Floating nuclear power generation system

Abstract

The present application discloses a floating nuclear power generation system that allows for a reduction in the capacity of a power cable. The floating nuclear power generation system comprises: a nuclear reactor; a turbine generator that is driven by steam generated using heat from the nuclear reactor; a floating structure moored at sea and having the nuclear reactor and the turbine generator mounted thereon; and a data center mounted on the floating structure. The turbine generator is connected to a power cable electrically connecting the floating structure and a power grid on land. The data center is operated using power output from the turbine generator.

Description

Floating nuclear power generation system

[0001] The present invention relates to a floating nuclear power generation system.

[0002] A floating power generation system installed on the sea needs to be connected to the land by a transmission line (see, for example, Patent Document 1).

[0003] Japanese Patent Application Laid-Open No. 49-71418

[0004] When a nuclear power generation system is floated on the sea, a power cable for electrically connecting the floating body and the power grid on land needs to be laid for power transmission. However, when the output of the nuclear power generation system floating on the sea is large, the power cable also needs to be increased in capacity, so the cost of laying and maintaining the power cable also becomes high.

[0005] Therefore, the present application discloses a floating nuclear power generation system capable of reducing the capacity of the power cable.

[0006] To solve the above problems, in the present invention, a data center is mounted on the floating body of the floating nuclear power generation system, and the data center is operated by the power output from the turbine generator.

[0007] Specifically, the present invention includes a nuclear reactor, a turbine generator driven by steam generated by the heat of the nuclear reactor, a floating body on which the nuclear reactor and the turbine generator are mounted and moored on the sea, and a data center mounted on the floating body. The turbine generator is connected to a power cable for electrically connecting the floating body and the power grid on land, and the data center operates with the power output from the turbine generator. It is a floating nuclear power generation system.

[0008] In the above floating nuclear power generation system, since the power output from the turbine generator is consumed by the data center, the power flowing through the power cable connecting the floating body and the land is reduced. Therefore, in the above floating nuclear power generation system, it is possible to reduce the capacity of the power cable connecting the floating body and the land.

[0009] Furthermore, the power consumption of the data center may be equivalent to that of the turbine generator. In this case, since the data center consumes an amount of power equivalent to that output from the turbine generator, there will be almost no power flowing through the power cable connecting the floating structure and the land. For this reason, with the floating nuclear power generation system described above, it is possible to reduce the capacity of the power cable connecting the floating structure and the land as much as possible.

[0010] Furthermore, the relationship between the power consumption of the data center and the power generation capacity of the turbine generator may be determined according to the capacity of the power cable. This makes it possible to appropriately determine the relationship between the power consumption of the data center and the power generation capacity of the turbine generator.

[0011] Furthermore, the reactor output may be adjusted according to the data center load. This makes it possible to adjust the amount of power flowing through the power cables connecting the floating structure and the land to an appropriate range.

[0012] With the floating nuclear power generation system described above, the capacity of the power cables can be reduced.

[0013] Figure 1 is a schematic diagram showing the equipment layout of a floating nuclear power generation system according to an embodiment. Figure 2 is a schematic diagram showing the system configuration of a floating nuclear power generation system according to an embodiment. Figure 3 is a diagram explaining the capacity of the power cables.

[0014] The embodiments of the present invention will be described below. The embodiments shown below are one aspect of the present invention and do not limit the technical scope of the present invention.

[0015] <Overview of Equipment Layout> Figure 1 is a schematic diagram showing the equipment layout of the floating nuclear power generation system 1 according to this embodiment. Figure 1(A) shows the layout of the various pieces of equipment installed in the floating nuclear power generation system 1 as viewed from above. Figure 1(B) shows the layout of the various pieces of equipment installed in the floating nuclear power generation system 1 as viewed from the side.

[0016] The floating nuclear power generation system 1 is a floating power generation system that can be floated on the sea. For this reason, the floating nuclear power generation system 1 is equipped with a floating body 2. As can be seen in Figure 1(A), the floating body 2 is a streamlined floating body. However, the floating body 2 is not a vessel intended for autonomous navigation on the sea. The floating body 2 floats on the sea while moored in order to transmit the electricity generated by the floating nuclear power generation system 1 to land. Furthermore, in order to suppress resistance to the current, the floating body 2 floats on the sea with only one end in the longitudinal direction moored, and the other end unmoored. For this reason, the floating body 2 floats on the sea like a windsock. That is, when the floating body 2 is subjected to a current, it floats on the sea with the moored part naturally facing upstream of the current.

