Hybrid nuclear energy system

Abstract

This application provides a hybrid nuclear energy system, including a fusion core adapted to radiate fusion products; a blanket device surrounding the fusion core to receive fusion products, the blanket device being adapted to contain blanket material, including fissile material; a fuel loop connected to the blanket device, the blanket material being adapted to circulate within the blanket device and the fuel loop; a heat exchange module adapted to contain heat exchange material, at least a portion of the fuel loop being located within the heat exchange module or the heat exchange module being at least partially located within the blanket device; and a cooling loop connected to the heat exchange module, the heat exchange material circulating within the heat exchange module and the cooling loop and exchanging heat with the blanket material. This application provides a hybrid nuclear energy system that can improve the system's energy gain factor and has stronger reliability and safety.

Description

Technical Field

[0001] This application relates primarily to the field of reactor technology, and more particularly to a hybrid nuclear energy system. Background Technology

[0002] Fusion energy primarily utilizes the fusion reaction of light nuclei such as deuterium and tritium to release energy. Its fuel sources are extremely abundant; seawater contains 45 trillion tons of deuterium, and the fusion energy of one liter of seawater is equivalent to the calorific value of 300 liters of gasoline. Fusion energy technologies are generally divided into two main categories: inertial confinement fusion and magnetic confinement fusion. The mainstream magnetic confinement device is the Kamak. Magnetic confinement tokamak devices (such as ITER and BEST) confine high-temperature plasma in a vacuum chamber using a circumferential magnetic field, achieving the fusion reaction conditions: plasma temperatures exceeding 150 million degrees Celsius, approximately 10 times the temperature of the sun's core, and a density exceeding 10²⁰ m³ / s. -3 The energy confinement time exceeds 5 seconds. The fusion process produces only inert helium and neutrons, without generating large amounts of radioactive waste, and possesses inherent safety (such as automatic flameout in case of instability) and environmental friendliness. Currently, more than 60 experimental devices have been built worldwide, verifying the scientific feasibility of deuterium-tritium fusion, with neutron flux output reaching the order of 10¹⁹ n / s.

[0003] Fission energy releases energy through a chain reaction of heavy nuclei such as uranium and plutonium, and its technological maturity ranks among the top mainstream energy sources. Currently, there are 432 operating units worldwide, with a total installed capacity of 392 GWe, providing 10% of global electricity. Fission reactors have high energy density; the energy released by the fission of 1 kg of uranium-235 is equivalent to 2700 tons of coal, and the fuel supply system is complete—a complete industrial chain has been formed from uranium mining and enrichment to fuel manufacturing. Among them, pressurized water reactors (PWRs) use light water for moderation / cooling, employ highly enriched low-enriched uranium (HALEU) fuel, have a thermal efficiency exceeding 30%, and have high technological maturity, making them the main reactor type currently used in commercial applications. Fast neutron reactors can utilize high-energy neutrons to breed nuclear fuel, which can greatly improve the utilization rate of uranium resources and ensure energy supply. Fourth-generation reactors such as molten salt reactors can raise the coolant outlet temperature to over 700°C, improving thermoelectric conversion efficiency and supporting the comprehensive utilization of nuclear energy.

[0004] However, both technologies still face significant challenges in their application. The challenges for commercial fusion reactor applications include: first, the energy gain factor (Q-value), a core indicator of fusion device performance defined as the ratio of fusion output energy to external heating energy; a Q-value less than 1 indicates a net energy deficit, hindering engineering applications; second, insufficient material tolerance, as fusion reactor materials must withstand the synergistic effects of high temperatures and intense neutron radiation (annual dose > 100 dpa); and third, difficulties in tritium self-sustaining cycling, with low tritium breeding ratio (TBR) in tritium breeding blankets making it difficult to maintain a closed fuel cycle. These challenges limit the engineering progress of fusion reactors. The challenges facing fission reactors include: first, the difficulty of radioactive waste management, with long-lived fission products and minor actinides being difficult to handle, and high costs and low public acceptance for safe storage and reprocessing; second, significant safety risks, as some serious accidents may still release large amounts of radioactive material despite the design of redundant protection systems, requiring strict accident prevention and emergency response; and third, resource sustainability issues, with limited reserves of fissile materials, and approximately 6 million tons of recoverable uranium ore globally, facing long-term supply pressure. Summary of the Invention

[0005] The technical problem to be solved by this application is to provide a hybrid nuclear energy system that can improve the system's energy gain factor and has stronger reliability and safety.

[0006] To address the aforementioned technical problems, this application provides a hybrid nuclear energy system, comprising: a fusion core adapted to radiate fusion products; a blanket device disposed around the fusion core to receive the fusion products, the blanket device being adapted to contain blanket material, the blanket material including fissile material; a fuel loop connected to the blanket device, the blanket material being adapted to circulate within the blanket device and the fuel loop; a heat exchange module adapted to contain heat exchange material, at least a portion of the fuel loop being located within the heat exchange module or the heat exchange module being at least partially located within the blanket device; and a cooling loop connected to the heat exchange module, the heat exchange material circulating within the heat exchange module and the cooling loop and exchanging heat with the blanket material.

