A nuclear power generating system

Abstract

This invention relates to the field of nuclear power technology and discloses a nuclear power generation system comprising multiple active large reactor modules. Electrical equipment in the active large reactor modules, with different voltages and currents, is connected to external power transmission cables via a distribution cabinet. The distribution cabinet of the active large reactor modules is also connected to an off-site power source via cables to provide basic power. The system also includes a floating platform module, a passive small reactor module, and a mooring module. The floating platform module is located within a breakwater adjacent to the nuclear power plant site. The passive small reactor module is mounted on the floating platform module to cope with natural disasters such as earthquakes and floods. The passive small reactor module includes a small nuclear reactor, a distribution box, and self-generating equipment. The distribution box is connected to the distribution cabinet of the active large reactor module via cables. The mooring module is connected to both the floating platform and the landmass of the nuclear power plant site. This invention is a multi-functional system that integrates power supply, safety, and economy.

Description

Technical Field

[0001] This invention relates to the field of nuclear power technology, and in particular to a nuclear power generation system. Background Technology

[0002] Nuclear reactor power generation, as a clean and efficient form of energy, occupies an important position in the global energy structure. Currently, the types of reactors used in the construction of nuclear reactor power plants include two categories: small active reactor modules (SARMs) and large active reactor modules (MAMs). Both typically require an external power source to provide basic electricity to maintain operation.

[0003] Currently, the construction of nuclear reactor power plants typically employs either passive small reactor modules (SSMEs) or active large reactor modules (MRTs) to ensure engineering coordination, standardized maintenance, and common spare parts. However, while using SSMEs offers advantages over MRTs, such as smaller size, more flexible placement, lower external power requirements, and the ability to utilize emergency diesel generators to maintain the cooling system, their individual power output is lower, and their construction cost is significantly higher. Conversely, using MRTs provides stable power output and relatively lower costs, but their operation is entirely dependent on external power. A power outage not only prevents the normal transmission of electricity but also... The inability of cooling equipment to dissipate heat prevents the removal of residual heat generated in the reactor core and other parts of the reactor, resulting in extreme safety risks. Although active small reactor modules and active large reactor modules are currently being built simultaneously at the same site to ensure normal power supply, these two types of reactors mostly operate independently, failing to form an effective coupling and coordination of stable power supply, safety, and economy. Furthermore, under the influence of multiple extreme natural disasters such as earthquakes, floods, and tsunamis, the safety of active large reactor modules currently built according to the single-accident criterion will face severe challenges. They will be threatened by multiple factors, including external power outages after earthquakes and internal power shortages after site flooding, making safe power supply extremely difficult and ultimately inevitably leading to serious accidents. Therefore, there is an urgent need for a nuclear power generation system that can balance power supply, safety, and economy. Summary of the Invention

[0005] This invention provides a nuclear power generation system that integrates power supply, safety, and economy.

[0006] This invention provides a nuclear power generation system comprising multiple active large reactor modules. Electrical equipment of different voltages and currents within the active large reactor modules is connected to external power transmission cables via a distribution cabinet. The distribution cabinet of the active large reactor modules is also connected via cables to an external power source providing basic power. The multiple active large reactor modules are located on land at the nuclear power plant site. The system also includes a floating platform module, a passive small reactor module, and a mooring module. The floating platform module is located within a breakwater adjacent to the nuclear power plant site. The passive small reactor module is mounted on the floating platform module to cope with natural disasters such as earthquakes and floods. The passive small reactor module includes a small nuclear reactor, a distribution box for power control, and self-generating equipment for providing basic power. The distribution box is connected to the distribution cabinet of the active large reactor module via cables to continue providing basic power to the active large reactor module even after the external power supply is disconnected. The mooring module is connected to both the floating platform and the land at the nuclear power plant site for towing and mooring the floating platform module.

