Mixed molten salt reactor

Abstract

The invention provides a mixed molten salt reactor, and relates to the technical field of nuclear reactors. The hybrid molten salt reactor comprises: a reactor vessel having a reactor cavity; the reactor core is located in the reactor cavity, the reactor core comprises molten salt and a solid fuel assembly arranged in the molten salt, first convertible nuclides are dissolved in the molten salt, the solid fuel assembly comprises a fuel rod with a fuel core block, fissile nuclides and second convertible nuclides are contained in the fuel core block, and the first convertible nuclides and the second convertible nuclides are arranged in the fuel rod. Wherein the fissile nuclide is used for carrying out chain fission reaction to generate neutrons, and the neutrons are used for respectively converting the first convertible nuclide and the second convertible nuclide into fissile nuclides. According to the method, solid fuel proliferation and liquid fuel proliferation are coupled, the neutron economy can be more effectively improved, and the fuel proliferation ratio is increased.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of nuclear reactors, in particular to a hybrid molten salt reactor. BACKGROUND

[0002] Nuclear power is an important part of clean energy. The recycling of nuclear fuel mainly includes two technical routes of uranium-plutonium cycle and thorium-uranium cycle. The process of converting uranium-238 (U-238) into plutonium-239 (Pu-239) by absorbing neutrons and utilizing it is called uranium-plutonium cycle. The process of converting thorium-232 (Th-232) into uranium-233 (U-233) by absorbing neutrons and utilizing it is called thorium-uranium cycle.

[0003] Most of the current nuclear reactors use uranium, but the cost of natural uranium is rising, and there is a risk of supply security and cost control of uranium resources. Thorium-based molten salt reactor is a type of reactor that can achieve efficient utilization of thorium fuel. Developing thorium-based molten salt reactor can effectively improve the ability of nuclear fuel supply and cost control, and ensure energy security.

[0004] Molten salt reactors usually use liquid fuel, which directly dissolves nuclear fuel (such as uranium-233, thorium-232, etc.) in fluoride molten salt (such as FLiBe, FLiNaK, etc.), and the molten salt also serves as the fuel carrier and coolant. The fuel molten salt circulates in the reactor core and the primary circuit pipeline, serving as both fuel and coolant. The nuclear fuel conversion and multiplication of the liquid fuel molten salt reactor (LF-MSR) is mainly achieved by bombarding the fuel molten salt with neutrons in the reactor and then removing it outside the reactor for separation. However, the thorium-uranium cycle of liquid fuel is suitable for proliferation under thermal spectrum, with a relatively soft energy spectrum, and is limited by the density of convertible nuclides dissolved in the molten salt. The neutron flux of the reactor core is not high, and the proliferation ratio of the thorium-uranium cycle is not high. SUMMARY

[0005] Therefore, the present application provides a hybrid molten salt reactor to improve the fuel multiplication ratio.

[0006] In a first aspect, the present application provides a hybrid molten salt reactor, comprising: a reactor vessel having a reactor cavity; a reactor core located in the reactor cavity, the reactor core comprising a molten salt and a solid fuel assembly arranged in the molten salt, the molten salt dissolving a first convertible nuclide, the solid fuel assembly comprising a fuel rod having a fuel pellet, the fuel pellet containing a fissile nuclide and a second convertible nuclide, wherein the fissile nuclide is used to occur a chain fission reaction to generate neutrons, and the neutrons are used to convert the first convertible nuclide and the second convertible nuclide into fissile nuclides, respectively.

[0007] In a possible implementation, the reactor vessel further has a molten salt inlet and a molten salt outlet, and the molten salt-hybrid reactor further comprises: a molten salt circulation pipeline connected with the molten salt inlet and the molten salt outlet respectively; an online fuel processing system arranged on the molten salt circulation pipeline, the online fuel processing system being configured to perform post-processing on the molten salt to extract a nuclide generated after the first transmutable nuclide absorbs the neutrons from the molten salt.

[0008] In a possible implementation, the molten salt-hybrid reactor further comprises: a heat exchanger arranged on the molten salt circulation pipeline, wherein the online fuel processing system is arranged in parallel with the heat exchanger or is arranged at a rear end of the heat exchanger.

[0009] In a possible implementation, the molten salt-hybrid reactor further comprises: an offline post-processing system configured to perform post-processing on the solid fuel assembly to extract a nuclide generated after the second transmutable nuclide absorbs the neutrons from the fuel rod.

