Hybrid molten salt pile

Abstract

This application provides a hybrid molten salt reactor, relating to the field of nuclear reactor technology. The hybrid molten salt reactor includes: a reactor vessel having a reactor cavity; and a core located within the reactor cavity. The core includes molten salt and solid fuel assemblies disposed within the molten salt. A first convertible nuclide is dissolved in the molten salt. The solid fuel assembly includes fuel rods with fuel pellets, each fuel pellet containing a fissile nuclide and a second convertible nuclide. The fissile nuclide is used to undergo a chain fission reaction to produce neutrons, which are used to convert the first and second convertible nuclides into fissile nuclides, respectively. This application couples solid fuel breeding with liquid fuel breeding, which can more effectively improve neutron economy and increase the fuel breeding ratio.

Description

Technical Field

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

[0002] Nuclear power is an important component of clean energy. The recycling of nuclear fuel mainly includes two technical routes: the uranium-plutonium cycle and the thorium-uranium cycle. The process of converting uranium-238 (U-238) into plutonium-239 (Pu-239) through neutron absorption is called the uranium-plutonium cycle. The process of converting thorium-232 (Th-232) into uranium-233 (U-233) through neutron absorption is called the thorium-uranium cycle.

[0003] Most current nuclear reactors use uranium; however, the cost of natural uranium is constantly rising, posing risks to the supply security and cost control of uranium resources. Thorium-based molten salt reactors are a type of reactor that achieves efficient utilization of thorium fuel. Developing thorium-based molten salt reactors can effectively improve nuclear fuel supply security and cost control capabilities, thus ensuring energy security.

[0004] Molten salt reactors typically use liquid fuel, directly dissolving nuclear fuel (such as uranium-233, thorium-232, etc.) in fluoride molten salt (such as FLiBe, FLiNaK, etc.). The molten salt serves as both fuel carrier and coolant. The molten fuel circulates within the reactor core and primary coolant circuit. Nuclear fuel conversion and breeding in liquid fuel molten salt reactors (LF-MSRs) are primarily achieved through neutron bombardment of the molten fuel within the reactor core, followed by separation outside the reactor. However, the thorium-uranium cycle of liquid fuel is best suited for breeding under thermal conditions, resulting in a relatively soft energy spectrum. Furthermore, the neutron flux in the reactor core is limited by the density of convertible nuclides dissolved in the molten salt, leading to a low breeding ratio for the thorium-uranium cycle. Summary of the Invention

[0005] In view of this, this application provides a hybrid molten salt reactor to improve the fuel breed-up ratio.

[0006] In a first aspect, this application provides a hybrid molten salt reactor, comprising:

[0007] A reactor vessel, having a reactor cavity;

[0008] The reactor core, located within the reactor cavity, comprises molten salt and solid fuel assemblies disposed within the molten salt. A first convertible nuclide is dissolved in the molten salt. The solid fuel assembly comprises fuel rods having fuel pellets. The fuel pellets contain fissile nuclides and a second convertible nuclide. The fissile nuclide is used to undergo a chain fission reaction to produce neutrons, which are used to convert the first and second convertible nuclides into fissile nuclides, respectively.

[0009] In one possible implementation, the reactor vessel further has a molten salt inlet and a molten salt outlet, and the hybrid molten salt reactor further includes:

[0010] A molten salt circulation pipeline is connected to the molten salt inlet and the molten salt outlet, respectively;

[0011] An online fuel processing system is installed on the molten salt circulation pipeline. The online fuel processing system is used to post-process the molten salt to extract the nuclide generated after the first convertible nuclide absorbs the neutron from the molten salt.

[0012] In one possible implementation, the hybrid molten salt reactor further includes:

[0013] A heat exchanger is installed on the molten salt circulation pipeline, wherein the online fuel processing system is arranged in parallel with or in series with the heat exchanger at the rear end of the heat exchanger.

