of each heat pipe extending outward from the core; A thermoelectric conversion module is disposed outside the core. The thermoelectric conversion module includes a plurality of first thermoelectric conversion elements. Each first thermoelectric conversion element has a ring structure. Each first thermoelectric conversion element is sleeved on the condensation section of a heat pipe and is thermally connected to the condensation section to convert the heat transmitted by the heat pipe into electrical energy. A first cooling chamber is provided for the flow of coolant. The first cooling chamber is disposed outside the core and spaced apart from the core. The plurality of first thermoelectric conversion elements are located inside the first cooling chamber so that the coolant inside the first cooling chamber cools the first thermoelectric conversion elements. The first coolant inlet is connected to the first cooling chamber and is used to introduce coolant into the first cooling chamber; The first coolant outlet is connected to the first cooling chamber and is used to draw out the coolant in the first cooling chamber. The first cooling chamber includes: First annular collecting cavity; The second annular current collection cavity is coaxially arranged with the first annular current collection cavity, and the second annular current collection cavity is closer to the core. Multiple axially extending first connecting channels are used to connect the first annular collection cavity and the second annular collection cavity.

2. The nuclear power source according to claim 1, wherein, The first thermoelectric conversion element is a thermoelectric power generation element, and the hot end and cold end of the thermoelectric power generation element are located on the radial inner side and radial outer side of the annular structure, respectively; The hot end of the thermoelectric generator is thermally connected to the condensation section, and the coolant in the first cooling chamber cools the cold end of the thermoelectric generator.

3. The nuclear power source according to claim 1, wherein, The first cooling chamber further includes: Multiple axially extending receiving cavities, each of which is formed radially inside the first connecting channel, and each of the first thermoelectric conversion elements is located within one of the receiving cavities.

4. The nuclear power source according to claim 1, wherein, The first annular collecting cavity and the second annular collecting cavity have the same cross-sectional dimensions and size, and the annular width of the first annular collecting cavity and the second annular collecting cavity is greater than the diameter of the first connecting channel.

5. The nuclear power source according to claim 1, wherein, The first coolant inlet is connected to the second annular manifold. The first coolant outlet is connected to the first annular manifold.

6. The nuclear power source according to claim 1, wherein, The thermoelectric conversion module also includes: A plurality of second thermoelectric conversion elements are disposed outside the core and between the core and the plurality of first thermoelectric conversion elements, wherein the second thermoelectric conversion elements have a ring structure. Each of the second thermoelectric conversion elements is fitted onto the condenser section of one of the heat pipes, and the second thermoelectric conversion element is thermally connected to the condenser section to convert the heat transferred by the heat pipe into electrical energy. Each of the first thermoelectric conversion elements is sleeved on the section of the heat pipe away from the core. Each of the second thermoelectric conversion elements is mounted on a section of the same heat pipe near the core.

7. The nuclear power source according to claim 6, further comprising: The second cooling chamber is used for the flow of coolant. The second cooling chamber is disposed outside the core and between the core and the plurality of first thermoelectric conversion elements. The plurality of second thermoelectric conversion elements are located inside the second cooling chamber so that the coolant inside the second cooling chamber cools the cold end of the second thermoelectric conversion elements. The second coolant inlet is connected to the second cooling chamber and is used to introduce coolant into the second cooling chamber; as well as The second coolant outlet is connected to the second cooling chamber and is used to draw out the coolant from the second cooling chamber.

8. The nuclear power source according to claim 7, further comprising: The first radiator is used to dissipate heat from the coolant from the first coolant outlet; The first pump is used to circulate the cooled coolant back to the first coolant inlet; The second radiator is used to dissipate heat from the coolant from the second coolant outlet; as well as The second pump is used to circulate the cooled refrigerant back to the second refrigerant inlet. The first heat sink is connected to the second heat sink, and the first heat sink is closer to the core.

9. The nuclear power source according to claim 8, wherein, The first heat sink includes: The first manifold ring is connected to the first coolant outlet via a pipeline; The second collector ring is connected to the first coolant inlet via a pipeline, and the second collector ring is farther away from the reactor core than the first collector ring. Multiple first connecting pipes are used to connect the first collector ring and the second collector ring, through which coolant in the first collector ring flows into the second collector ring; and Multiple first heat sinks, each of which is welded to a first connecting pipe, are used to dissipate heat from the first connecting pipe, and / or The second heat sink includes: The third manifold is connected to the second coolant outlet via a pipeline; The fourth collector ring is connected to the second coolant inlet via a pipeline, and the fourth collector ring is farther away from the reactor core than the third collector ring; Multiple second connecting pipes are used to connect the third manifold and the fourth manifold, through which coolant in the third manifold flows into the fourth manifold; and Multiple second heat sinks are provided, each of which is welded to a second connecting pipe for heat dissipation of the second connecting pipe.

10. The nuclear power source according to claim 9, wherein, The third collector ring is connected to the second collector ring, and the first and second heat sinks are generally truncated cone structures. The thermoelectric conversion module is located on the radial inner side of the frustum structure.

11. The nuclear power source according to claim 1, further comprising: A shield is disposed between the reactor core and the thermoelectric conversion module. The multiple heat pipes extend through the shielding body toward the thermoelectric conversion module.

12. The nuclear power source according to claim 11, wherein, The condensation sections of the multiple heat pipes are all located on the first cylindrical surface, and the evaporation sections of the multiple heat pipes are all located on the second cylindrical surface. The diameter of the second cylindrical surface is smaller than the diameter of the first cylindrical surface. The heat pipe segment located within the shielding body includes: A first straight pipe section coaxial with the evaporation section, a second straight pipe section coaxial with the condensation section, and a third straight pipe section connecting the first straight pipe section and the second straight pipe section, wherein the axis of the third straight pipe section forms an angle with the axis of the first straight pipe section.

13. The nuclear power source according to claim 1, wherein, The core includes: A fuel block having a plurality of slots extending axially and distributed around the axis of the fuel block; A radial reflective layer is disposed on the radially outer side of the fuel block; Multiple control drums are disposed within the radial reflective layer; and Two axial reflective layers are respectively disposed at both ends of the fuel block. In this configuration, the evaporation section of each heat pipe is inserted into a slot of the fuel block through one of the axial reflective layers.

14. The nuclear power source according to claim 13, wherein, The fuel block is made of uranium-molybdenum alloy.

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