[0017] Because the floating body 2 is a streamlined floating body, in this embodiment, for convenience, the moored portion of the floating body 2 in the longitudinal direction will be referred to as the "bow side," and the unmoored portion will be referred to as the "stern side." Therefore, in Figure 1, the left side of the paper is the "bow side," and the right side of the paper is the "stern side." Figure 1(B) shows the internal configuration of the floating nuclear power generation system 1 as viewed from the port side of the floating body 2.

[0018] In this embodiment, a streamlined floating body 2 is illustrated, but the floating body 2 may be a non-streamlined floating body. The floating body 2 used in the floating nuclear power generation system 1 may be, for example, a cylindrical floating body with a circular top view, a rectangular floating body with a square top view, or a floating body of various other shapes.

[0019] As shown in Figure 1, the floating nuclear power generation system 1 comprises a reactor 3 located near the center of the floating body 2 and a turbine generator 4 located towards the bow of the ship relative to the reactor 3. The reactor 3 generates steam by boiling water with the heat generated by nuclear fission. The turbine generator 4 generates electricity by rotating a generator with a steam-driven turbine. In this embodiment, a floating nuclear power generation system 1 of a boiling water reactor (BWR) that drives the turbine generator 4 with steam from the reactor 3 is illustrated, but the floating nuclear power generation system 1 may be, for example, a pressurized water reactor (PWR), or may use various other types of systems.

[0020] The floating nuclear power generation system 1 is equipped with various equipment in addition to the floating body 2, reactor 3, and turbine generator 4 described above. For example, the floating nuclear power generation system 1 has reactor equipment areas 5 and 7, a pit 6, and a fuel pool 8 around the reactor 3. The floating nuclear power generation system 1 also has a desalination plant 9, an IC / PCCS pool 10, various equipment areas 12, a living area 13, and a waste treatment room 24 located aft of the reactor 3. The floating nuclear power generation system 1 also has a condensate storage tank 14 located between the reactor 3 and the turbine generator 4. The floating nuclear power generation system 1 also has a laydown area 18 and an ancillary equipment area 19 located near the bow of the floating body 2. The ancillary equipment area 19 is equipped with a main transformer 20 and an auxiliary boiler 21. The floating nuclear power generation system 1 also has a diesel fuel tank 23 on the deck near the bow of the floating body 2. Furthermore, the floating nuclear power generation system 1 is equipped with a bow ballast tank 25, a bottom ballast tank 26, a stern ballast tank 27, and side ballast tanks 28 for controlling the attitude of the floating body 2.

[0021] Reactor equipment areas 5 and 7 house various reactor equipment installed outside the containment vessel of reactor 3. Equipment located in reactor equipment areas 5 and 7 includes, for example, pumps and valves for various reactor cooling systems such as the emergency core cooling system and residual heat removal system, pumps and valves for the pool water cooling system that cools the fuel pool, control compressed air equipment, ventilation and air conditioning equipment, emergency diesel generators that serve as emergency power sources, DC power supply equipment using batteries, and various other equipment.

[0022] Pit 6 is a pit for temporarily storing various items during periodic inspections and fuel changes. Examples of items to be stored in Pit 6 include steam separators and steam dryers that are located above the nuclear fuel inside Reactor 3.

[0023] The fuel pool 8 is a pool for storing unused or spent nuclear fuel. The nuclear fuel of the reactor 3 is in the form of fuel assemblies. Therefore, the fuel pool 8 is equipped with racks to hold the fuel assemblies at appropriate intervals from each other. In addition, a fuel exchange machine is provided at the top of the fuel pool 8 for transferring fuel assemblies between the reactor 3 and the fuel pool 8.