[0007] Preferably, a safety water pool for cooling and heat dissipation is provided outside the small nuclear reactor, and the safety water pool is equipped with a cooling water sharing module.

[0008] Preferably, the cooling water sharing module includes pipes connected to the safety water pool and control valves. The other end of the pipes is connected to the cooling water pools in each active large reactor module through branch pipes. Each branch pipe is independently equipped with a valve. When the water in the active large reactor module that is used to cool the corresponding large nuclear reactor is exhausted, the safety water pool can provide an emergency cooling water source to its pool.

[0009] Preferably, the ratio of active large reactor modules to passive small reactor modules is 4:1 to 6:1.

[0010] Preferably, the power output terminal of the self-generating equipment is equipped with an energy storage module for storing electricity, in order to maintain a normal basic power supply when the grid fluctuates or the power generation of the self-generating equipment is unstable.

[0011] Preferably, the floating platform module is connected to an energy-absorbing seismic module at the base.

[0012] Preferably, the cables connecting the distribution box and the distribution cabinet of the active large reactor module are all flexible, bendable cables.

[0013] Preferably, the cables connecting the distribution box to the distribution cabinet of the active large reactor module have an extendable redundant length to meet the needs of floating platform movement.

[0014] Preferably, the redundant length of the cable connecting the distribution box to the distribution cabinet of the active large reactor module is 50m to 60m.

[0015] Preferably, the limiting mooring module includes multiple traction cables that are respectively connected to the floating platform and the nuclear power plant site land, for mitigating the swaying amplitude of the floating platform module after it floats.

[0016] Compared with existing technologies, the beneficial effects of this invention are as follows: This invention achieves the dual goals of "high safety and optimal economy" at the same nuclear power plant site, truly constructing a nuclear power generation system that can balance power supply reliability, inherent safety, and operational economy. Specifically, this invention arranges highly safe passive small reactor modules on a floating platform and establishes a power connection with the distribution cabinets of multiple highly economical active reactor modules on land through a distribution box, forming an organic coupling. When an off-site power loss accident occurs, the passive small reactor, due to its characteristic of continuous operation without external power, immediately acts as a backup power source to supply power to the active reactor modules, ensuring that the active electrical equipment of its safety system can continue to operate. Effectively dissipating residual heat and preventing core meltdown, the floating platform design allows the small nuclear reactor to float with the water level and avoid being submerged in extreme flooding disasters such as earthquake-induced tsunamis and plant flooding. The mooring system restricts its drift, ensuring that it remains in a safe position and continues to generate electricity. Thus, this invention "transfers" the high safety characteristics of the passive small nuclear reactor to the active large reactor module, significantly improving the ability of all units within the site to withstand extreme and superimposed accidents. Furthermore, the active large reactor module, due to its high economic efficiency and absolute dominance in power generation, ensures that the overall average cost per kilowatt-hour of the site remains low. This achieves the dual benefits of near-maximum safety factor reactor type and near-maximum economic factor reactor type on the same nuclear power plant site. Attached Figure Description

[0018] Figure 1 This is a front view structural diagram of a passive small reactor module of a nuclear power generation system provided in an embodiment of the present invention; Figure 2 This is a connection diagram of a nuclear power generation system provided in an embodiment of the present invention; Figure 3 This is a top-view structural diagram of a passive small reactor module of a nuclear power generation system provided in an embodiment of the present invention.

[0019] Explanation of reference numerals in the attached figures: 1. Active large reactor module; 2. Floating platform module; 3. Passive small reactor module; 31. Self-generating equipment; 4. Limiting mooring module; 5. Energy storage module; 6. Seismic resistance module. Detailed Implementation

[0020] The following detailed description of a specific embodiment of the present invention is provided in conjunction with the accompanying drawings. However, it should be understood that the scope of protection of the present invention is not limited to the specific embodiment.