[0007] Optionally, the cladding device includes a plurality of cladding modules, and each cladding module includes a plurality of cladding units.

[0008] Optionally, the fuel circuit further includes a recovery device and / or a fuel power pump, the recovery device being adapted to recover the fusion material.

[0009] Optionally, the recovery device includes an exhaust gas treatment module, an adsorber, a storage tank, a degassing module, and / or a compressor, wherein the compressor is connected to the fusion core.

[0010] Optionally, the heat exchange module includes a main heat exchanger, at least a portion of the fuel circuit is located inside the main heat exchanger, the heat exchange material is located inside the main heat exchanger, the fuel circuit located inside the main heat exchanger is independent of the heat exchange material, and the cooling circuit is connected to the main heat exchanger.

[0011] Optionally, the heat exchange module includes a heat exchange tube bundle, at least a portion of which is located within the cladding module, the cooling heat exchange circuit is connected to the heat exchange tube bundle, and the heat exchange material is adapted to flow within the heat exchange tube bundle and the cooling circuit.

[0012] Optionally, the heat exchange material includes cooling molten salt.

[0013] Optionally, the cladding material further includes convertible nuclides, including thorium-232 and / or uranium-238, and the fissile material includes uranium-233, uranium-235 and / or plutonium-239.

[0014] Optionally, the fusion material includes deuterium and / or tritium, and the fusion products include high-energy neutrons.

[0015] Optionally, the cooling circuit further includes a cooling circuit pump adapted to power the heat exchange material, and the energy conversion module includes a steam generator.

[0016] Optionally, a communication interface is included between two adjacent cladding modules.

[0017] Optionally, the cooling circuit includes an energy conversion module adapted to convert heat from the heat exchange material, and the energy conversion module includes a steam generator.

[0018] Optionally, at least some of the cladding units include a slowing block, and the cladding unit is a detachable unit.

[0019] Optionally, the cladding unit in each cladding module is in communication with the adjacent cladding unit, and the cladding material is adapted to flow along the cladding module within the cladding device.

[0020] Optionally, the multiple cladding modules have the same structure, each cladding module is closely fitted with the adjacent cladding module, and the cladding unit in each cladding module is connected to the cladding unit in the adjacent cladding module at the corresponding position.

[0021] Compared with existing technologies, this application utilizes a hybrid nuclear energy system to efficiently utilize neutrons generated by fusion, amplifying energy output through fission and significantly improving the system's energy gain factor. Furthermore, the use of a blanket device allows the functional unit to be divided into multiple blanket units, enabling replacement of specific blanket units when problems arise, thus improving system maintainability and scalability. Moreover, the inclusion of a recovery device enables the recovery of fusion materials, significantly reducing the system's dependence on external fusion material supplies and providing crucial support for the system's long-term stable operation. Attached Figure Description

[0022] The accompanying drawings are included to provide a further understanding of this application; they are incorporated into and constitute a part of this application. The drawings illustrate embodiments of this application and, together with this specification, serve to explain the principles of this application. In the drawings: Figure 1 This is a schematic diagram of the structure of a hybrid nuclear energy system according to one embodiment of this application; Figure 2 This is a schematic diagram of the structure of a recovery device in a hybrid nuclear energy system according to an embodiment of this application. Figure 3 This is a partial structural schematic diagram of a hybrid nuclear energy system according to another embodiment of this application; Figure 4 This is a schematic diagram of a hybrid nuclear energy system according to another embodiment of this application. Detailed Implementation

[0023] To more clearly illustrate the technical solutions of the embodiments of this application, the accompanying drawings used in the description of the embodiments will be briefly introduced below. Obviously, the drawings described below are merely some examples or embodiments of this application. For those skilled in the art, these drawings can be applied to other similar scenarios without creative effort. Unless obvious from the context or otherwise specified, the same reference numerals in the drawings represent the same structures or operations.

[0024] As indicated in this application and claims, unless the context clearly indicates otherwise, the words "a," "an," "an," and / or "the" are not specifically singular and may include plural forms. Generally speaking, the terms "comprising" and "including" only indicate the inclusion of explicitly identified steps and elements, which do not constitute an exclusive list, and the method or apparatus may also include other steps or elements.

[0025] Unless otherwise specifically stated, the relative arrangement, numerical expressions, and values ​​of the components and steps described in these embodiments do not limit the scope of this application. It should also be understood that, for ease of description, the dimensions of the various parts shown in the drawings are not drawn to actual scale. Techniques, methods, and devices known to those skilled in the art may not be discussed in detail, but where appropriate, such techniques, methods, and devices should be considered part of the specification. In all examples shown and discussed herein, any specific values ​​should be interpreted as merely exemplary and not as limitations. Therefore, other examples of exemplary embodiments may have different values. It should be noted that similar reference numerals and letters in the following drawings denote similar items; therefore, once an item is defined in one drawing, it need not be further discussed in subsequent drawings.