[0024] The desalination plant 9 is a device that desalinates seawater. Since the floating nuclear power generation system 1 is used while floating on the sea, it is not possible to obtain fresh water with almost no salt content from rivers, as is the case with facilities located on land. For this reason, the floating nuclear power generation system 1 is equipped with a desalination plant 9 to desalinate seawater by removing salt in order to secure reactor cooling water and various other types of water. Various methods such as reverse osmosis and evaporation can be applied as desalination methods to the desalination plant 9.

[0025] The IC / PCCS pool 10 houses an IC heat exchanger and a PCCS heat exchanger. The IC heat exchanger is an emergency condenser (IC) that cools the reactor 3 in the event of a complete loss of AC power or other incident that isolates the containment vessel. The PCCS heat exchanger is a passive containment cooling system (PCCS) that cools the steam released into the containment vessel during severe accidents.

[0026] The various equipment areas 12 include a central control room for operating the floating nuclear power generation system 1, an access control room for managing entry and exit to the radiation controlled area, and various other facilities. Note that the aforementioned emergency diesel generators and DC power supply equipment may be located in the various equipment areas 12 rather than in the reactor equipment areas 5 and 7.

[0027] The residential area 13 is equipped with living facilities for operators and other personnel staying at the floating nuclear power generation system 1. These living facilities include, for example, private rooms with beds, a dining room with cooking equipment, bathing facilities, recreational facilities, and various other amenities.

[0028] The waste treatment room 24 is equipped with various facilities for processing radioactive waste. Examples of radioactive waste processed in the waste treatment room 24 include liquid waste such as wastewater generated in radiation controlled areas, and miscellaneous solid waste such as waste materials generated in connection with various operations. These wastes are reduced in volume in the waste treatment room 24 by evaporation, concentration, compression, or incineration, and then stored in the floating body 2 before being transported out of the floating body 2.

[0029] The condensate storage tank 14 is a tank that stores water that can be supplied to the reactor 3. The condensate storage tank 14 is connected to the condenser of the turbine generator 4 and the emergency core cooling system, and is used for supplying water to the condenser during normal operation and for injecting water into the reactor 3 in emergencies.

[0030] The laydown area 18 is a workspace for disassembling and inspecting various large pieces of equipment, such as the turbine generator 4. The laydown area 18 is on the same floor as the operating floor of the turbine generator 4, and large pieces of equipment can be easily moved using the crane equipment installed above the operating floor.

[0031] The ancillary equipment area 19 houses various ancillary equipment, such as the main transformer 20 and the auxiliary boiler 21. The main transformer 20 is a transformer that boosts the electricity generated by the turbine generator 4 to the voltage of the power grid. The auxiliary boiler 21 is a boiler that generates steam using the heat produced by burning light oil.

[0032] The floating nuclear power generation system 1 is moored to the sea by an anchor chain 22 installed on the bow side of the floating body 2. As mentioned above, when the floating nuclear power generation system 1 is subjected to a current, it floats on the sea with the moored portion naturally facing upstream of the current. For this reason, the submarine cable for connecting the floating nuclear power generation system 1 to the onshore power grid is suspended from near the bow of the floating body 2 toward the seabed, similar to the anchor chain 22. For this reason, it is reasonable to position the main transformer 20, which boosts the electricity generated by the turbine generator 4 to the voltage of the power grid, near the bow of the floating body 2, close to the submarine cable, as shown in Figure 1.

[0033] Furthermore, the auxiliary boiler 21 is used during the startup of the floating nuclear power generation system 1 to provide steam for the turbine generator 4's gland and to heat the steam equipment around the turbine. For this reason, it is reasonable to position the auxiliary boiler 21 near the turbine generator 4.

[0034] Therefore, the floating nuclear power generation system 1 adopts a configuration in which the main transformer 20 and auxiliary boiler 21 are located in an ancillary equipment area 19 provided on the bow side of the floating body 2. In addition, the floating nuclear power generation system 1 adopts a configuration in which a diesel fuel tank 23 for storing diesel fuel supplied to the auxiliary boiler 21 is located above the ancillary equipment area 19. Not only the main transformer 20 and auxiliary boiler 21, but also switching equipment such as a disconnector (LS: Line Switch) for opening and closing the electrical connection between the submarine cable and the main transformer 20 may be installed in the ancillary equipment area 19.