[0014] In one possible implementation, the hybrid molten salt reactor further includes:

[0015] An offline post-processing system is used to post-process the solid fuel assembly to extract the nuclide generated after the second convertible nuclide absorbs the neutron from the fuel rod.

[0016] In one possible implementation, the hybrid molten salt reactor further includes:

[0017] A reflector layer is arranged around the reactor core, and a coolant flow channel is provided in the reflector layer. The coolant flow channel is connected to the reactor cavity to allow the molten salt to flow.

[0018] In one possible implementation, the reflective layer comprises a graphite layer.

[0019] In one possible implementation, the solid fuel assembly includes a square assembly or a hexagonal assembly.

[0020] In one possible implementation, the molten salt comprises lithium fluoride, beryllium fluoride, and thorium tetrafluoride; or

[0021] The molten salt comprises lithium fluoride, beryllium fluoride, and thorium tetrachloride.

[0022] In one possible implementation, the fuel pellets are composed of one or more of uranium-plutonium-zirconium alloy fuel, mixed oxide fuel, and minor actinide fuel.

[0023] In one possible implementation, the fissile nuclide includes any or more of uranium-233, uranium-235, and plutonium-239; and / or

[0024] The first convertible nuclide includes thorium-232 and / or uranium-238; and / or

[0025] The second convertible nuclide includes uranium-238 and / or thorium-232.

[0026] This application arranges solid fuel assemblies in molten salt containing a first convertible nuclide. The solid fuel assembly includes fuel rods with fuel pellets containing fissile nuclides and a second convertible nuclide. During reactor operation, the fissile nuclides in the fuel rods undergo a chain fission reaction to produce neutrons. These neutrons convert the first and second convertible nuclides into fissile nuclides, respectively, thus achieving fuel breeding. This application couples solid fuel breeding with liquid fuel breeding, which can more effectively improve neutron economy and increase the fuel breeding ratio. Attached Figure Description

[0027] 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:

[0028] Figure 1 This is a schematic diagram of a hybrid molten salt reactor provided in an embodiment of this application;

[0029] Figure 2 This is a schematic diagram of the core structure provided in an embodiment of this application;

[0030] Figure 3A This is a longitudinal cross-sectional schematic diagram of the solid fuel assembly provided in the embodiments of this application;

[0031] Figure 3B This is a schematic cross-sectional view of a solid fuel assembly along the AA direction provided in an embodiment of this application;

[0032] Figure 3C This is a cross-sectional schematic diagram of another solid fuel assembly along the AA direction provided in an embodiment of this application;

[0033] Figure 4 This is a schematic diagram of another hybrid molten salt reactor provided in the embodiments of this application.

[0034] The attached figures are labeled as follows:

[0035] 100. Hybrid molten salt reactor;

[0036] 110. Reactor container;

[0037] 120. Core;

[0038] 130. Molten salt circulation pipeline;

[0039] 140. Online fuel handling system;

[0040] 150. Heat exchanger;

[0041] 1101, Molten Salt Inlet;

[0042] 1102. Molten salt outlet;

[0043] 121. Molten salt;

[0044] 122. Solid fuel assembly;

[0045] 123. Reflective layer;

[0046] 1220. Fuel rods;

[0047] 1231. Coolant flow channels;

[0048] 400. Hybrid molten salt pile. Detailed Implementation

[0049] 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.

[0050] As indicated in this application, unless the context clearly indicates otherwise, the words "a," "an," "an," and / or "the" do not specifically refer to the singular and may also include the plural. 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. Furthermore, it should be noted that the use of words such as "first" and "second" to define the object is merely for the purpose of distinguishing the corresponding objects, and unless otherwise stated, the above words have no special meaning and therefore should not be construed as limiting the scope of protection of this application.

[0051] 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.

[0052] Furthermore, 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 the description herein. Moreover, this application is to be understood not only by the actual terms used, but also by the meaning implied by each term.

[0053] 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.

[0054] 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.

