Design method of nuclear island main building and layout structure of reactor nuclear island main building

Abstract

The present application discloses a design method for a nuclear island main building and a layout structure of a reactor nuclear island main building, the design method comprising the following steps: S100: dividing the nuclear island main building into functional modules including a reactor body module, a primary circuit auxiliary system module, a fuel operation and component equipment cleaning module, a fuel storage module, a secondary circuit main system module, a secondary circuit auxiliary system module, and an accident residual heat removal module according to functions; S200: determining the position of the reactor body module; S300: obtaining dominant association attributes between the reactor body module and other multiple functional modules, and between other multiple functional modules; S400: determining the positions of other multiple functional modules according to the position of the reactor body module and the dominant association attributes and priorities between the reactor body module and other multiple functional modules; S500: determining the positions of each sub-functional module according to the dominant association attributes between the sub-functional modules in each functional module.

Description

Technical Field

[0001] The embodiments of the present application relate to a design method for a nuclear island main building, and more particularly to a design method for a nuclear island main building applicable to a sodium-cooled fast neutron reactor and a reactor nuclear island main building layout structure. Background Art

[0002] The main building of the nuclear island of a nuclear power plant is a building that houses the reactor, nuclear steam supply and its auxiliary systems. The overall layout design of the main building of the nuclear island studies the overall layout of the main building of the nuclear island, determines the overall layout of the main building of the nuclear island, and then forms the architectural drawing of the main building of the nuclear island. The overall layout design of the main building of the nuclear island of a nuclear power plant is closely related to the selection of coolant for the main process system of the nuclear island of the nuclear power plant, the configuration of the main process system, and the setting of supporting systems serving the main process system. There are great differences in the overall layout of the main building of the nuclear island for different nuclear power unit types.

[0003] As a fourth-generation nuclear power technology, the sodium-cooled fast neutron reactor (hereinafter referred to as the sodium-cooled fast reactor) has a very different layout from that of the second-generation and third-generation pressurized water reactor nuclear power units due to the characteristics of the reactor itself and the differences in the coolant and process system settings. The overall layout design schemes that can be used for reference are limited; at the same time, the overall layout design of the main plant of the sodium-cooled fast reactor nuclear island lacks an effective forward design process. How to achieve the compactness of the overall layout of the main plant of the sodium-cooled fast reactor nuclear island and improve the rationality and economy of the overall layout design of the main plant of the sodium-cooled fast reactor nuclear island is an urgent problem to be solved. Summary of the invention

[0004] In order to solve at least one of the above-mentioned or other technical problems, the embodiments of the present application provide a design method for a nuclear island main building and a layout structure of a reactor nuclear island main building, which can realize the compactness of the overall layout of the sodium-cooled fast reactor nuclear island main building and improve the rationality and economy of the overall layout design of the sodium-cooled fast reactor nuclear island main building.

[0005] According to an embodiment of one aspect of the present application, a design method for a nuclear island main building is provided, comprising the following steps: S100: dividing the nuclear island main building into functional modules including a reactor body module, a primary loop auxiliary system module, a fuel operation and component equipment cleaning module, a fuel storage module, a secondary loop main system module, a secondary loop auxiliary system module, and an accident residual heat removal module; S200: determining the position of the reactor body module; S300: obtaining dominant association attributes between the reactor body module and other multiple functional modules, and between other multiple functional modules, wherein the dominant association attributes include natural circulation requirements, radiation protection requirements, and transportation distance requirements, wherein the priority of the natural circulation requirements is The priority level is higher than that of the radiation protection requirement, and the priority of the radiation protection requirement is higher than that of the transfer distance; S400: determining the positions of multiple functional modules according to the position of the reactor body module and the dominant association attributes and priorities with other multiple functional modules; and S500: determining the positions of each sub-functional module according to the dominant association attributes between the sub-functional modules in each functional module; wherein the natural circulation requirement represents that there is a structure for heat exchange using a naturally circulating coolant between the two functional modules, the radiation protection requirement represents that there is a pipeline with radiation material flowing between the two functional modules, and the transfer distance requirement represents that there is material transfer between the two functional modules.