[0035] The bow ballast tank 25, bottom ballast tank 26, stern ballast tank 27, and side ballast tanks 28 are tanks for receiving ballast water to control the attitude of the floating body 2. The ballast water in the bow ballast tank 25, bottom ballast tank 26, and stern ballast tank 27 can also be used as seawater to cool the reactor 3 in the event of an emergency of the floating nuclear power generation system 1. The water in the bow ballast tank 25, bottom ballast tank 26, and stern ballast tank 27 can be naturally injected using the water pressure of the seawater by opening an intake port provided on the bottom of the floating body 2, for example. Pumps may also be used in conjunction with the water injection as needed. Drainage from the bow ballast tank 25, bottom ballast tank 26, and stern ballast tank 27 can be performed using pumps or ejectors.

[0036] The above outline describes the equipment layout of the floating nuclear power generation system 1 according to this embodiment. However, the above equipment layout is merely an example, and other equipment layouts may be adopted. Next, the outline of the system configuration of the floating nuclear power generation system 1 will be described.

[0037] <Overview of System Configuration> Figure 2 is a schematic diagram showing the system configuration of the floating nuclear power generation system 1 according to the embodiment. The floating nuclear power generation system 1 mainly consists of a reactor system R and a turbine system T. The aforementioned reactor 3 is the main component of the reactor system R. The aforementioned turbine generator 4 is the main component of the turbine system T.

[0038] The reactor system R, which includes reactor 3, is equipped with various facilities such as a containment vessel 3A, nuclear fuel 3B, control rods 3C, recirculation pump 3D, and pressure vessel 3E. The turbine system T, which includes turbine generator 4, is equipped with various facilities such as a condenser 4C, circulating water piping 4D, circulating water pump 4E, and feedwater pump 4F, in addition to the turbine 4A and generator 4B that make up the turbine generator 4.

[0039] The containment vessel 3A is a vessel that houses the pressure vessel 3E containing the nuclear fuel 3B, etc., and plays the role of containing radioactive materials released from the pressure vessel 3E in the event of a meltdown accident of the reactor 3. The containment vessel 3A may be made of concrete or of the steel materials that make up the floating body 2. The containment vessel 3A encloses the pressure vessel 3E containing the reactor 3 in its center, and has an upper drywell 3M above the pressure vessel 3E and a lower drywell 3N below the pressure vessel 3E. The containment vessel 3A also has a suppression pool 3H around the lower drywell 3N.

[0040] The pressure vessel 3E is a container that encloses the nuclear fuel 3B and other materials, and plays the role of containing water and steam for cooling the reactor 3. In the center of the pressure vessel 3E, hundreds of nuclear fuel 3B are arranged in the form of fuel assemblies, forming the main body of the reactor 3. Control rods 3C, which can move up and down by a drive mechanism provided at the bottom of the pressure vessel 3E, are inserted into the gaps between the fuel assemblies in the main body of the reactor 3. When the control rods 3C are withdrawn from the reactor 3 and the reactor 3 reaches a critical state, the reactor 3 continuously generates heat. When the control rods 3C are inserted into the reactor 3 and the reactor 3 reaches a subcritical state, the heat generated by the reactor 3 gradually decreases.

[0041] A recirculation pump 3D is provided in the pressure vessel 3E. The recirculation pump 3D is responsible for heat removal and control of the reactor output of the reactor 3 by forcibly circulating water, which is the reactor coolant, in the liquid phase portion within the pressure vessel 3E. In this embodiment of the floating nuclear power generation system 1, an Advanced Boiling Water Reactor (ABWR) is assumed, and therefore in Figure 2, the recirculation pump 3D is shown to be provided in the pressure vessel 3E. However, the floating nuclear power generation system 1 is not limited to this configuration. For example, the floating nuclear power generation system 1 may have a recirculation system in which the recirculation pump and circulation piping are arranged outside the pressure vessel 3E.

[0042] A main steam pipe 3L is connected to the pressure vessel 3E to send steam generated in the pressure vessel 3E to the turbine generator 4 of the turbine system T. Since the main steam pipe 3L is a pipe that connects the inside and outside of the containment vessel 3A, main steam isolation valves 3J and 3K are provided near the penetration point of the containment vessel 3A to allow the containment vessel 3A to be isolated. A relief safety valve 3F is provided in the middle of the main steam pipe 3L to prevent the internal pressure of the pressure vessel 3E from becoming excessive when the main steam isolation valves 3J and 3K are closed. The end of the exhaust pipe 3G, located downstream of the relief safety valve 3F, is located in the suppression pool 3H.