[0026] In the description of this application, it should be understood that the orientation or positional relationship indicated by directional terms such as "front, back, up, down, left, right", "horizontal, vertical, horizontal" and "top, bottom" is usually based on the orientation or positional relationship shown in the accompanying drawings, and is only for the convenience of describing this application and simplifying the description. Unless otherwise stated, these directional terms do not indicate or imply that the device or element referred to must have a specific orientation or be constructed and operated in a specific orientation, and therefore should not be construed as a limitation on the scope of protection of this application; the directional terms "inner" and "outer" refer to the inner and outer contours relative to the outline of each component itself.

[0027] For ease of description, spatial relative terms such as "above," "on top of," "on the upper surface of," "above," etc., are used herein to describe the spatial positional relationship of a device or feature as shown in the figures to other devices or features. It should be understood that spatial relative terms are intended to encompass different orientations in use or operation beyond the orientation of the device as described in the figures. For example, if the device in the figures were inverted, a device described as "above" or "on top of" other devices or structures would subsequently be positioned as "below" or "under" other devices or structures. Thus, the exemplary term "above" can include both "above" and "below." The device may also be positioned in other different ways (rotated 90 degrees or in other orientations), and the spatial relative descriptions used herein will be interpreted accordingly.

[0028] Furthermore, it should be noted that the use of terms such as "first" and "second" to define components is merely for the purpose of distinguishing the corresponding components. Unless otherwise stated, these terms have no special meaning and therefore should not be construed as limiting the scope of protection of this application. In addition, although the terminology used in this application is selected from commonly known and used terms, some terms mentioned in this application's specification may have been chosen by the applicant according to his or her judgment, and their detailed meanings are explained in the relevant sections of this description. Moreover, this application should be understood not only through the actual terms used, but also through the meaning implied by each term.

[0029] This application refers to Figure 1 A hybrid nuclear energy system 10 is shown, with reference to Figure 3 A hybrid nuclear energy system 20 is shown, with reference to Figure 4 A hybrid system 30 is shown. The hybrid nuclear energy systems proposed in any embodiment of this application, such as the hybrid nuclear energy system 10, hybrid nuclear energy system 20, and hybrid nuclear energy system 30 described above, all include a blanket device 11, a fusion core 12, a fuel loop 13, a heat exchange module 14, and a cooling loop 15. Exemplarily, the fuel loop 13 and cooling loop 15 include loop pipes and valves (not shown), and the fuel loop 13 and cooling loop 15 operate at atmospheric pressure.

[0030] Specifically, Figure 1 , Figure 2 as well as Figure 3 The arrows indicate the flow direction of the cladding material. Figure 4 The arrows indicate the flow direction of the heat exchange material. Specifically, the fusion core 12 is adapted to radiate fusion products; the blanket device 11 is arranged around the fusion core 12 to receive fusion products, and the blanket device 11 is adapted to contain blanket material, including fissile material; the fuel loop 13 is connected to the blanket device 11, and the blanket material is adapted to circulate within the blanket device 11 and the fuel loop 13; the heat exchange module 14 is adapted to contain heat exchange material, and at least a portion of the fuel loop 13 is located within the heat exchange module 14 or at least a portion of the heat exchange module 14 is located within the blanket device 11; the cooling loop 15 is connected to the heat exchange module 14, and the heat exchange material circulates within the heat exchange module 14 and the cooling loop 15, exchanging heat with the blanket material.

[0031] For example, the blanket material is a liquid lithium-containing fuel molten salt, and each blanket unit 22 contains the blanket material. Preferably, in this embodiment, fissile material is added to the blanket material. The fissile material includes uranium and / or thorium. In this embodiment, the fissile material includes uranium-233, uranium-235, and / or plutonium-239. Preferably, the blanket material also includes convertible nuclides, including thorium-232 and / or uranium-238. On the other hand, the fusion material includes deuterium and tritium, and the fusion products include high-energy neutrons. The heat exchange material includes a cooling molten salt.

[0032] For example, adding uranium as fissile fuel can utilize depleted uranium from the tailings of the uranium enrichment industry. Uranium-238 in this fuel is gradually converted into plutonium-239 under neutron irradiation, achieving the conversion and utilization of uranium-238 to plutonium-239, thus forming a uranium-plutonium cycle. Alternatively, thorium can be added as a convertible material to the fuel molten salt. Thorium-232 undergoes a two-step decay under neutron irradiation to generate fissile uranium-233, constructing a fuel breeder pathway from thorium-232 to uranium-233, achieving a thorium-uranium cycle. Compared to the uranium-plutonium cycle, the thorium-uranium cycle has advantages such as more abundant resources, fewer minor actinide nuclides produced, and lower toxicity of radioactive waste. This alternative provides a sustainable, environmentally friendly, and safer option for the nuclear fuel cycle.