[0006] According to an embodiment of another aspect of the present application, a reactor nuclear island main building layout structure is provided, including: a reactor body module; a secondary circuit main system module, which is arranged adjacent to the reactor body module; an accident waste heat removal module, which is respectively arranged adjacent to the reactor body module and the secondary circuit main system module; a primary circuit auxiliary system module, which is symmetrically arranged on both sides of the reactor body module with respect to the secondary circuit main system module; a fuel operation and component equipment cleaning module, which is symmetrically arranged on both sides of the reactor body module with respect to the accident waste heat removal module; and a fuel storage module, which is arranged adjacent to the fuel operation and component equipment cleaning module.

[0007] According to the design method of the nuclear island main building of the embodiment of the present application, the nuclear island main building is divided into multiple functional modules according to its function. By sorting out the forward design process of the overall layout design of the fast reactor nuclear island main building, the dominant correlation attributes and factors between the various functional modules in the overall layout design of the nuclear island main building are identified, which are used to guide the overall layout design of the fast reactor nuclear island main building, which is conducive to realizing the compact design of the overall layout of the nuclear island main building and improving the rationality and economy of the overall layout design of the pool-type sodium-cooled fast reactor nuclear island main building. BRIEF DESCRIPTION OF THE DRAWINGS

[0008] Figure 1 is a flow chart of a design method for a nuclear island main building according to an embodiment of the present application;

[0009] Figure 2 It is a schematic diagram of the dominant association attributes between various functional modules and between various sub-modules according to the design method of the nuclear island main plant in an embodiment of the present application;

[0010] Figure 3 is a flowchart of a design method for a nuclear island main building according to another embodiment of the present application; and

[0011] Figure 4 It is a schematic plan view of the layout structure of the main building of the reactor nuclear island according to an embodiment of the present application.

[0012] In the above drawings, the meanings of the reference numerals are as follows:

[0013] 100- Reactor body module;

[0014] 200-Secondary circuit main system module;

[0015] 210 - sodium distributor submodule;

[0016] 220-steam generator submodule;

[0017] 230 - sodium buffer tank module;

[0018] 240-main pump submodule;

[0019] 300- accident residual heat discharge module;

[0020] 400-primary circuit auxiliary system module;

[0021] 410- Radioactive argon purge and decay submodule;

[0022] 420-primary circuit sodium purification submodule;

[0023] 430-primary circuit sodium charging and discharging submodule;

[0024] 500-Fuel handling and component equipment cleaning module; and

[0025] 600 - Fuel storage module. DETAILED DESCRIPTION

[0026] In order to make the objectives, technical solutions and advantages of the present application more clearly understood, the present application is further described in detail below in combination with specific embodiments and with reference to the accompanying drawings.

[0027] However, it should be understood that these descriptions are exemplary only and are not intended to limit the scope of the present application. In the following detailed description, for ease of explanation, many specific details are set forth to provide a comprehensive understanding of the embodiments of the present application. However, it is apparent that one or more embodiments may also be implemented without these specific details. In addition, in the following description, the description of the known technology is omitted to avoid unnecessary confusion of the concept of the present application.

[0028] The terms used herein are only for describing specific embodiments and are not intended to limit the present application. The term "comprising" used herein indicates the existence of features, steps, operations, but does not exclude the existence or addition of one or more other features.

[0029] All terms (including technical and scientific terms) used herein have the meanings commonly understood by those skilled in the art, unless otherwise defined. It should be noted that the terms used herein should be interpreted as having a meaning consistent with the context of this specification, and should not be interpreted in an idealized or overly rigid manner.

[0030] Figure 1 It is a flow chart of a design method for a nuclear island main building according to an embodiment of the present application.

[0031] According to an embodiment of one aspect of the present application, a design method for a nuclear island main plant is provided, such as Figure 1 As shown, it includes steps S100 to S500.

[0032] Step S100 includes dividing the main building of the nuclear island into functional modules including a reactor body module, a primary circuit auxiliary system module, a fuel operation and component equipment cleaning module, a fuel storage module, a secondary circuit main system module, a secondary circuit auxiliary system module, and an accident residual heat removal module.