[0043] The turbine 4A and the generator 4B that constitute the turbine generator 4 are connected by the same rotating shaft. The turbine 4A has a structure in which an impeller is housed in a casing. And, a condenser (recondenser) 4C for condensing the steam that has passed through the turbine 4A is provided below the turbine 4A. Inside the condenser 4C, a large number of thin tubes are provided that form a part of the path of a circulating water pipe 4D that connects a water intake provided below the waterline of the outer surface of the floating body 2 to a water discharge port, and the steam is condensed by the cold heat of seawater pumped by a circulating water pump 4E provided on the path of the circulating water pipe 4D. For this reason, due to the pressure difference between the steam supplied from the nuclear reactor 3 through the main steam pipe 3L and the inside of the condenser 4C, power for rotating the generator 4B is applied to the impeller. Thereby, the generator 4B rotates and generates electricity. Further, the condensed water in the condenser 4C is fed again into the pressure vessel 3E via a feed water pipe 4G by a feed water pump 4F.

[0044] Note that in FIG. 2, only the outlines of the nuclear reactor system R and the turbine system T are shown, and actually, a wide variety of devices are provided. For example, important devices such as a steam control valve and a turbine bypass valve are provided near the turbine 4A of the main steam pipe 3L. The turbine bypass valve may be capable of 100% bypassing all of the main steam at the rated output directly to the condenser 4C without passing through the turbine 4A, or may have a bypass capacity less than that. Also, important devices such as a feed water flow control valve, a condensate desalination device, and a feed water heater are provided in the feed water pipe 4G. Further, pipes of an emergency core cooling system and the like are provided inside and outside the containment vessel 3A. Also, the turbine 4A is a combination of a high-pressure turbine and a plurality of low-pressure turbines.

[0045] Also, in FIG. 2, only one system of each device is shown, but each device of the floating nuclear power generation system 1 is multiplexed. For example, a plurality of circulating water pumps 4E and feed water pumps 4F are provided.

[0046] In the reactor system R, the position of the control rod 3C is adjusted so that the reactor 3 maintains a predetermined reactor output. Also, in the turbine system T, the opening degree of the steam control valve is adjusted so that the turbine generator 4 maintains a predetermined rotational speed, and the feed water flow rate of the feed water pump 4F is adjusted so that the reactor 3 maintains a predetermined water level. The floating nuclear power generation system 1 is configured in this way to transmit the thermal energy generated by the nuclear reaction of the reactor 3 to the power grid as electrical energy through the generator 4B synchronized with the system frequency.

[0047] The above is the outline of the system configuration of the floating nuclear power generation system 1 according to the present embodiment. Next, the data center provided in the floating nuclear power generation system 1 will be described.

[0048] As shown in FIG. 1, the floating body 2 of the floating nuclear power generation system 1 is provided with a data center DC. In FIG. 1, the data center DC is arranged below the turbine generator 4 in the floating body 2. However, the data center DC is not limited to being arranged in such a location. The data center DC may be arranged at an appropriate location within the floating body 2, for example, near various equipment areas 12, near the residential area 13, near the waste treatment room 24, etc.

[0049] The data center DC is a facility in which server racks accommodating a large number of servers responsible for various information processing are arranged. Each server is equipped with a CPU (Central Processing Unit), memory, storage, and an input / output interface, and realizes various services that can be provided through various communication means including the Internet.

[0050] The data center DC may be a liquid immersion method in which the servers are cooled while being submerged in an insulating liquid, a liquid cooling method in which refrigerant pipes are connected to heat generating components such as CPUs for cooling, an air cooling method in which heat generating components such as CPUs are cooled by air, or a combination of these cooling methods.

[0051] Immersion servers are heavier than liquid-cooled or air-cooled servers. Therefore, when installing immersion servers in buildings on land, the ground and building flooring must be made particularly strong to withstand acceleration during earthquakes. However, if the data center DC is mounted on a floating structure 2, it is not necessary to withstand acceleration during earthquakes as is the case when installing it in a building on land. For this reason, it is possible to reduce the strength of the structural materials supporting the server compared to when installing it in a building on land.