[0010] In a possible implementation, the molten salt-hybrid reactor further comprises: a reflector arranged at a periphery of the core, the reflector being provided with a coolant flow passage therein, the coolant flow passage being in communication with the reactor cavity to allow the molten salt to flow therethrough.

[0011] In a possible implementation, the reflector comprises a graphite layer.

[0012] In a possible implementation, the solid fuel assembly comprises a square assembly or a hexagonal assembly.

[0013] In a possible implementation, the molten salt comprises lithium fluoride, beryllium fluoride, and thorium tetrafluoride; or

[0014] the molten salt comprises lithium fluoride, beryllium fluoride, and thorium tetrachloride.

[0015] In a possible implementation, the fuel pellet comprises any one or more of a uranium-plutonium-zirconium alloy fuel, a mixed oxide fuel, and a minor actinide fuel.

[0016] In a possible implementation, the fissile nuclide comprises any one or more of uranium-233, uranium-235, and plutonium-239; and / or

[0017] the first transmutable nuclide comprises thorium-232 and / or uranium-238; and / or

[0018] The second transmutable nuclide includes uranium-238 and / or thorium-232.

[0019] The application arranges a solid fuel assembly in a molten salt in which a first transmutable nuclide is dissolved, the solid fuel assembly including a fuel rod having fuel pellets containing a fissile nuclide and a second transmutable nuclide, and the fissile nuclide in the fuel rod generates neutrons in a chain fission reaction during operation of the reactor, which convert the first transmutable nuclide and the second transmutable nuclide into the fissile nuclide respectively, achieving fuel breeding. The application couples solid fuel breeding and liquid fuel breeding, which can more effectively improve neutron economy and enhance the fuel breeding ratio. BRIEF DESCRIPTION OF DRAWINGS

[0020] The accompanying drawings are included to provide a further understanding of the application, and are incorporated in and constitute a part of this application, illustrate embodiments of the application, and together with the description serve to explain the principles of the application. In the drawings: Figure 1 is a structural schematic diagram of a hybrid molten salt reactor provided by an embodiment of the application; Figure 2 is a structural schematic diagram of a reactor core provided by an embodiment of the application; Figure 3A is a longitudinal sectional schematic diagram of a solid fuel assembly provided by an embodiment of the application; Figure 3B is a sectional schematic diagram of a solid fuel assembly along the A-A direction provided by an embodiment of the application; Figure 3C is another sectional schematic diagram of a solid fuel assembly along the A-A direction provided by an embodiment of the application; Figure 4 is a structural schematic diagram of another hybrid molten salt reactor provided by an embodiment of the application.

[0021] The reference signs in the drawings are as follows: 100, hybrid molten salt reactor; 110, reactor vessel; 120, reactor core; 130, molten salt circulation pipeline; 140, online fuel processing system; 150, heat exchanger; 1101, molten salt inlet; 1102, molten salt outlet; 121, molten salt; 122, solid fuel assembly; 123, reflector; 1220, fuel rod; 1231, coolant flow passage 400. Hybrid molten salt reactor. DETAILED DESCRIPTION

[0022] In order to more clearly illustrate the technical solutions of the embodiments of the present application, the drawings needed to be used in the embodiment description will be briefly introduced as follows. Obviously, the drawings in the following description are only some examples or embodiments of the present application, and for those skilled in the art, the present application can also be applied to other similar scenarios without creative labor on the basis of the drawings. Unless it is obvious from the language context or otherwise stated, the same reference numbers in the drawings represent the same structures or operations.

[0023] As shown in the present application, unless the context clearly indicates otherwise, the words "one", "an", "a", and / or "the" do not specify a singular number, but also include a plural number. Generally speaking, the terms "comprise" and "include" only indicate that the steps and elements explicitly identified are included, and these steps and elements do not constitute an exclusive list, and the method or device can also include other steps or elements. In addition, it should be noted that the use of the words "first", "second", etc. to limit objects is only for the convenience of distinguishing the corresponding objects, and unless otherwise stated, the above words have no special meaning, and therefore cannot be understood as a limitation on the scope of protection of the present application.

[0024] Unless otherwise specifically stated, the relative arrangement of the components and steps, numerical expressions, and numerical values set forth in these embodiments do not limit the scope of the present application. At the same time, it should be understood that the sizes of the various parts shown in the drawings are not drawn in accordance with the actual proportional relationship. The technology, methods and devices known to those skilled in the relevant art can not be discussed in detail, but under appropriate circumstances, the technology, methods and devices should be considered as part of the specification. In all examples shown and discussed here, any specific value should be interpreted as merely exemplary, and not as a limitation. Therefore, other examples of exemplary embodiments can have different values. It should be noted that similar reference numbers and letters represent similar items in the following drawings, and therefore, once an item is defined in one drawing, it does not need to be further discussed in subsequent drawings.