[0033] Step S200 includes determining the position of the reactor body module.

[0034] Step S300 includes obtaining dominant association attributes between the reactor body module and other multiple functional modules, and between other multiple functional modules, wherein the dominant association attributes include natural circulation requirements, radiation protection requirements, and transfer distance requirements, wherein the priority of the natural circulation requirement is higher than the priority of the radiation protection requirement, and the priority of the radiation protection requirement is higher than the priority of the transfer distance.

[0035] Step S400 includes determining the positions of the other multiple functional modules according to the position of the reactor body module and the dominant association attributes and priorities with the other multiple functional modules; and

[0036] Step S500 includes determining the positions of the sub-functional modules according to the dominant association attributes between the sub-functional modules within each functional module.

[0037] In step S300, the natural circulation requirement indicates that there is a structure for heat exchange between two functional modules using a naturally circulating coolant, the radiation protection requirement indicates that there is a pipeline with radiation materials flowing between the two functional modules, and the transfer distance requirement indicates that there is material transfer between the two functional modules.

[0038] In this embodiment, the nuclear island main building is divided into multiple functional modules according to its function. By sorting out the forward design process of the overall layout design of the fast reactor nuclear island main building, the dominant correlation attributes and factors between the functional modules in the overall layout design of the nuclear island main building are identified to guide the overall layout design of the fast reactor nuclear island main building, which is conducive to realizing the compact design of the overall layout of the nuclear island main building and improving the rationality and economy of the overall layout design of the pool-type sodium-cooled fast reactor nuclear island main building.

[0039] Figure 2 It is a schematic diagram of the dominant association attributes between various functional modules and between various sub-modules in the design method of the nuclear island main plant according to an embodiment of the present application.

[0040] According to some embodiments of the present application, Figure 2 As shown, in step S300, the natural circulation requirement is met between the reactor body module and the secondary loop main system module, the natural circulation requirement is met between the reactor body module and the accident residual heat removal module, the radiation protection requirement is met between the primary loop auxiliary system module and the reactor body module, the transfer distance requirement is met between the reactor body module and the fuel operation and component equipment cleaning module, and the transfer distance requirement is met between the fuel operation and component equipment cleaning module and the fuel storage module.

[0041] According to some embodiments of the present application, step S400 includes sub-steps S410 to S430.

[0042] Sub-step S410 includes respectively arranging the secondary circuit main system module, the accident residual heat removal module and the reactor body module adjacent to each other so as to minimize the length of the main pipeline.

[0043] Sub-step S420 includes arranging the primary auxiliary system module adjacent to the reactor main module to minimize the cost of radiation protection.

[0044] Sub-step S430 includes arranging the fuel operation and component equipment cleaning module, the fuel storage module and the reactor body module adjacent to each other so that the relative distance is the shortest.

[0045] According to some embodiments of the present application, the secondary circuit main system module includes a sodium distribution submodule, a steam generator submodule, a sodium buffer tank submodule and a main pump submodule which are sequentially connected through a sodium pipeline. In sub-step S410, the positions of the steam generator submodule, the sodium buffer tank submodule, the main pump submodule and the sodium distribution submodule are determined in sequence to make the total length of the sodium pipeline as short as possible.

[0046] According to some embodiments of the present application, sub-step S410 includes sub-steps S411 to S412.

[0047] Sub-step S411 includes determining the position of the steam generator sub-module according to the relative height between the steam generator sub-module and the reactor body module.

[0048] Sub-step S412 includes determining the positions of the sodium buffer tank sub-module, the main pump sub-module, and the sodium distribution sub-module according to the position of the steam generator sub-module.

[0049] According to some embodiments of the present application, in sub-step S420, factors affecting the cost of radiation protection include the length of the radioactive pipeline, the length of the sodium pipeline, and the thickness of the shielding layer.

[0050] In this embodiment, the sodium coolant in the primary circuit is radioactive and needs to be subjected to radiation protection treatment, which is mainly reflected in the protection of the sodium coolant flowing through the pipeline. Correspondingly, the pipeline length and the thickness of the protective layer are the main influencing factors of the radiation protection cost.