[0052] The data center DC located within the floating body 2 consumes a large amount of power. The power consumption of the data center DC depends on the processing capacity required for the data center DC and the space available on the floating body 2 for mounting the data center DC, but in this embodiment, it is desirable that it be about the same size as the power generation capacity of the turbine generator 4. If the power consumption of the data center DC is equivalent to the power generation capacity of the turbine generator 4, it becomes possible to significantly reduce the capacity of the submarine cable used for power transmission connecting the floating body 2 to the land.

[0053] Figure 3 illustrates the capacity of the submarine cable for power transmission. For example, if the power generation capacity of the turbine generator 4 is 1100 MWe, and as shown in Figure 3(B), if the floating nuclear power generation system 1 does not have a data center DC, or if the power consumption of the data center DC is extremely small, then the submarine cable for power transmission connecting the floating body 2 to the land must have a capacity capable of transmitting at least 1100 MWe of power. In the case of the floating nuclear power generation system 1, the floating body 2 and the land are connected by a submarine cable, so the cost required to lay a submarine cable with a capacity capable of transmitting 1100 MWe of power is considerable.

[0054] In this regard, if the power consumption of the data center DC is comparable to the power generation capacity of the turbine generator 4 (for example, around 800 MWe), then, as shown in Figure 3(A), 800 MWe of the 1100 MWe generated by the floating nuclear power generation system 1 will be consumed within the floating body 2. Therefore, the submarine cable for power transmission connecting the floating body 2 to the land only needs to have a capacity capable of transmitting at least 300 MWe of power. In other words, if a data center DC with a power generation capacity comparable to that of the turbine generator 4 is provided in the floating nuclear power generation system 1, the submarine cable for power transmission connecting the floating body 2 to the land can be reduced to a fraction of the capacity required if such a data center DC were not provided in the floating nuclear power generation system 1.

[0055] In the above, the power generation capacity of the turbine generator 4 was assumed to be 1100 MWe, and the power consumption of the data center DC was assumed to be 800 MWe. However, the relationship between the power generation capacity of the turbine generator 4 and the power consumption of the data center DC is not limited to these figures. For example, the power consumption of the data center DC may exceed the power generation capacity of the turbine generator 4. If the power consumption of the data center DC exceeds the power generation capacity of the turbine generator 4, the submarine cable connecting the floating body 2 to the land will serve the purpose of enabling the floating body 2 to receive power from the land. The magnitude of the difference between the power generation capacity of the turbine generator 4 and the power consumption of the data center DC may be determined according to the capacity of the submarine cable connecting the floating body 2 to the land.

[0056] Data centers for AI (Artificial Intelligence), which have become rapidly widespread in recent years (sometimes called "hyperscale data centers"), consume far more power and generate far more heat than conventional data centers that implement various applications and web pages, because they process large amounts of data in parallel on a large scale. Therefore, if the data center DC installed in the floating nuclear power generation system 1 is such an AI data center, the transmission costs, such as the laying of large-capacity submarine cables required to transmit the electricity generated by the floating nuclear power generation system 1 from the floating body 2 to land, can be significantly reduced. In addition, electrical transmission losses, which increase when transmitting power to remote locations, can also be reduced. Furthermore, since the floating body 2 floats on the surface of the sea, it is easy to utilize the cold energy of the seawater surrounding the floating body 2 to cool the data center DC.

[0057] If a data center (DC) is installed on the floating nuclear power generation system 1, a communication line is required to connect the data center DC to the internet or land-based communication network. However, even if a data center DC is not installed on the floating nuclear power generation system 1, a communication line is still required within the floating body 2 to use the internet, etc. Such a communication line can be constructed relatively inexpensively by procuring submarine fiber optic cables that are already laid all over the world, or by using satellite communication lines. Even if the floating body 2 and land are connected by a submarine fiber optic cable for the data center DC, the cost is far cheaper than the cost of laying and maintaining a submarine cable with a capacity to transmit 1100 MWe of power. Therefore, it can be said that installing a data center DC on the floating nuclear power generation system 1 is extremely rational. It is preferable that the fiber optic cable be suspended from near the bow of the floating body 2, where the anchor chain 22 is installed, down to the seabed, similar to submarine cables used for power transmission.