[0033] On the other hand, depleted uranium, whose main component is uranium-238, is used as the convertible material, and the conversion of plutonium-239 mainly relies on fusion neutrons to initiate it. In other embodiments of this application, low-enriched uranium or uranium-thorium mixed fuel can be used instead of depleted uranium as the initial fuel in the blanket device 11. Introducing low-enriched uranium with a uranium-235 enrichment of 5% to 20% can significantly improve the initial fission capability of the system and enhance the initial energy output; at the same time, it increases neutron output and accelerates the fuel cycle establishment process. Mixing low-enriched uranium with thorium in a certain proportion to form uranium-thorium mixed fuel not only utilizes the low-enriched uranium to provide initiation reactivity, but also takes advantage of the ability of thorium-232 to be efficiently converted into uranium-233 under neutron irradiation, gradually building a combined cycle of thorium and uranium-plutonium, which can balance energy output and resource sustainability.

[0034] Preferably, high-energy neutrons and long-lived radionuclides have a larger nuclear reaction cross-section, making them particularly suitable for efficient transmutation. In the hybrid nuclear energy system provided in any embodiment of this application, the 14 MeV high-energy neutrons generated by fusion, after entering the blanket device 11, can not only be used to drive fission and breeding, but also undergo fission or capture reactions with minor actinides such as neptunium, americium, and curium, as well as long-lived fission products such as technetium-99 and iodine-129 in the blanket material, converting them into short-lived or stable nuclides. Compared with thermal neutron systems, fast neutrons have significantly higher transmutation efficiency for these difficult-to-process nuclides, especially effectively initiating fission of minor actinides rather than simple capture, thereby completely eliminating their long-term radiotoxicity. This function enables the system to play a dual role as an energy producer and a nuclear waste "cleaner," promoting the development of nuclear energy towards near-zero emissions and environmental friendliness.

[0035] Furthermore, in natural lithium, lithium-6 accounts for approximately 7.5%, and lithium-7 accounts for approximately 92.5%. In conventional fission reactors, lithium-6 absorbs a large number of neutrons to generate tritium and alpha particles, reducing the available neutrons and leading to reactive poisoning. This prevents the reactor from reaching criticality, and the chain fission reaction cannot be self-sustaining. Therefore, enriched lithium-7 must be used to reduce neutron absorption. However, in the hybrid nuclear energy system proposed in any embodiment of this application, neutrons mainly originate from the fusion core 12, and the blanket device 11 is in a subcritical state, not relying on a self-sustaining chain reaction. Even if lithium-6 absorbs some neutrons, it will not affect the overall reaction continuity. Therefore, the system can directly use natural lithium or unenriched lithium to prepare the blanket material (fuel molten salt), which simplifies the molten salt preparation process and avoids the technical barriers and increased costs caused by lithium isotope separation, thus improving economic efficiency and engineering feasibility.

[0036] Furthermore, the blanket device 11 remains subcritical under all operating conditions, with the fission reaction entirely dependent on the fusion neutron source. This design ensures an effective multiplication factor k by precisely controlling the fuel concentration and geometry within the blanket. eff The neutron level remains consistently below 1, meaning the chain fission reaction cannot be self-sustaining and requires a continuous supply of high-energy neutrons from the fusion core 12 to sustain the fission process. Once the fusion reaction stops and the neutron source disappears, the fission reaction within the blanket rapidly decays to background levels. This fundamentally eliminates typical risks of traditional fission reactors, such as supercritical accidents, power runaway, or core meltdown, making it a core technology for ensuring nuclear safety.

[0037] For example, the fusion materials deuterium and tritium undergo a fusion reaction in the fusion core 12 to produce a large number of high-energy neutrons. The high-energy neutrons enter the blanket unit 22 in the blanket device 11. The high-energy neutrons react with the fissile material (uranium-233, uranium-235 and / or plutonium-239) in the blanket unit 22 to generate heat and release more neutrons. Some of the neutrons react with convertible nuclides (thorium-232, uranium-238, etc.) in the fuel molten salt to generate more fissile nuclides (which are fissile materials in this embodiment). Therefore, the increase and circulation of fissile materials can be automatically realized, thereby achieving the purpose of fissile material proliferation.

[0038] Furthermore, such as Figure 1 In the hybrid nuclear energy system 10 shown, when the heat exchange module 14 is located within the fuel loop 13, the heat exchange module 14 includes a main heat exchanger 31, at least part of the fuel loop 13 is located inside the main heat exchanger 31, the heat exchange material is located inside the main heat exchanger 31, and the fuel loop 13 located inside the main heat exchanger is independent of the heat exchange material. At this time, the cooling loop 15 is connected to the main heat exchanger 31.