[0021] In the description of this invention, it should be understood that the terms "center," "longitudinal," "lateral," "length," "width," "thickness," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," "axial," "radial," and "circumferential" indicate the orientation or positional relationship based on the orientation or positional relationship shown in the accompanying drawings. They are only for the convenience of describing the technical solution of this invention and simplifying the description, and 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. Therefore, they should not be construed as limitations on this invention.

[0022] The design requirements for existing civilian nuclear reactor power plants are to improve economic efficiency while ensuring safety. Therefore, the current mainstream design approach is to balance safety and economy in a single reactor. However, these two requirements are often difficult to achieve optimally in all cases. For example, when we adopt the "redundancy" principle in reactor safety design and design multiple sets of batteries and multiple sets of diesel generators for a "total power outage accident," the redundancy and mutual backup of such multiple safety measures will significantly increase the economic cost of the nuclear power plant. Moreover, even with such redundant safety equipment, it can only be activated and function for a short period of time. For example, traditionally, batteries have a lifespan of about 10 hours, and diesel generators rely on limited fuel. In the event of a large-scale accident, it is difficult to effectively replenish fuel to maintain continuous operation. In other words, for a nuclear reactor power plant design, it is difficult to achieve both, either prioritizing safety or prioritizing economy. Therefore, there is an urgent need for a nuclear power generation system that can balance power supply, safety, and economy.

[0023] refer to Figure 1 , Figure 2 and Figure 3This invention provides a nuclear power generation system, comprising multiple active large reactor modules 1. Electrical equipment of different voltages and currents within each active large reactor module 1 is connected to external power transmission cables via a distribution cabinet. The distribution cabinet of each active large reactor module 1 is also connected via cables to an off-site power source providing basic electrical energy. The multiple active large reactor modules 1 are located on land at the nuclear power plant site. The system also includes: a floating platform module 2, a passive small reactor module 3, and a mooring module 4. The floating platform module 2 is located within a breakwater adjacent to the nuclear power plant site. The passive small reactor module 3 is installed on the floating platform module 2 to cope with natural disasters such as earthquakes and floods. The passive small reactor module 3 includes a small nuclear reactor, a power distribution box for power control, and a self-generating device 31 for providing basic power. The power distribution box is connected to the power distribution cabinet of the active large reactor module 1 through cables, so that it can still provide basic power to the active large reactor module 1 after the off-site power supply is disconnected. The restraining and mooring module 4 is connected to the floating platform and the land of the nuclear power plant site respectively, and is used for towing and restraining the floating platform module 2.

[0024] In the above embodiments, the present invention achieves the dual goals of "high safety and optimal economy" at the same nuclear power plant site, truly constructing a nuclear power generation system that can balance power supply reliability, inherent safety, and operational economy. Specifically, the present invention arranges the highly safe passive small reactor module 3 on a floating platform and establishes a power connection with the distribution cabinets of multiple highly economical active reactor modules 1 on land through a distribution box, forming an organic coupling. When an off-site power loss accident occurs, the passive small reactor, with its characteristic of continuous operation without external power, immediately acts as a backup power source to supply power to the active reactor module 1, ensuring that the active electrical equipment of its safety system can continue to operate and effectively dissipate residual heat. To prevent core meltdown, the floating platform design allows the small nuclear reactor to float with the water level and avoid being submerged in extreme flooding disasters such as earthquake-induced tsunamis and plant flooding. The mooring system restricts its drift, ensuring that it remains in a safe position and continues to generate electricity. Thus, this invention "transfers" the high safety characteristics of the passive small nuclear reactor to the active large reactor module 1, significantly improving the ability of all units within the site to withstand extreme and superimposed accidents. Furthermore, the active large reactor module 1, due to its high economic efficiency and absolute dominance in power generation, ensures that the overall average cost per kilowatt-hour of the site remains low. This achieves the dual benefits of having safety levels close to the highest safety factor reactor type and economic efficiency close to the highest economic factor reactor type at the same nuclear power plant site.