[0058] Furthermore, since movement at sea is more difficult for humans than on land, a data center (DC) mounted on a floating structure 2 on the sea can reduce the risk of intruders compared to a data center installed on land. Also, since both the nuclear reactor 3 and the data center (DC) are facilities that need to be protected from intruders, mounting both on the same floating structure 2 allows for a more rational deployment of security personnel and installation of security equipment.

[0059] While the floating nuclear power generation system 1 can stably supply power through the output of the reactor 3, the power consumption of the data center DC fluctuates significantly depending on the computational processing demands on the data center DC. If the power consumption of the data center DC fluctuates frequently, the power flowing through the submarine transmission cable connecting the floating structure 2 and the land will fluctuate significantly in order to adjust for any surplus or deficit in the power generated by the floating nuclear power generation system 1. If the capacity of the submarine transmission cable is small, the power flowing through the submarine cable may exceed its capacity. Therefore, when a data center DC is provided in the floating nuclear power generation system 1, it is desirable to adjust the computational processing load schedule so that a constant level of computational processing is always performed in the data center DC, in order to suppress frequent fluctuations in the power consumption of the data center DC, and to systematically adjust the output of the reactor 3 in accordance with that schedule. Such adjustments may be performed automatically based on a pre-created algorithm, or they may be performed manually by the administrator of the floating nuclear power generation system 1.

[0060] Furthermore, although the above embodiment illustrates a configuration in which the floating body 2 and the land are connected by an underwater power cable, if the floating body 2 is moored near the land, it may be connected by an overhead power transmission line.

[0061] R: Reactor system; T: Turbine system; F: Floating platform; C: Core; 1: Floating nuclear power generation system; 2: Floating platform; 3: Reactor; 4: Turbine generator; 5: Reactor equipment area; 6: Pit; 7: Reactor equipment area; 8: Fuel pool; 9: Desalination plant; 10: IC / PCCS pool; 12: Various equipment areas; 13: Living area; 14: Condensate storage tank; 18: Laydown area; 19: Ancillary equipment area; 20: Main transformer; 21: Auxiliary boiler; 22: Anchor chain; 23: Diesel fuel tank; 24: Waste disposal room; 25: Bow ballast Ballast Tanks: 26...Bottom Ballast Tanks: 27...Stern Ballast Tanks: 28...Side Ballast Tanks: 3A...Containment Vessel: 3B...Nuclear Fuel: 3C...Control Rods: 3D...Recirculation Pumps: 3E...Pressure Vessel: 3F...Relief Safety Valves: 3G...Exhaust Pipes: 3H...Suppression Pool: 3J...Main Steam Isolation Valves: 3K...Main Steam Isolation Valves: 3L...Main Steam Pipes: 3M...Upper Drywell: 3N...Lower Drywell: 4A...Turbine: 4B...Generator: 4C...Condenser: 4D...Circulating Water Piping: 4E...Circulating Water Pumps: 4F...Feedwater Pumps: 4G...Feedwater Piping: DC...Data Center:

Claims

1. A floating nuclear power generation system comprising: a nuclear reactor; a turbine generator driven by steam generated by the heat of the nuclear reactor; a floating body moored at sea on which the nuclear reactor and the turbine generator are mounted; and a data center mounted on the floating body, wherein the turbine generator is connected to a power cable that electrically connects the floating body to a land-based power grid; the data center operates on the power output from the turbine generator; and the magnitude of the difference between the power generation capacity of the turbine generator and the power consumption of the data center is determined according to the capacity of the power cable.

2. The floating nuclear power generation system according to claim 1, wherein the power consumption of the data center is greater than the value obtained by subtracting the capacity of the power cable from the power generation capacity of the turbine generator.

3. The floating nuclear power generation system according to claim 1 or 2, wherein the output of the reactor is adjusted according to the load of the data center.

4. The floating nuclear power generation system according to claim 3, wherein the output of the reactor is adjusted so that the power flowing through the power cable does not exceed the capacity of the power cable.

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