[0051] According to some embodiments of the present application, the primary-loop auxiliary system module includes a radioactive argon purge and decay submodule, a primary-loop sodium purification submodule and a primary-loop sodium filling and discharge submodule, and step S500 includes: arranging the radioactive argon purge and decay submodule adjacent to the reactor body module to ensure that the length of the radioactive pipeline between the radioactive argon purge and decay submodule and the reactor body module is the shortest; arranging the primary-loop sodium purification submodule adjacent to the reactor body module to ensure that the thickness of the shielding layer between the primary-loop sodium purification submodule and the reactor body module is the minimum; and arranging the primary-loop sodium filling and discharge submodule adjacent to the reactor body module to ensure that the length of the sodium pipeline between the primary-loop sodium filling and discharge and the reactor body module is the shortest.

[0052] According to some embodiments of the present application, after sub-step S410, the step is also included: arranging the secondary loop auxiliary system module adjacent to the secondary loop main system module to minimize the cost of radiation protection, wherein the secondary loop auxiliary system module and the secondary loop main system module meet the radiation protection requirements.

[0053] According to some embodiments of the present application, the reactor body module is suitable for realizing core reaction and heat transfer.

[0054] According to some embodiments of the present application, step S600 is further included after step S500, in which the locations of the pipe corridors and process rooms of the auxiliary supporting systems of each functional module are determined in the order of ventilation, electrical, and instrumentation and control.

[0055] Figure 3 It is a flowchart of a design method for a nuclear island main building according to another embodiment of the present application.

[0056] According to some embodiments of the present application, Figure 3 As shown, the main plant of the nuclear island is first divided into areas according to function.

[0057] The process room where the reaction body is located is the reactor pit. The reactor pit is the core of the primary main system. Its position determines the location of the primary auxiliary system, fuel operation and components, equipment cleaning, fuel storage, secondary main system, secondary auxiliary system, and accident waste heat removal system. Based on this, the size and location of the reactor pit process room are determined first.

[0058] After the location of the reactor pit is determined, the dominant factor between the reactor pit and the process room of the primary-loop auxiliary system is radiation protection (such as the length of the radioactive pipeline, the number of process rooms, shielding thickness, etc.). Therefore, the location of the process room of the primary-loop radioactive auxiliary system is determined close to the reactor pit.

[0059] The present application is a sodium-cooled fast reactor, which adopts closed-loop refueling. The transportation distance between the fuel operation and component and equipment cleaning is the dominant factor between the reactor pit and the fuel operation and equipment cleaning process room. The location of the fuel operation and equipment cleaning process room is determined close to the reactor pit.

[0060] The dominant factors for the process rooms between the reactor pit and the steam generator, sodium buffer tank, and secondary circuit main pump of the secondary circuit main system are the natural circulation requirements (if any) and the length of the secondary circuit main pipeline. First, determine the relative height between the steam generator process room and the reactor pit, and then determine the location of the sodium buffer tank process room and the secondary circuit main pump process room.

[0061] The natural circulation requirements for accident waste heat removal determine the relative position of the reactor pit and the sodium-air heat exchanger process room, and further determine the position of the auxiliary process room of the accident waste heat removal system.

[0062] The size of the reactor hall is mainly determined by the fuel operation and equipment cleaning process, the primary circuit auxiliary system, and the secondary circuit main system.

[0063] The location of the steam generator process room determines the location of the steam generator accident protection system and the secondary circuit auxiliary system process room.

[0064] The relationship between the reactor and the fuel storage process determines the location of the fuel storage process room (e.g., new fuel, storage pool, etc.).

[0065] The relative positions of the above-mentioned main process modules form the overall layout of the main process of the nuclear island.

[0066] After completing the overall layout of the main processes of the nuclear island, determine the pipe corridors and process rooms of the auxiliary supporting systems of each main process module in the order of ventilation, electrical, and instrumentation and control. Then, combined with the overall layout of the main processes of the nuclear island, determine the overall layout of the main plant of the nuclear island.

[0067] Figure 4 It is a schematic plan view of the layout structure of the main building of the reactor nuclear island according to an embodiment of the present application.