[0055] It should be understood that when a component is referred to as "on another component," "connected to another component," "coupled to another component," or "in contact with another component," it can be directly on, connected to, coupled to, or in contact with that other component, or there may be an insert component. In contrast, when a component is referred to as "directly on another component," "directly connected to," "directly coupled to," or "directly in contact with" another component, there is no insert component. Similarly, when a first component is referred to as "electrically contacting" or "electrically coupled to" a second component, there is an electrical path between the first and second components that allows current to flow. This electrical path may include capacitors, coupled inductors, and / or other components that allow current to flow, even if there is no direct contact between metallic components.

[0056] In the description of the embodiments in this application, the term "and / or" is merely a description of the relationship between related objects, indicating that three relationships can exist. For example, A and / or B can represent: A existing alone, A and B existing simultaneously, and B existing alone. Additionally, the character " / " in this document generally indicates that the preceding and following related objects have an "or" relationship.

[0057] Please refer to Figure 1 and Figure 2 , Figure 1 A schematic diagram of the structure of a hybrid molten salt reactor 100 according to an exemplary embodiment of this application is shown. Figure 2 A schematic diagram of the core 120 according to an exemplary embodiment of this application is shown. It will be understood that the hybrid molten salt reactor 100 is not required to include... Figure 1 All elements shown in the diagram may also be included in the mixed molten salt reactor 100. Figure 1 Other elements not shown in the diagram. Similarly, core 120 is not required to include... Figure 2 All elements shown in the diagram may also be included in core 120. Figure 2 Other elements not shown in the text.

[0058] A hybrid molten salt reactor 100 includes a reactor vessel 110 and a core 120. The reactor vessel 110 has a reactor cavity. The core 120 is located within the reactor cavity of the reactor vessel 110. The core 120 includes molten salt 121 and solid fuel assemblies 122. A first convertible nuclide is dissolved in the molten salt 121. Exemplarily, the first convertible nuclide includes thorium-232 (Th-232) and / or uranium-238 (U-238). The molten salt 121 serves as both a fuel carrier and a coolant. Exemplarily, the composition of the molten salt 121 includes lithium fluoride (LiF), beryllium fluoride (BeF2), and thorium tetrafluoride (ThF4), or includes lithium fluoride (LiF), beryllium fluoride (BeF2), and thorium tetrachloride (ThCl4). Alternatively, ThCl4 can provide fuel nuclides (Th-232), LiF and Be The thermodynamic stability and cooling performance of molten salt 121 are synergistically ensured. In an exemplary embodiment, molten salt 121 uses ThCl4 to provide the fuel nuclide (Th-232) compared to using Th... The fuel nuclide (Th-232) is provided because chlorides have a weaker neutron-moderating effect, resulting in a harder energy spectrum in the fuel region and thus a higher multiplication capacity. This can be achieved through selection. 37 Cl enrichment further reduces neutron loss.

[0059] Solid fuel assembly 122 is disposed in molten salt 121. Solid fuel assembly 122 includes fuel rods 1220 having fuel pellets. Please refer to... Figures 3A-3C , Figure 3A A longitudinal cross-sectional schematic diagram of a solid fuel assembly 122 according to an exemplary embodiment of this application is shown. Figure 3B This illustration shows a schematic cross-sectional view of a solid fuel assembly 122 along the AA direction, according to an exemplary embodiment of this application. Figure 3B This illustration shows a cross-sectional schematic diagram of another solid fuel assembly 122 along the AA direction according to an exemplary embodiment of this application. In some embodiments, the solid fuel assembly 122 includes a square component, that is, the cross-sectional shape of the solid fuel assembly 122 in the radial plane is square, such as... Figure 3B As shown, the fuel rods 1220 are arranged in a square pattern. In some other embodiments, the solid fuel assembly 122 includes a hexagonal component, that is, the cross-sectional shape of the solid fuel assembly 122 in the radial plane is hexagonal, such as... Figure 3C As shown, the fuel rods 1220 are arranged in a hexagonal pattern.