[0025] In addition, although the terms used in the present application are selected from commonly known terms, some terms mentioned in the specification of the present application can be selected by the applicant according to his or her judgment, and the detailed meaning of each term is described in the relevant part of the description. In addition, the present application is not only required to be understood by the actual terms used, but also by the meaning implied by each term.

[0026] In the description of the application, it should be understood that the orientation words such as "front, back, up, down, left, right", "transverse, vertical, perpendicular, horizontal" and "top, bottom" and the like indicated by the orientation or position relationship shown in the drawings are generally based on the orientation or position relationship shown in the drawings, and are only for the convenience of describing the application and simplifying the description, without the opposite description, these orientation words do not indicate and imply that the indicated device or element must have a particular orientation or be constructed and operated in a particular orientation, therefore it cannot be understood as a limitation on the protection scope of the application; The orientation words "inner, outer" refer to the inner and outer of the contour of each component itself.

[0027] For the convenience of description, spatial relative terms such as "over", "above", "upper surface", "upper" and the like can be used herein to describe the spatial position relationship of one device or feature with other devices or features as shown in the drawings. It should be understood that the spatial relative terms are intended to include different orientations in use or operation in addition to the orientation of the device described in the drawings. For example, if the device in the drawing is inverted, the device described as "above" or "over" other devices or structures will be positioned "below" or "under" other devices or structures. Thus, the exemplary term "above" can include both "above" and "below" orientations. The device can also be positioned in other different ways (rotated 90 degrees or in other orientations), and the spatial relative descriptions used herein are interpreted accordingly.

[0028] It should be understood that when a component is referred to as "on", "connected to", "coupled to" or "contacting" another component, it can be directly on, connected to, coupled to, or contacting the other component, or there can be an intervening component. In contrast, when a component is referred to as "directly on", "directly connected to", "directly coupled to" or "directly contacting" another component, there is no intervening 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 component and the second component that allows current to flow. The electrical path can include capacitors, coupled inductors, and / or other components that allow current to flow, even without direct contact between metal components.

[0029] In the description of the embodiments of the application, the term "and / or" is only a description of the association relationship of the associated objects, which means that there can be three relationships, for example, A and / or B, which means that there are three cases of A alone, A and B together, and B alone. In addition, the character " / " herein generally represents that the front and rear associated objects are in an "or" relationship.

[0030] Please refer toFigure 1 and Figure 2 , Figure 1 A structural schematic diagram of a hybrid molten salt reactor 100 according to an example embodiment of the present application is shown, Figure 2 A structural schematic diagram of a core 120 according to an example embodiment of the present application is shown. It will be understood that the hybrid molten salt reactor 100 is not required to include all of the elements shown in Figure 1 The hybrid molten salt reactor 100 can also include other elements not shown in Figure 1 Similarly, the core 120 is not required to include all of the elements shown in Figure 2 The core 120 can also include other elements not shown in Figure 2

[0031] The 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 a molten salt 121 and a solid fuel assembly 122. A first transmutable nuclide is dissolved in the molten salt 121. Exemplarily, the first transmutable nuclide includes thorium-232 (Th-232) and / or uranium-238 (U-238). The molten salt 121 assumes both a fuel carrier and a coolant function. 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). Th or ThCl4provides the fuel nuclide (Th-232), LiF and Be cooperate to ensure the thermodynamic stability and cooling performance of the molten salt 121. In one example embodiment, the molten salt 121 employs ThCl4to provide the fuel nuclide (Th-232) as compared to employing Th provides the fuel nuclide (Th-232), because the chloride is weaker in slowing down neutrons, the fuel region spectrum is harder, and there can be higher breeding capability, which can be further reduced by selecting 37 Cl enrichment to further reduce neutron loss.