[0039] Therefore, in such Figure 1 In the hybrid nuclear energy system 10 shown, the molten fuel salt continues to flow through the fuel loop 13 connected to the blanket device 11, such as... Figure 1 As shown, it is clear that part of the fuel circuit 13 is located inside the main heat exchanger 31. When the heat from the molten fuel enters the fuel circuit 13 inside the main heat exchanger 31, it exchanges heat with the cooling molten salt inside the main heat exchanger 31. After heat exchange, the molten fuel returns to the cladding device 11 through the fuel circuit 13, thus achieving the recycling of the molten fuel. The cooling molten salt then flows further into the cooling circuit 15 connected to the main heat exchanger 31, thereby transferring heat to the cooling circuit 15 through the cooling molten salt.

[0040] On the other hand, we can refer to Figure 4 , Figure 4 This application illustrates a hybrid nuclear energy system 30 according to another embodiment, in which the heat exchange module 14 is a heat exchange tube bundle 32, from... Figure 4 As can be seen, some of the heat exchange tube bundles 32 are located in the cladding module 21. Each cladding unit 22 contains a curved arrangement of heat exchange tube bundles 32. In this embodiment, the heat exchange material, cooling molten salt, is directly located in the heat exchange tube bundles 32, exchanging heat with the high-temperature fuel molten salt in the cladding device 11, thus achieving in-situ heat transfer. Meanwhile, the fuel molten salt in the cladding device 11 flows into the fuel circuit 13 and eventually returns to the cladding device 11 to achieve fuel molten salt recycling.

[0041] Furthermore, during operation, the molten fuel salt circulates within the cladding module 21, continuously transferring the heat generated by fission and fusion to the heat exchange tube bundle 32, enabling immediate heat removal. With this approach, the molten fuel salt flow rate only needs to consider online post-processing requirements, without needing to consider heat removal, significantly reducing the molten fuel salt flow rate and the requirements for the molten fuel salt pump. In addition, the heat exchange tube bundle 32 is designed to support passive waste heat removal, allowing waste heat to be discharged outside the containment via natural convection or radiation during accident conditions, enhancing intrinsic safety.

[0042] In the hybrid nuclear energy system 30, the heat exchange tube bundle 32 is made of high-temperature corrosion-resistant alloy. The integrated design of the heat exchange module 14 and the cladding device 11 significantly shortens the heat transfer path, reduces heat loss and thermal stress, and improves overall thermal efficiency. Simultaneously, it simplifies the structure of the hybrid nuclear energy system 30, reducing the safety risks and maintenance difficulties associated with the external transport of molten fuel salt. By eliminating the main heat exchanger and its connecting pipes, the equipment footprint is reduced, the system compactness is improved, facilitating modular construction and deployment. Furthermore, the system simplification also helps reduce costs and improve economic efficiency.

[0043] For example, fuel loop 13 also includes a recovery unit 34 and a fuel power pump 35, the recovery unit 34 being adapted to recover fusion materials. Figure 2As shown, the recovery device 34 includes an exhaust gas treatment module 41, an adsorber 42, a storage tank 43, a degassing module 44, and a compressor 46, wherein the compressor 46 is connected to the fusion core 12. A fuel power pump 35 is adapted to power the molten fuel salt, enabling the molten fuel salt to flow in the fuel loop 13.

[0044] Specifically, refer to Figure 2 Before entering the fuel power pump 35, the molten fuel salt first passes through a degassing module 44 to remove tritium and other gaseous products. It then enters a tail gas treatment module 41 to remove particulate matter and radioactive inert gases. The remaining tail gas enters an adsorber 42, where tritium is adsorbed, recovered, and temporarily stored in a storage tank 43. The temporarily stored tritium can be controlled by valves in the fuel circuit 13 and powered by a compressor 46 to be transported back to the fusion core 11 as needed to maintain tritium concentration balance and achieve tritium recycling. Preferably, tritium-blocking coatings are applied to the cladding unit 22, the pipelines of the fuel circuit 11, and the heat exchange module 14 to reduce tritium diffusion and permeation, thereby improving the tritium recovery rate and further reducing the possibility of tritium permeating into the environment.

[0045] On the other hand, the cooling circuit 15 also includes a cooling circuit pump 51, which is adapted to provide power to the heat exchange material. The cooling circuit 15 includes an energy conversion module 23, which is adapted to convert heat in the heat exchange material. The energy conversion module 23 includes a steam generator 52. For example, after absorbing heat in the main heat exchanger 31, the cooling molten salt enters the cooling circuit 15. At this time, the cooling circuit pump 51 provides power for the cooling molten salt to flow in the cooling circuit 15. Then, the cooling molten salt flows into the steam generator 52 to convert heat. Subsequently, the cooling molten salt returns to the main heat exchanger 31 to achieve circulation. In the energy conversion module 23, the heat can be used for comprehensive nuclear energy utilization such as power generation, heating, steam supply, power supply for the equipment, and seawater desalination.

[0046] Furthermore, refer to Figure 1 The hybrid nuclear energy system 10 shown Figure 3 The diagram shows a partial structural schematic of the hybrid nuclear energy system 20. The flow paths of the blanket material in the hybrid nuclear energy system 10 and the hybrid nuclear energy system 20 are different.