[0068] According to another aspect of the present application, an embodiment provides a reactor nuclear island main building layout structure, such as Figure 4 As shown, it includes a reactor body module 100, a secondary circuit main system module 200, an accident residual heat removal module 300, a primary circuit auxiliary system module 400, a fuel operation and component equipment cleaning module 500 and a fuel storage module 600.

[0069] The secondary loop main system module 200 is arranged adjacent to the reactor body module 100 .

[0070] The accident residual heat removal module 300 is respectively arranged adjacent to the reactor body module 100 and the secondary circuit main system module 200 .

[0071] The primary loop auxiliary system module 400 and the secondary loop main system module 200 are symmetrically arranged on both sides of the reactor body module 100 .

[0072] The fuel operation and component equipment cleaning module 500 and the accident residual heat removal module 300 are symmetrically arranged on both sides of the reactor body module 100 .

[0073] The fuel storage module 600 is disposed adjacent to the fuel handling and component equipment cleaning module 500 .

[0074] According to some embodiments of the present application, the reactor body module includes a reactor main vessel, a primary circuit system device and a heat exchanger. The primary circuit system device is connected to the primary circuit auxiliary system module. The heat exchanger is connected to the secondary circuit main system module.

[0075] According to some embodiments of the present application, the primary auxiliary system module includes a radioactive argon purge and decay submodule 410, a primary sodium purification submodule 420, and a primary sodium charging and discharging submodule 430. The sodium charging and discharging submodule 430 is connected to the primary system equipment.

[0076] The primary sodium purification submodule 420 is connected to the primary sodium filling and discharging submodule 430 to purify impurities in the coolant sodium in the primary circuit, wherein the impurities include metals, non-metallic impurities, corrosion products and fission products, etc. The radioactive argon purge and decay submodule 410 is suitable for providing argon protection for the sodium in the primary circuit.

[0077] According to some embodiments of the present application, the fuel storage module includes a storage depot and a spent fuel storage pool. The storage depot is connected to the fuel operation and assembly equipment cleaning module, and the storage depot is suitable for storing new fuel assemblies. The spent fuel storage pool is connected to the fuel operation and assembly equipment cleaning module, and the spent fuel storage pool is suitable for storing spent fuel, damaged fuel, and providing a place for underwater operations to inspect, repair, and transport fuel.

[0078] According to some embodiments of the present application, the secondary circuit main system module includes a sodium distributor submodule 210, a steam generator submodule 220, a sodium buffer tank submodule 230, and a main pump submodule 240. The steam generator submodule 220 is connected to the heat exchanger. The sodium buffer tank submodule 230 is connected to the steam generator submodule 220. The main pump submodule 240 is arranged between the steam generator submodule 220 and the sodium buffer tank submodule 230.

[0079] According to some embodiments of the present application, the reactor nuclear island main building layout structure also includes a secondary circuit auxiliary system module, which includes a secondary circuit sodium charging and discharging submodule, a secondary circuit sodium purification submodule and a steam generator accident protection submodule. The secondary circuit sodium charging and discharging submodule is connected to the sodium buffer tank submodule 230. The secondary circuit sodium purification submodule is connected to the secondary circuit sodium charging and discharging submodule to purify impurities in the coolant sodium in the secondary circuit. The steam generator accident protection submodule is connected to the steam generator submodule.

[0080] According to some embodiments of the present application, the reactor nuclear island main building layout structure also includes an auxiliary supporting system, which includes a pipe gallery, which is suitable for connecting various functional modules to provide ventilation, electrical connection or communication connection between the modules.

[0081] So far, the embodiments of the present application have been described in detail in conjunction with the accompanying drawings. It should be noted that the implementation methods not shown or described in the drawings or the body of the specification are all forms known to ordinary technicians in the relevant technical field and are not described in detail. In addition, the above definitions of each component are not limited to the various specific structures, shapes or methods mentioned in the embodiments, and ordinary technicians in the field can simply change or replace them.