[0032] The solid fuel assembly 122 is disposed in the molten salt 121. The solid fuel assembly 122 includes a fuel rod 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 example embodiment of the present application is shown, Figure 3B A cross-sectional schematic diagram of a solid fuel assembly 122 according to an example embodiment of the present application along the A-A direction is shown, Figure 3B ​Another cross-sectional view of the exemplary embodiment of the present application is shown along the A-A direction of the solid fuel assembly 122. In some embodiments, the solid fuel assembly 122 comprises a square assembly, i.e., the cross-sectional shape of the solid fuel assembly 122 in the radial plane is square, as shown in Figure 3B The fuel rods 1220 are arranged in a square form, as shown. In other embodiments, the solid fuel assembly 122 comprises a hexagonal assembly, i.e., the cross-sectional shape of the solid fuel assembly 122 in the radial plane is hexagonal, as shown in Figure 3C The fuel rods 1220 are arranged in a hexagonal form, as shown.

[0033] In the embodiment shown in Figure 2 It is understood that in other embodiments, the solid fuel assembly 122 (fuel rods 1220) can be arranged in the molten salt 121 in a specific form as desired.

[0034] The fissile nuclides and the second transmutable nuclides are contained in the fuel pellets of the fuel rods 1220. The fissile nuclides in the fuel rods 1220 are used to undergo a chain fission reaction to generate neutrons, which are used to transmute the first transmutable nuclides and the second transmutable nuclides into fissile nuclides, respectively.

[0035] In one exemplary embodiment, the composition of the fuel pellets includes any one or more of a uranium-plutonium-zirconium alloy fuel (UPuZr alloy fuel), a mixed oxide fuel (MOX fuel), and a minor actinide fuel (MA fuel). As the composition of the fuel pellets uses a minor actinide fuel (MA fuel), high level waste can be reduced by core burning and transmutation. The fissile nuclides include any one or more of uranium-233 (U-233), uranium-235 (U-235), and plutonium-239 (Pu-239). The second transmutable nuclides include uranium-238 (U-238) and / or thorium-232 (Th-232). It is understood that the first transmutable nuclides and the second transmutable nuclides can be the same or different, such as the first transmutable nuclides include Th-232 and the second transmutable nuclides include U-238, or the first transmutable nuclides include U-238 and the second transmutable nuclides include Th-232, or the first transmutable nuclides and the second transmutable nuclides both include Th-232 or both include U-238, or the first transmutable nuclides and the second transmutable nuclides both include Th-232 and U-238. The following is described by way of example with the first transmutable nuclides including Th-232 and the second transmutable nuclides including U-238.

[0036] During the operation of the reactor, the chain fission reaction mainly relies on the fission of U-233, U-235, Pu-239 and other fissile nuclides in the fuel rod 1220. The abundant neutrons generated by the fission convert the transmutable nuclides (including the first transmutable nuclide and the second transmutable nuclide) in the core 120 into fissile nuclides, thereby achieving fuel multiplication. The fuel multiplication includes two parts: the conversion of U-238 in the solid fuel assembly 122 into Pu-239, and the conversion of Th-232 in the molten salt 121 into U-233. The generated Pu-239 can further maintain the chain fission reaction of the core 120.

[0037] The embodiment of the present application couples solid fuel multiplication and liquid fuel multiplication. The fuel multiplication is simultaneously performed in the solid fuel assembly and the coolant (molten salt) of the core, which can more effectively improve the neutron economy and increase the fuel multiplication ratio. In addition, the embodiment of the present application also simultaneously utilizes fast spectrum and thermal spectrum multiplication, and simultaneously realizes the multiplication and conversion of U-Pu and Th-U, thereby coupling the U-Pu cycle and the Th-U cycle, and the comprehensive multiplication ratio of the core is higher than that of the existing reactor. In the existing liquid fuel molten salt reactor, the loading capacity and the fuel density of the fuel are limited due to the limited solubility of the fuel, and the neutron flux of the core is relatively low. The embodiment of the present application can increase the neutron flux of the core by increasing the loading capacity of the solid fuel assembly, thereby effectively improving the Th-U conversion capacity in the liquid fuel of the core.

[0038] With reference 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 can be understood that in some other embodiments, the molten salt inlet 1101 and the molten salt outlet 1102 can 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 embodiment of the present application does not limit the positions of the molten salt inlet 1101 and the molten salt outlet 1102.

[0039] The hybrid molten salt reactor 100 also includes a molten salt circulation pipeline 130 and an online fuel processing system 140. The molten salt circulation pipeline 130 is connected with the molten salt inlet 1101 and the molten salt outlet 1102, respectively. The online fuel processing system 140 is arranged on the molten salt circulation pipeline 130. The online fuel processing system 140 is used for post-processing the molten salt 121 to extract the nuclide generated after the first transmutable nuclide absorbs the neutrons. For example, the Th-232 in the molten salt 121 absorbs the neutrons to be first converted into Pa-233, and then decayed into U-233. During the operation of the reactor, after the molten salt 121 is discharged from the core 120, the nuclide separation is performed on the molten salt 121 by using the reduction extraction, Pa-233 is extracted, and U-233 is further converted.