[0047] First refer to Figure 1 ,exist Figure 1 In the blanket device 11, the blanket unit 22 in each blanket module 21 is connected to the adjacent blanket unit 22 through an interface, and the blanket material flows along the blanket module 21 within the blanket device 11 of the hybrid nuclear energy system 10. (See more details...) Figure 1 The cladding module 21 is shaped like an "ear".

[0048] Further reference Figure 3 ,exist Figure 3 In the hybrid nuclear energy system 20 shown, multiple blanket modules 21 have identical structures. Each blanket module 21 is tightly fitted with an adjacent blanket module 22. Each blanket unit 221 within a blanket module 21 (different labels are used to describe the positions of the blanket units 221 for better illustration) is connected to the corresponding blanket unit 222 in the adjacent blanket module 21. To more intuitively visualize the flow path of the blanket material, Figure 3 Only a structural schematic diagram of one of the cladding units 22 located in the same position among the multiple cladding modules 21 is shown, such as Figure 3 It can be clearly seen that the cladding material flows between the cladding units 22 in each cladding module 21 and the corresponding cladding units 22 in adjacent cladding modules 21, rather than flowing within the cladding module 21 itself; that is, the cladding material flows circumferentially. In practical applications, different methods can be adopted according to different needs. Figure 1 or Figure 3 The direction of the flow of the cladding material further enhances the system's flexibility and adaptability.

[0049] On the other hand, in hybrid nuclear energy systems 10, 20, and 30, moderator blocks are provided in all blanket units 22. In any embodiment of the hybrid nuclear energy system provided in this application, a fast neutron spectrum design is adopted by default, which can fully utilize the high-energy characteristics of fusion neutrons, improve the fission matter breeding capacity and long-lived nuclide transmutation efficiency, and is particularly suitable for the efficient conversion of uranium-238 to plutonium-239 or thorium-232 to uranium-233. Based on this, by arranging moderator blocks (such as graphite, zirconium hydride, etc.) in the blanket units 22, local neutron moderation is achieved, forming a hybrid energy spectrum. The system can flexibly adjust the distribution position, volume ratio, and geometric configuration of the moderator blocks according to requirements, thereby controlling the ratio of thermal neutrons to fast neutrons. This design takes into account the differentiated requirements of different fuel systems for neutron energy spectra, improving the system's adaptability to multiple fuel cycles. Meanwhile, the integrated design of the moderator block and the blanket device 11 can support later replacement or reconfiguration, achieving a balance between neutron utilization efficiency and system flexibility.

[0050] Furthermore, by employing graphite or other neutron moderators to locally moderate the high-energy neutrons produced by fusion, the neutron energy spectrum can be optimized and controlled. In practical applications, the reaction cross-section of the thermal neutron or ultrathermal neutron (generated by the reaction of the moderator block and high-energy neutrons) region is larger, resulting in higher utilization efficiency. By embedding graphite moderator blocks in the blanket unit 22, some high-energy neutrons can be gradually slowed down to the thermal energy region, forming a local thermal neutron channel and improving the neutron utilization efficiency of key reactions such as lithium-6 tritium production and uranium / plutonium fission. Graphite has excellent neutron moderation performance, high-temperature stability, and radiation tolerance, making it suitable for long-term operation as a moderator material. The geometric layout, volume ratio, and distribution position of the moderator block can be optimized according to the neutron flux distribution to achieve controllable adjustment of the fast thermal mixing energy spectrum, balancing breeding, tritium production, and reactivity requirements while maintaining overall subcritical safety. This further enhances the system's adaptability to different fuel cycle modes, and is particularly beneficial for the start-up and transition of the thorium-uranium cycle, improving system flexibility and engineering feasibility.

[0051] Preferably, the cladding device 11 includes multiple cladding modules 21, each cladding module 21 including multiple cladding units 22. The cladding units 22 have a detachable structure for easy replacement of the cladding modules 21. When the fuel molten salt enters the cladding module 21 from the circulation, it absorbs heat generated by neutron fission within the cladding unit 22. Subsequently, the fuel molten salt flows from one cladding module 21 through the interface between the multiple cladding modules 21 into the next cladding module 21. After passing through multiple cladding modules 21, the fuel molten salt flows to the fuel power pump 35.

[0052] Furthermore, the design of the detachable modular blanket unit 22 effectively solves the problem of long-term stable operation of materials in traditional nuclear systems under strong radiation and high-temperature corrosion environments. Fusion neutron flux is high, and reactor internal materials are subjected to extreme heat loads and radiation damage over long periods, making them prone to embrittlement, swelling, and performance degradation, severely impacting equipment lifespan and safety. The detachable blanket unit 22 structure allows functional units to be decomposed into independent, replaceable components. Each blanket unit 22 consists of a high-temperature resistant alloy cladding and an internal molten salt fuel chamber. When a blanket unit 22 reaches the end of its service life or is damaged, it can be replaced online or periodically during reactor shutdown, preventing the entire system from becoming unusable due to localized aging. Simultaneously, the blanket material (molten fuel salt) can be reprocessed online, reducing the accumulation of radioactive waste. The aforementioned detachable modular blanket unit 22 design also facilitates generational upgrades using advanced radiation-resistant materials, improving system maintainability and scalability, fundamentally overcoming material tolerance bottlenecks, and ensuring long-term safe and stable system operation.