[0025] Specifically, the electrical equipment of the powered large reactor module 1 includes all electric pumps, electric valves, electric doors, electric monitoring systems, etc. The floating platform module 2 is fixed on the dry dock. The self-generating equipment 31 is preferably a steam turbine and a rotor generator, which can generate electricity on its own and provide basic electrical energy output.

[0026] Further, refer to Figure 2 The small nuclear reactor is equipped with a safety water pool for cooling and heat dissipation, and the safety water pool is equipped with a cooling water sharing module.

[0027] In the above embodiments, the safety pool of the passive small nuclear reactor is itself part of its passive safety system, used for long-term removal of residual heat from the reactor core. A shared cooling water module is added on top of this, allowing the emergency cooling water in the pool to not only be used for the small nuclear reactor itself, but also to serve as an external emergency water source to provide critical cooling for the active large reactor module 1 in the event of a cooling water depletion accident, such as a large breach loss-of-coolant accident. This significantly extends the accident response time window and further enhances the site's defense-in-depth capability. Specifically, the cooling water in the active large reactor module 1 typically experiences single-unit anomalies; therefore, the cooling water in the safety pool of the small nuclear reactor is sufficient to handle such anomalies. Under normal circumstances, the cooling system involves the pressure vessel generating steam to remove heat. The steam then powers a turbine to generate electricity, and after liquefaction and preparation in the condenser, it returns to the pressure vessel to continue removing heat. Under shutdown conditions, heat can be dissipated to the water in the watertight compartment / pool through a dedicated cooling circuit within the pressure vessel.

[0028] Further, refer to Figure 2 The cooling water sharing module includes pipelines and control valves connected to the safety water pool. The other end of the pipelines is connected to the cooling water pools in each active large reactor module 1 through branch pipes. Each branch pipe is independently equipped with a valve. When the water in the active large reactor module 1 used to cool the corresponding large nuclear reactor is exhausted, the safety water pool can provide an emergency cooling water source to its pool.

[0029] In the above embodiments, the independent pipeline, control valve, and valve design enables refined and intelligent scheduling of cooling water resources. In the event of an accident, the corresponding valve can be opened selectively based on which active large reactor module 1 requires support, precisely delivering the valuable cooling water from the small nuclear reactor safety pool to the required location. This design avoids resource waste, ensures the effectiveness and reliability of emergency response, and demonstrates the system's high controllability and safety.

[0030] Further, refer to Figure 2 The ratio of active large reactor module 1 to passive small reactor module 3 is 4:1 to 6:1.

[0031] In the above embodiments, the ratio range is a preferred scheme obtained through optimized calculations. Under this ratio, the total installed capacity of the passive small nuclear reactor is typically around 100MW, which accounts for only about 1% to 2% of the total installed capacity of the site. With a single 100MW reactor paired with 4 to 6 1250MW active large reactor modules 1, the high safety of the small nuclear reactor can be fully utilized, while its high unit construction cost is diluted by the superior number and economic efficiency of the active large reactor modules 1. This ensures that the overall average cost per kilowatt-hour of the site remains competitive in the market, achieving an optimal balance between safety investment and economic output.

[0032] Further, refer to Figure 2 The power output terminal of the self-generating equipment 31 is equipped with an energy storage module 5 for storing electricity, which is used to maintain a normal basic power supply when the power grid fluctuates or the power generation of the self-generating equipment 31 is unstable.

[0033] In the above embodiments, the introduction of energy storage module 5, such as conventional lithium battery energy storage or molten salt thermal energy storage system, plays the role of "stabilizer". When the external power grid fluctuates or the power output of the passive small nuclear reactor becomes unstable, the energy storage module 5 can charge and discharge quickly, smooth the power output, and ensure that the backup power supplied to the active large reactor module 1 is stable and reliable. This avoids unnecessary protection actions or equipment damage to the active large reactor module 1 caused by power fluctuations, and enhances the robustness of the entire power supply system.