[0082] It should also be noted that, in the specific embodiments of the present application, unless otherwise indicated, the numerical parameters in the present specification and the attached claims are approximate values ​​and can be changed according to the desired characteristics obtained through the content of the present application. Specifically, all numbers used in the specification and claims to express the size, range conditions, etc. of the composition should be understood to be modified by the term "about" in all cases. In general, the meaning of the expression refers to the change of ±10% in some embodiments, ±5% in some embodiments, ±1% in some embodiments, and ±0.5% in some embodiments by a specific number.

[0083] It will be appreciated by those skilled in the art that the features described in the various embodiments and / or claims of the present application may be combined in a variety of ways and / or combinations, even if such combinations or combinations are not explicitly described in the present application. In particular, without departing from the spirit and teachings of the present application, the features described in the various embodiments and / or claims of the present application may be combined in a variety of ways and / or combinations. All of these combinations and / or combinations fall within the scope of the present application.

[0084] The specific embodiments described above further illustrate the purpose, technical solutions and beneficial effects of the present application. It should be understood that the above description is only a specific embodiment of the present application and is not intended to limit the present application. Any modifications, equivalent substitutions, improvements, etc. made within the spirit and principles of the present application should be included in the scope of protection of the present application.

Claims

1. A design method for a nuclear island main building, comprising the steps of: S100: The main building of the nuclear island is divided into functional modules including a reactor body module, a primary circuit auxiliary system module, a fuel operation and component equipment cleaning module, a fuel storage module, a secondary circuit main system module, a secondary circuit auxiliary system module, and an accident residual heat removal module according to the functions; S200: Determine the position of the reactor body module; S300: Obtaining dominant association attributes between the reactor body module and other multiple functional modules, and between other multiple functional modules, wherein the dominant association attributes include natural circulation requirements, radiation protection requirements, and transport distance requirements, wherein: The priority of the natural circulation requirement is higher than the priority of the radiation protection requirement, and the priority of the radiation protection requirement is higher than the priority of the transfer distance; S400: Determine the positions of the other multiple functional modules according to the position of the reactor body module and the dominant association attributes and priorities between the reactor body module and the other multiple functional modules; as well as S500: Determine the position of each sub-functional module according to the dominant association attribute between the sub-functional modules in each functional module; Among them, the natural circulation requirement indicates that there is a structure for heat exchange between two functional modules using a naturally circulating coolant, the radiation protection requirement indicates that there is a pipeline with radiation materials flowing between the two functional modules, and the transfer distance requirement indicates that there is a transfer of materials between the two functional modules; Wherein, step S400 includes sub-steps: S410, respectively arranging the secondary circuit main system module, the accident residual heat removal module and the reactor body module adjacent to each other so that the length of the main pipeline is the shortest; S420, arranging the primary loop auxiliary system module adjacent to the reactor body module to minimize the cost of radiation protection; and S430, arranging the fuel operation and component equipment cleaning module, the fuel storage module and the reactor body module adjacent to each other so that the relative distance is the shortest.

2. The design method according to claim 1, wherein: In step S300: the natural circulation requirement is met between the reactor body module and the secondary loop main system module, the natural circulation requirement is met between the reactor body module and the accident residual heat removal module, the radiation protection requirement is met between the primary loop auxiliary system module and the reactor body module, the transfer distance requirement is met between the reactor body module and the fuel operation and component equipment cleaning module, and the transfer distance requirement is met between the fuel operation and component equipment cleaning module and the fuel storage module.

3. The design method according to claim 1, wherein: The secondary circuit main system module includes a sodium distribution submodule, a steam generator submodule, a sodium buffer tank submodule and a main pump submodule which are sequentially connected through a sodium pipeline. In sub-step S410, the positions of the steam generator submodule, the sodium buffer tank submodule, the main pump submodule and the sodium distribution submodule are determined in sequence to make the total length of the sodium pipeline as short as possible.

4. The design method according to claim 3, wherein: The sub-step S410 includes the following sub-steps: S411, determining the position of the steam generator submodule according to the relative height between the steam generator submodule and the reactor body module; and S412: Determine the positions of the sodium buffer tank submodule, the main pump submodule, and the sodium distribution submodule according to the position of the steam generator submodule.