[0053] Preferably, the blanket device 11 can employ a fast neutron spectrum design, which can fully leverage the advantages of fast neutrons in nuclear fuel breeding, significantly improve neutron utilization efficiency, and achieve efficient conversion of uranium-238 to plutonium-239 or thorium-232 to uranium-233. The blanket device 11 can be loaded with depleted uranium or natural uranium, or it can be doped with thorium-based fuel, continuously generating new fissile nuclides in a strong neutron field, forming a closed fuel cycle. This design greatly improves the utilization rate of nuclear fuel resources and provides a technological path for the large-scale utilization of thorium resources. Thus, it fundamentally alleviates the resource bottleneck faced by fission energy development and promotes the evolution of nuclear energy towards a more sustainable and efficient direction.

[0054] Preferably, the blanket device 11 adopts a subcritical design, meaning that the hybrid nuclear energy system always operates in a subcritical state, further ensuring reactor safety. This design ensures that the hybrid nuclear energy system always operates in a subcritical state, meaning that the fission chain reaction cannot sustain itself and must rely on the continuous injection of fusion neutrons to drive the fission process. Once the fusion reaction in the fusion core 12 stops, the fission reaction in the blanket device 11 rapidly decays, fundamentally eliminating the risk of a runaway, self-sustaining chain reaction in the reactor and avoiding supercritical accidents that may occur in conventional fission reactors. This design significantly reduces reliance on human intervention and emergency systems, achieving intrinsic safety and providing better safety assurance for nuclear energy systems.

[0055] Preferably, the hybrid nuclear energy system proposed in any embodiment of this application, through optimized design of the neutron energy spectrum and blanket device, can achieve efficient tritium regeneration, ensuring that the tritium production meets the continuous combustion requirements of the fusion reaction. The molten fuel salt contains a large amount of lithium. Under neutron irradiation, lithium-6 undergoes a neutron-alpha reaction (n, α) to generate tritium. Simultaneously, lithium-7 can also generate tritium through a neutron-tritium reaction (n, n'T) under the action of high-energy neutrons. This dual pathway can increase tritium production and ensure net tritium gain. A highly efficient tritium recovery device 34 is constructed to extract the generated tritium from the blanket material (molten fuel salt) in real time, purify it, and return it to the fusion core 12 for reuse.

[0056] Furthermore, the accompanying tritium recovery device 34 can efficiently extract and recover tritium from the molten salt and transport it back to the fusion core 12. This design effectively improves the tritium breeding ratio, ensuring fuel balance for long-term system operation. It is independent of external tritium supply, a crucial prerequisite for the engineering and commercialization of fusion-fission hybrid systems. The highly fluid blanket material facilitates continuous tritium extraction, avoiding the risk of tritium retention or leakage. The entire tritium cycle is closed-loop and controllable, significantly reducing dependence on external tritium supply and ultimately achieving tritium self-sufficiency. This enables the engineering and commercialization of fusion energy, providing key support for the long-term stable operation of the system.

[0057] The hybrid nuclear energy system proposed in any embodiment of this application efficiently utilizes neutrons generated by fusion through the introduction of a fission process. Neutrons generated by fusion entering the blanket device 11 can trigger fission reactions in nuclides such as uranium or thorium, releasing thermal energy far exceeding the fusion energy, thus achieving energy multiplication. Each fusion neutron can trigger multiple fissions, significantly improving the overall energy output capacity of the system and effectively increasing the Q value. Liquid fuel molten salt, as an integrated fuel and coolant medium, has excellent thermal conductivity, efficiently removing the heat generated by both fission and fusion, and transferring it to the cooling circuit 15 through the heat exchange module 14, driving a steam turbine or other energy conversion modules to achieve efficient power generation or multi-energy integrated utilization.

[0058] The basic concepts have been described above. Obviously, for those skilled in the art, the above disclosure is merely illustrative and does not constitute a limitation of this application. Although not explicitly stated herein, those skilled in the art may make various modifications, improvements, and corrections to this application. Such modifications, improvements, and corrections are suggested in this application, and therefore remain within the spirit and scope of the exemplary embodiments of this application.

[0059] Furthermore, this application uses specific terms to describe embodiments of the application. For example, "an embodiment," "one embodiment," and / or "some embodiments" refer to a particular feature, structure, or characteristic related to at least one embodiment of the application. Therefore, it should be emphasized and noted that "an embodiment," "one embodiment," or "an alternative embodiment" mentioned twice or more in different locations in this specification do not necessarily refer to the same embodiment. In addition, certain features, structures, or characteristics in one or more embodiments of the application can be appropriately combined.