[0034] Further, refer to Figure 1 and Figure 3 The floating platform module 2 is located at the base and is connected to the seismic-resistant module 6 for energy absorption.

[0035] In the above embodiments, the seismic module 6 can be implemented using a combination of traditional vibration isolation structures such as spring dampers, elastic plates, and metal to achieve the purpose of seismic resistance. The seismic module 6, i.e., spring dampers, rubber vibration isolation pads, etc., forms a buffer layer between the platform and the base. When an earthquake occurs, this module can effectively absorb and dissipate the energy transmitted to the platform by seismic waves, significantly reduce the seismic load on the platform and the upper small nuclear reactor structure, protect key equipment and pipelines from damage, and ensure that the small nuclear reactor can still operate safely after the earthquake. This is a specific enhancement of the "seismic resistance" function of the floating platform.

[0036] Furthermore, the cables connecting the distribution box to the distribution cabinet of the powered large reactor module 1 are all flexible, bendable cables.

[0037] In the above embodiments, flexible cables are used instead of rigid busbars, which allows the connection to adapt to the displacement and swaying of the floating platform under wind, waves, water level changes or earthquakes. The cables can bend without breaking or coming apart, ensuring the physical integrity of the power transmission channel and the reliability of the electrical connection. This is a key design detail that achieves the unity of the seemingly contradictory concepts of "floating" and "connection".

[0038] Furthermore, the cables electrically connecting the distribution box to the distribution cabinet of the powered large reactor module 1 have an extendable redundant length to meet the needs of the floating platform's movement.

[0039] In the above embodiments, redundant length is further reserved on the basis of flexible cables, providing sufficient space for the maximum vertical displacement that the platform may experience, such as the buoyancy height during extreme floods, as well as horizontal displacement. This ensures that under any design-base failure, the cable will not be subjected to excessive tensile force due to straightening or tension, fundamentally eliminating the risk of power outage due to physical connection failure. The cable has good elasticity and tensile strength, which can adapt to platform floating, seismic tension, and other situations, ensuring uninterrupted power transmission.

[0040] Furthermore, the redundant length of the cable connecting the distribution box to the distribution cabinet of the powered large reactor module 1 is 50m to 60m.

[0041] In the above embodiments, the redundancy length range is a typical value derived from a comprehensive analysis of extreme tsunami inundation depths, platform design drafts, and allowable drift of the mooring system. It fully meets the requirements for handling extreme conditions while avoiding the cable tangling, management, and cost issues caused by excessive redundancy, representing another balance between safety and economy in the design details.

[0042] Further, refer to Figure 1 The limiting mooring module 4 includes multiple traction cables that are respectively connected to the floating platform and the nuclear power plant site land, used to reduce the swaying amplitude of the floating platform module 2 after it floats.

[0043] In the above embodiments, the mooring system composed of multiple traction cables not only serves as a "limiting" function to prevent platform drift, but more importantly, through reasonable arrangement and tension control, it can significantly suppress the platform's roll, pitch, and heave amplitude under the action of wind, waves, or water flow. A stable platform attitude is crucial for the stable operation of small nuclear reactors, the control of internal fluid sloshing, and the reliability of pipeline connections.