[0060] exist Figure 2 In the illustrated embodiment, the solid fuel assembly 122 (fuel rod 1220) is uniformly arranged in the molten salt 121. It will be understood that in some other embodiments, the solid fuel assembly 122 (fuel rod 1220) may be arranged in a specific manner in the molten salt 121 as required.

[0061] The fuel pellets of fuel rod 1220 contain fissile nuclides and a second convertible nuclide. The fissile nuclides in fuel rod 1220 are used to initiate a chain fission reaction to produce neutrons, which are then used to convert the first and second convertible nuclides into fissile nuclides, respectively.

[0062] In one exemplary embodiment, the fuel pellets are composed of one or more of uranium-plutonium-zirconium alloy fuel (UPuZr alloy fuel), mixed oxide fuel (MOX fuel), and minor actinide fuel (MA fuel). If the fuel pellets are composed of minor actinide fuel (MA fuel), high-level radioactive waste can be reduced through core incineration and transmutation. Fissile nuclides include any or more of uranium-233 (U-233), uranium-235 (U-235), and plutonium-239 (Pu-239). A second convertible nuclide includes uranium-238 (U-238) and / or thorium-232 (Th-232). It is understood that the first convertible nuclide and the second convertible nuclide may be the same or different. For example, the first convertible nuclide may include Th-232, and the second convertible nuclide may include U-238; or the first convertible nuclide may include U-238, and the second convertible nuclide may include Th-232; or both the first and second convertible nuclides may include Th-232 or both may include U-238; or both the first and second convertible nuclides may include Th-232 and U-238. The following example illustrates this.

[0063] During reactor operation, the chain fission reaction mainly relies on the fission of fissile nuclides such as U-233, U-235, and Pu-239 in fuel rod 1220. The surplus neutrons produced by fission convert convertible nuclides (including the first and second convertible nuclides) in core 120 into fissile nuclides, achieving fuel breeding. This fuel breeding consists of two parts: first, U-238 in solid fuel assembly 122 is converted into Pu-239, and the generated Pu-239 can further sustain the chain fission reaction in core 120; second, Th-232 in molten salt 121 is converted into U-233.

[0064] This application's embodiments couple solid fuel breeding and liquid fuel breeding, with fuel breeding occurring simultaneously in a single reactor core's solid fuel assemblies and coolant (molten salt). This can more effectively improve neutron economy and increase the fuel breeding ratio. Furthermore, this application's embodiments also utilize both fast and thermal breeding, simultaneously achieving U-Pu and Th-U breeding conversions, coupling the U-Pu and Th-U cycles. The overall breeding ratio of the reactor core is higher than that of existing reactors. In existing liquid fuel molten salt reactors, the fuel loading and density are limited due to fuel solubility, resulting in relatively low neutron flux in the reactor core. This application's embodiments can increase the neutron flux in the reactor core by increasing the loading of solid fuel assemblies, thereby effectively improving the Th-U conversion capability in the liquid fuel of the reactor core.

[0065] Continue to refer to Figure 1 The reactor vessel 110 also has a molten salt inlet 1101 and a molten salt outlet 1102. The molten salt inlet 1101 is located at the lower part of the reactor vessel 110, and the molten salt outlet 1102 is located at the upper part of the reactor vessel 110. It is understood that in some other embodiments, the molten salt inlet 1101 and the molten salt outlet 1102 may both be located at the lower part of the reactor vessel 110 or both be located at the upper part of the reactor vessel 110. The embodiments of this application do not limit the location of the molten salt inlet 1101 and the molten salt outlet 1102.

[0066] The hybrid molten salt reactor 100 also includes a molten salt circulation pipe 130 and an online fuel processing system 140. The molten salt circulation pipe 130 is connected to a molten salt inlet 1101 and a molten salt outlet 1102, respectively. The online fuel processing system 140 is disposed on the molten salt circulation pipe 130. The online fuel processing system 140 is used to reprocess the molten salt 121 to extract the nuclides generated after a first convertible nuclide absorbs a neutron from the molten salt 121. For example, Th-232 in the molten salt 121 absorbs a neutron, is first converted to Pa-233, and then decays to U-233. During reactor operation, after the molten salt 121 is discharged from the core 120, it undergoes nuclide separation using a reduction extraction method to extract Pa-233, which is then further converted to U-233.