[0060] Similarly, it should be noted that, in order to simplify the description of the present application and thus aid in the understanding of one or more embodiments, the foregoing description of the embodiments of the present application sometimes combines multiple features into a single embodiment, drawing, or description thereof. However, this disclosure method does not imply that the subject matter of the present application requires more features than those mentioned in the claims. In fact, the embodiments contain fewer features than all the features of the single embodiments disclosed above.

[0061] In some embodiments, numbers describing the quantity of components and attributes are used. It should be understood that such numbers used in the description of embodiments are modified in some examples with the terms "approximately," "approximately," or "generally." Unless otherwise stated, "approximately," "approximately," or "generally" indicates that the numbers are allowed to vary by ±20%. Accordingly, in some embodiments, the numerical parameters used in the specification and claims are approximate values, which may be changed depending on the characteristics required by individual embodiments. In some embodiments, numerical parameters should take into account specified significant digits and employ a general method of digit reservation. Although the numerical ranges and parameters used to confirm their breadth of scope in some embodiments of this application are approximate values, in specific embodiments, such values ​​are set as precisely as feasible.

[0062] Although this application has been described with reference to specific embodiments, those skilled in the art should recognize that the above embodiments are only used to illustrate this application, and various equivalent changes or substitutions can be made without departing from the spirit of this application. Therefore, any changes or modifications to the above embodiments within the essential spirit of this application will fall within the scope of the claims of this application.

Claims

1. A hybrid nuclear power system, characterized by, include: Fusion core, suitable for radiation fusion products; A blanket device, disposed around the fusion core to receive the fusion products, the blanket device being adapted to contain blanket material, the blanket material including fissile material; A fuel circuit connected to the cladding device, wherein the cladding material is adapted to circulate within the cladding device and the fuel circuit; A heat exchange module adapted to contain heat exchange material, wherein at least a portion of the fuel circuit is located within the heat exchange module or the heat exchange module is at least partially located within the cladding device; A cooling circuit is connected to the heat exchange module, and the heat exchange material circulates in the heat exchange module and the cooling circuit, exchanging heat with the cladding material.

2. The hybrid nuclear power system of claim 1, wherein, The cladding device includes multiple cladding modules, and each cladding module includes multiple cladding units.

3. The hybrid nuclear power system of claim 1, wherein, The fuel circuit also includes a recovery device and / or a fuel power pump, the recovery device being adapted to recover the fusion material.

4. The hybrid nuclear power system of claim 3, wherein, The recovery device includes an exhaust gas treatment module, an adsorber, a storage tank, a degassing module, and / or a compressor, wherein the compressor is connected to the fusion core.

5. The hybrid nuclear power system of claim 1, wherein, The heat exchange module includes a main heat exchanger, at least a portion of the fuel circuit is located inside the main heat exchanger, the heat exchange material is located inside the main heat exchanger, the fuel circuit located inside the main heat exchanger is independent of the heat exchange material, and the cooling circuit is connected to the main heat exchanger.

6. The hybrid nuclear power system of claim 1, wherein, The heat exchange module includes a heat exchange tube bundle, at least a portion of which is located within the cladding module. The cooling heat exchange circuit is connected to the heat exchange tube bundle, and the heat exchange material is adapted to flow within the heat exchange tube bundle and the cooling circuit.

7. The hybrid nuclear power system of claim 1, wherein, The heat exchange material includes cooling molten salt.

8. The hybrid nuclear power system of claim 1, wherein, The cladding material also includes convertible nuclides, including thorium-232 and / or uranium-238, and the fissile material includes uranium-233, uranium-235 and / or plutonium-239.

9. The hybrid nuclear power system of claim 1, wherein, The fusion material includes deuterium and / or tritium, and the fusion products include high-energy neutrons.

10. The hybrid nuclear power system of claim 1, wherein, The cooling circuit also includes a cooling circuit pump, which is adapted to provide power to the heat exchange material.

11. The hybrid nuclear power system of claim 1, wherein, A connection interface is included between two adjacent cladding modules.

12. The hybrid nuclear power system of claim 1, wherein, The cooling circuit includes an energy conversion module adapted to convert heat from the heat exchange material, and the energy conversion module includes a steam generator.

13. The hybrid nuclear energy system as described in claim 2, characterized in that, At least a portion of the cladding unit includes a moderation block, and the cladding unit is a removable unit.

14. The hybrid nuclear energy system as described in claim 2, characterized in that, The cladding unit in each cladding module is in communication with the adjacent cladding unit, and the cladding material is adapted to flow along the cladding module within the cladding device.

15. The hybrid nuclear energy system as described in claim 2, characterized in that, The multiple cladding modules have the same structure, each cladding module is closely fitted with the adjacent cladding module, and the cladding unit in each cladding module is connected to the cladding unit in the adjacent cladding module at the corresponding position.

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