[0044] This invention provides a method to address accident risks. Specifically, when the passive small reactor module 3 is in use, if unpredictable problems occur that prevent the aforementioned safety measures from effectively cooling the small nuclear reactor placed on the floating platform module 2 or in the dry dock, posing a serious risk of core meltdown, the following decommissioning / shipping process can be implemented: First, a remotely controlled unmanned tugboat is deployed 24 / 7 near the floating platform module 2 or the sea area carrying the small nuclear reactor. Second, the anchoring points of the floating platform or hull of the small nuclear reactor can be automatically released via command, and redundant directional detonation points are set up. Even if the automatic release fails, the anchoring points can be manually detonated to destroy them. The isolation door of the dry dock is opened by blasting. The purpose of the isolation door is to prevent the entry of external seawater when closed, thus forming a dry dock. After the isolation door is opened, seawater enters, the floating platform / hull floats up, and can quickly enter the predetermined offshore disposal area along a pre-set waterway via the shortest path. Next, an autonomous unmanned tugboat, or if necessary, a backup manned tugboat, tows all the floating platforms / ships of the small nuclear reactors, whose maintenance personnel have been evacuated, to the predetermined disposal area. The bottom of the ship is then blasted, and it is sunk in a pre-set specific area in the offshore sea. Finally, an artificial / explored natural seabed depression has been pre-set in this area. After the small nuclear reactor is abandoned, a large number of wave-breaking stones / other buried materials can be sunk into the depression area to delay the possible release of radioactive contaminants.

[0045] In summary, this invention addresses the core technical challenge of balancing high safety and high economy in the construction of nuclear power plants at a single site. While the active large reactor module 1 offers good economics, it relies on external power sources and has weak disaster resistance; conversely, while the passive small reactor offers high safety, it has high construction costs and a low power generation share. This invention proposes an innovative "large and small reactor coupling, symbiotic land-water operation" system architecture. By independently mounting the highly safe passive small reactor module 3 on a floating platform and securing it within the site's breakwater using a restraining mooring module 4, the small reactor can effectively avoid direct impacts from extreme natural disasters such as earthquakes, tsunamis, and floods on the core equipment of the nuclear island. Furthermore, it enables the small reactor to operate continuously independently of external power sources during accident conditions. Simultaneously, by interconnecting the small reactor's distribution box with the active large reactor module 1's distribution cabinet using redundant flexible cables, it ensures continuous operation even in the event of external power loss or the need for on-site emergency power. In the event of source failure or superimposed disasters, the small reactor can serve as a "never-disconnected backup power source" to stably supply basic electrical energy to all active large reactor modules 1. This fundamentally solves the safety hazard of core meltdown caused by loss of cooling capacity in traditional active large reactor modules 1 during a plant-wide power outage. In addition, this invention also sets up a cooling water sharing module, using the small reactor's safety water pool as a reserve for the plant's emergency cooling water source. This provides valuable rescue time for active large reactor modules 1 when their cooling water is depleted. While ensuring safety, by controlling the ratio of active large reactor modules 1 to passive small reactors between 4:1 and 6:1, the total power generation of small reactors accounts for only about 1% to 2%. The overall cost per kilowatt-hour of the plant site is still dominated by the highly economical active large reactor modules 1. Thus, while achieving plant-wide safety comparable to the highest safety level reactor type, excellent economic efficiency is still maintained.

[0046] Operating Method and Working Principle: Under normal operating conditions, the multiple active large reactor modules 1 within the plant site operate powered by the off-site main power supply, distributing power through distribution cabinets and supplying power to the grid with high economic efficiency. The passive small reactor modules 3, located on floating platforms within the breakwater, continue to operate. Their self-generating equipment 31, such as steam turbine generator sets, generates electricity that is connected to the distribution cabinets of each active large reactor module 1 via flexible cables and reserved redundancy, but remains in hot standby mode. In the event of a loss of off-site power, such as a plant-wide blackout, the passive small nuclear reactors, employing passive safety technologies such as natural circulation, can continue to operate without external power. At this time, their distribution boxes immediately supply basic power to the distribution cabinets of the active large reactor modules 1 via connecting cables, activating their necessary active equipment to maintain core cooling and prevent meltdown. If an extreme tsunami occurs, causing the plant area to be flooded, the active large reactor modules on land... 1. Emergency power supply may fail, but at this time, the floating platform will rise with the water level, and the mooring cables will restrict its drift, ensuring the safe operation of the small nuclear reactor. At the same time, the redundant cables will stretch during the buoyancy process to ensure that the power channel is unobstructed, and the small nuclear reactor will continue to provide life-saving power to the flooded active reactor module 1. In addition, if the active reactor module 1 experiences a cooling water loss accident, emergency cooling water from the small nuclear reactor safety pool can be transported to the active reactor module 1 through the pipelines and valves of the cooling water sharing module, further extending its accident response time. Through the above-mentioned coupled design of "power sharing" and "water sharing", the high safety of the small nuclear reactor is endowed to the entire site; at the same time, since the number of small nuclear reactors is extremely small, about 1-2%, the overall power generation cost of the site is dominated by the efficient active reactor module 1, thus achieving the innovative goal of optimal safety and economy within the same site.