[0067] Because the intermediate nuclide protactinium-233 (Pa-233) in the thorium-uranium conversion process has a short half-life, and to avoid the unproductive conversion and loss of Pa-233 within the reactor core, it needs to be removed from the core in a timely manner to obtain a considerable U-233 yield. Therefore, adopting an online processing method is beneficial for achieving an efficient thorium-uranium fuel cycle.

[0068] The hybrid molten salt reactor 100 also includes a heat exchanger 150. The heat exchanger 150 is located on the molten salt circulation pipe 130. An online fuel reprocessing system 140 is connected in series at the rear end of the heat exchanger 150. Molten salt 121 absorbs neutrons and heat within the reactor core 120 before being discharged from the core 120. Molten salt 121 first enters the heat exchanger 150 to dissipate heat, then enters the online fuel reprocessing system 140 for online reprocessing, and finally returns to the reactor core 120.

[0069] In some embodiments, please refer to Figure 4 The online fuel reprocessing system 140 and the heat exchanger 150 are arranged in parallel. Molten salt 121 absorbs neutrons and heat within the reactor core 120 and is then discharged from the reactor core 120. The molten salt circulation pipe 130 is divided into two parallel paths, splitting the molten salt 121 into two paths: one goes to the heat exchanger 150 to discharge heat, and the other enters the online fuel reprocessing system 140 for online reprocessing. Then, the two paths of molten salt 121 merge and return to the reactor core 120.

[0070] It should be noted that, Figure 4 The hybrid molten salt pile 400 shown is... Figure 1 The only difference between the hybrid molten salt reactor 100 and the one shown is the arrangement of the online fuel processing system 140. The hybrid molten salt reactor 400 will not be described in detail here.

[0071] In some embodiments, the hybrid molten salt reactor 100 further includes an offline reprocessing system (not shown). The offline reprocessing system is used to reprocess the solid fuel assembly 122 to extract the nuclide generated after the absorption of a second convertible nuclide by neutrons from the fuel rods 1220. Exemplarily, after reactor shutdown, the solid fuel assembly 122 is removed from the reactor vessel 110, and Pu-239 is extracted from the fuel rods 1220 using the offline reprocessing system.

[0072] The embodiments of this application combine online fuel processing and offline reprocessing methods, which can maximize fuel utilization and improve the economics of nuclear power.

[0073] Continue to refer to Figure 2 The hybrid molten salt reactor 100 also includes a reflector layer 123. The reflector layer 123 is disposed around the core 120. The reflector layer 123 can be a neutron-reflecting material. For example, the reflector layer 123 includes a graphite layer. The neutron energy spectrum at the center of the active region of the core 120 is predominantly fast to achieve a higher U-Pu conversion. Distributing the reflector layer 123 around the core 120 moderates neutrons, which is beneficial for Th-U conversion, while reducing neutron leakage from the core and improving neutron economy.

[0074] A coolant flow channel 1231 is provided within the reflector layer 123. The coolant flow channel 1231 is connected to the reactor cavity to allow the flow of molten salt 121. The coolant flow channel 1231 facilitates the inflow of molten salt 121 into the reflector layer 123, which is beneficial for cooling the reflector layer 123 and for the absorption of neutrons by the first convertible nuclide in the molten salt 121.