5. The design method according to claim 4, wherein: In sub-step S420, factors affecting the cost of the radiation protection include the length of the radioactive pipeline, the length of the sodium pipeline and the thickness of the shielding layer.

6. The design method according to claim 5, wherein: The primary loop auxiliary system module includes a radioactive argon purge and decay submodule, a primary loop sodium purification submodule and a primary loop sodium charging and discharging submodule. Step S500 includes: The radioactive argon purge and decay submodule is arranged adjacent to the reactor body module to ensure that the length of the radioactive pipeline between the radioactive argon purge and decay submodule and the reactor body module is the shortest; The primary sodium purification submodule is arranged adjacent to the reactor body module to ensure that the thickness of the shielding layer between the primary sodium purification submodule and the reactor body module is minimized; and The primary sodium charging and discharging submodule is arranged adjacent to the reactor main module to ensure that the length of the sodium pipeline between the primary sodium charging and discharging submodule and the reactor main module is the shortest.

7. The design method according to claim 1, wherein: After sub-step S410, the method further includes: arranging the secondary loop auxiliary system module adjacent to the secondary loop main system module to minimize the cost of radiation protection, wherein the secondary loop auxiliary system module and the secondary loop main system module meet the radiation protection requirements.

8. The design method according to claim 1, wherein: The reactor body module is suitable for realizing core reaction and heat transfer.

9. The design method according to claim 1, wherein: After step S500, the method further includes the following steps: S600, determine the location of the pipe gallery and process room of the auxiliary supporting systems of each functional module in the order of ventilation, electrical, and instrumentation and control.

10. A reactor nuclear island main building layout structure, comprising: Reactor body module; A secondary circuit main system module is disposed adjacent to the reactor body module; An accident residual heat removal module is respectively arranged adjacent to the reactor body module and the secondary circuit main system module; A primary loop auxiliary system module is symmetrically arranged on both sides of the reactor body module with respect to the secondary loop main system module; A fuel operation and component equipment cleaning module is symmetrically arranged on both sides of the reactor body module with respect to the accident residual heat removal module; as well as a fuel storage module disposed adjacent to the fuel handling and component equipment cleaning module; Wherein, the reactor body module comprises: The primary reactor vessel; A primary circuit system device connected to a primary circuit auxiliary system module; and The heat exchanger is connected to the secondary circuit main system module; The primary loop auxiliary system module comprises: A primary circuit sodium charging and discharging submodule, connected to the primary circuit system equipment; a primary circuit sodium purification submodule, connected to the primary circuit sodium charging and discharging submodule to purify impurities in the coolant sodium in the primary circuit; and The radioactive argon purge and decay submodule is suitable for providing argon protection for the sodium in the primary circuit.

11. The reactor nuclear island main building layout structure according to claim 10, wherein: The fuel storage module comprises: a storage reservoir connected to the fuel handling and assembly equipment cleaning module, the storage reservoir being suitable for storing new fuel assemblies; and The spent fuel storage pool is connected to the fuel operation and component equipment cleaning module. The spent fuel storage pool is suitable for storing spent fuel, damaged fuel and providing a place for underwater operations of inspecting, repairing and transporting fuel.

12. The reactor nuclear island main building layout structure according to claim 10, wherein: The secondary circuit main system module includes: a steam generator submodule, connected to the heat exchanger; a sodium buffer tank submodule connected to the steam generator submodule; and The main pump submodule is arranged between the steam generator submodule and the sodium buffer tank submodule.

13. The reactor nuclear island main building layout structure according to claim 12 further comprises a secondary circuit auxiliary system module, wherein the secondary circuit auxiliary system module comprises: A secondary circuit sodium charging and discharging submodule, connected to the sodium buffer tank module; A secondary circuit sodium purification submodule, connected to the secondary circuit sodium charging and discharging submodule, for purifying impurities in the coolant sodium in the secondary circuit; and The steam generator accident protection submodule is connected to the steam generator submodule.

14. The reactor nuclear island main building layout structure according to claim 10 further includes an auxiliary supporting system, wherein the auxiliary supporting system includes a pipe gallery, and the pipe gallery is suitable for connecting various functional modules to provide ventilation, electrical connection or communication connection between various modules.

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