[0047] The above-disclosed embodiments are merely a few specific examples of the present invention. However, the embodiments of the present invention are not limited thereto, and any variations that can be conceived by those skilled in the art should fall within the protection scope of the present invention.

Claims

1. A nuclear power generation system comprising multiple powered large reactor modules, wherein electrical equipment of different voltages and currents of the powered large reactor modules are connected to external power transmission cables via voltage and current distribution cabinets, and the distribution cabinets of the powered large reactor modules are also connected via cables to an external power source that provides them with basic electrical energy, characterized in that, Multiple active large reactor modules are located on land at the nuclear power plant site, and also include: The floating platform module is installed inside the breakwater next to the nuclear power plant site; A passive small reactor module is installed on a floating platform module to cope with natural disasters such as earthquakes and floods. The passive small reactor module includes a small nuclear reactor, a power distribution box for power control, and a self-generating device for providing basic power. The power distribution box is connected to the power distribution cabinet of the active large reactor module through cables, so as to continue to provide basic power to the active large reactor module after the external power supply is disconnected. The limiting and mooring module is connected to both the floating platform and the land of the nuclear power plant site, and is used for towing and limiting the floating platform module.

2. The nuclear power generation system as described in claim 1, characterized in that, The small nuclear reactor is equipped with a safety water pool for cooling and heat dissipation, and the safety water pool is equipped with a cooling water sharing module.

3. A nuclear power generation system as described in claim 2, characterized in that, The cooling water sharing module includes pipelines and control valves connected to the safety water pool. The other end of the pipelines is connected to the cooling water pools in each active large reactor module through branch pipes. Each branch pipe is independently equipped with a valve. When the water in the active large reactor module that is used to cool the corresponding large nuclear reactor is exhausted, the safety water pool can provide an emergency cooling water source to its water pool.

4. A nuclear power generation system as described in claim 1, characterized in that, The ratio of the number of active large reactor modules to passive small reactor modules is 4:1 to 6:

1.

5. A nuclear power generation system as described in claim 1, characterized in that, The power output terminal of the self-generating equipment is equipped with an energy storage module for storing electricity, which is used to maintain a normal basic power supply when the power grid fluctuates or the power generation of the self-generating equipment is unstable.

6. A nuclear power generation system as described in claim 1, characterized in that, The floating platform module is connected to an energy-absorbing seismic module at the base.

7. A nuclear power generation system as described in claim 1, characterized in that, The cables connecting the distribution box and the distribution cabinet of the active large reactor module are all flexible, bendable cables.

8. A nuclear power generation system as described in claim 7, characterized in that, The cables electrically connecting the distribution box to the distribution cabinet of the active large reactor module have an extendable redundant length to meet the needs of the floating platform's movement.

9. A nuclear power generation system as described in claim 8, characterized in that, The redundant length of the cable connecting the distribution box to the distribution cabinet of the active large reactor module is 50m to 60m.

10. A nuclear power generation system as described in claim 1, characterized in that, The limiting mooring module includes multiple traction cables that are respectively connected to the floating platform and the nuclear power plant site land, used to reduce the swaying amplitude of the floating platform module after it floats.

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