[0075] Figure 1 The elements shown and Figure 4 The elements shown all belong to the primary loop system of a hybrid molten salt reactor. It can be understood that, in addition to the primary loop system, a hybrid molten salt reactor can also include a secondary loop system and a tertiary loop system. The primary loop system generates heat, the secondary loop system transfers the heat generated by the primary loop system to the tertiary loop system, and the tertiary loop system can perform comprehensive nuclear energy utilization such as power generation, heating, steam supply, plant power supply, and seawater desalination. The primary loop system relies on the primary loop main pump to provide forced circulation drive force. The liquid molten salt in the primary loop system serves as both fuel and coolant, operating at atmospheric pressure. The molten salt flows through the molten salt channels through the reactor core, generating heat and carrying it out of the core. It then enters the heat exchanger through the molten salt circulation pipes, transferring heat to the secondary loop molten salt. Subsequently, the primary loop molten salt enters the reactor core through the primary loop main pump. The secondary loop system includes a steam generator and a secondary loop circulation pump. The secondary loop system relies on a secondary loop circulating pump to provide forced circulation driving force. The secondary loop molten salt does not contain fuel and operates at atmospheric pressure. After being heated in the heat exchanger, the secondary loop molten salt flows into the steam generator, transferring heat to the tertiary loop working fluid, and then returns to the inlet of the heat exchanger via the secondary loop circulating pump.

[0076] 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.

[0077] 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.

[0078] 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 of the invention, 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 fact, the embodiments have fewer features than all the features of the single embodiments disclosed above.

[0079] 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 scope of the essential spirit of this application will fall within the scope of this application.

Claims

1. A hybrid molten salt reactor, characterized in that, Comprising: a reactor vessel having a reactor cavity; a core located within the reactor cavity, the core comprising a molten salt and a solid fuel assembly disposed in the molten salt, the molten salt having a first transmutable nuclide dissolved therein, the solid fuel assembly comprising a fuel rod having a fuel pellet containing a fissile nuclide and a second transmutable nuclide, wherein the fissile nuclide is used to undergo a chain fission reaction to generate neutrons, the neutrons being used to transmute the first transmutable nuclide and the second transmutable nuclide into fissile nuclides, respectively.

2. The mixed molten salt reactor of claim 1, wherein, The reactor vessel further has a molten salt inlet and a molten salt outlet, the hybrid molten salt reactor further comprising: a molten salt circulation pipe connected to the molten salt inlet and the molten salt outlet, respectively; an in-line fuel processing system disposed on the molten salt circulation pipe, the in-line fuel processing system being used to post-process the molten salt to extract nuclides generated from the first transmutable nuclide after absorbing the neutrons from the molten salt.

3. The mixed molten salt reactor of claim 2, wherein, Further comprising: a heat exchanger disposed on the molten salt circulation pipe, wherein the in-line fuel processing system is arranged in parallel with the heat exchanger or in series after an end of the heat exchanger.

4. The mixed molten salt reactor of claim 1, wherein, Further comprising: an off-line post-processing system used to post-process the solid fuel assembly to extract nuclides generated from the second transmutable nuclide after absorbing the neutrons from the fuel rod.

5. The hybrid molten salt reactor of claim 1, wherein, Further comprising: a reflector layer arranged at an outer periphery of the core, the reflector layer having coolant flow channels disposed therein, the coolant flow channels being in communication with the reactor cavity to allow the molten salt to flow therethrough.

6. The mixed molten salt reactor of claim 5, wherein, The reflector layer comprises a graphite layer.

7. The mixed molten salt reactor of any one of claims 1-6, wherein, The solid fuel assembly comprises a square assembly or a hexagonal assembly.

8. The mixed molten salt reactor of any one of claims 1-6, wherein, The molten salt comprises lithium fluoride, beryllium fluoride, and thorium tetrafluoride; or The molten salt comprises lithium fluoride, beryllium fluoride, and thorium tetrachloride.

9. The hybrid molten salt reactor of any one of claims 1-6, wherein, The fuel pellet comprises any one or more of a uranium-plutonium-zirconium alloy fuel, a mixed oxide fuel, and a minor actinide fuel.

10. The mixed molten salt reactor of any one of claims 1-6, wherein, The fissile nuclide comprises any one or more of uranium-233, uranium-235, and plutonium-239; and / or The first transmutable nuclide comprises thorium-232 and / or uranium-238; and / or The second transmutable nuclide comprises uranium-238 and / or thorium-232.

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