[0040] 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.

[0041] 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.

[0042] 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.

[0043] 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.

[0044] 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.

[0045] 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.

[0046] Continue to refer to Figure 2The hybrid molten salt reactor 100 further includes a reflector 123. The reflector 123 is disposed at the periphery of the core 120. The reflector 123 can be a neutron-reflecting material. Illustratively, the reflector 123 includes a graphite layer. The neutron spectrum at the center of the active region of the core 120 is dominated by fast spectrum to achieve higher U-Pu conversion. The reflector 123 disposed at the periphery of the core 120 moderates neutrons to facilitate Th-U conversion while reducing core neutron leakage and improving neutron economy.

[0047] The reflector 123 is provided with coolant flow channels 1231. The coolant flow channels 1231 are in communication with the reactor cavity to allow molten salt 121 to flow therethrough. The coolant flow channels 1231 facilitate the flow of molten salt 121 into the reflector 123 to cool the reflector 123 and to facilitate the absorption of neutrons by the first transmutable nuclide in the molten salt 121.

[0048] Figure 1 The illustrated elements and Figure 4 The illustrated elements are part of a primary system of the hybrid molten salt reactor. It is understood that the hybrid molten salt reactor can further include a secondary system and a tertiary system in addition to the primary system. The primary system is used to generate heat, the secondary system is used to transfer heat generated by the primary system to the tertiary system, and the tertiary system can be used for nuclear energy comprehensive utilization such as power generation, heat supply, steam supply, device power supply, seawater desalination, etc. The primary system relies on a primary pump to provide a forced circulation driving force. The liquid molten salt in the primary system is both fuel and coolant, and operates at atmospheric pressure. The molten salt flows through the core via a molten salt channel to generate heat, and carries the heat out of the core, through a molten salt circulation pipeline into a heat exchanger to transfer heat to secondary molten salt, and then the primary molten salt enters the core via the primary pump. The secondary system includes a steam generator and a secondary circulation pump. The secondary system relies on the secondary circulation pump to provide a forced circulation driving force. The secondary molten salt does not contain fuel and operates at atmospheric pressure. The secondary molten salt is heated in the heat exchanger and then flows into the steam generator to transfer heat to the tertiary working medium, and then returns to the inlet of the heat exchanger via the secondary circulation pump.

[0049] The foregoing merely illustrates the principles of the application. Various modifications and changes can be made as would be obvious to a person skilled in the art having the benefit of this disclosure. It is intended that the application embrace all such modifications and changes and, accordingly, the application to be limited only by the claims.

[0050] 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.

[0051] 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.

[0052] 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, include: A reactor vessel, having a reactor cavity; 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.

2. The hybrid molten salt reactor as described in claim 1, characterized in that, The reactor vessel also has a molten salt inlet and a molten salt outlet, and the hybrid molten salt reactor further includes: A molten salt circulation pipeline is connected to the molten salt inlet and the molten salt outlet, respectively; 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.

3. The hybrid molten salt reactor as described in claim 2, characterized in that, Also includes: 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.

4. The hybrid molten salt reactor as described in claim 1, characterized in that, Also includes: 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.

5. The hybrid molten salt reactor as described in claim 1, characterized in that, Also includes: 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.

6. The mixed molten salt reactor as described in claim 5, characterized in that, The reflective layer includes a graphite layer.

7. The mixed molten salt reactor as described in any one of claims 1-6, characterized in that, The solid fuel assembly includes a square assembly or a hexagonal assembly.

8. The mixed molten salt reactor as described in any one of claims 1-6, characterized in that, 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 mixed molten salt reactor as described in any one of claims 1-6, characterized in that, The fuel pellets are composed of one or more of the following: uranium-plutonium-zirconium alloy fuel, mixed oxide fuel, and minor actinide fuel.

10. The mixed molten salt reactor as described in any one of claims 1-6, characterized in that, The fissile nuclides include any one or more of uranium-233, uranium-235, and plutonium-239; and / or The first convertible nuclide includes thorium-232 and / or uranium-238; and / or The second convertible nuclide includes uranium-238 and / or thorium-232.

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