Floating nuclear power system

Abstract

The present application discloses a floating nuclear power generation system with a more robust emergency power supply system. [Solution] A floating nuclear power generation system comprising: a reactor; a turbine generator driven by steam generated by the heat of the reactor; a float on which the reactor and turbine generator are arranged and which is moored at sea; and an internal power supply system within the float which has at least an emergency system capable of supplying power to designated equipment for cooling the reactor in an emergency, and a normal system capable of supplying power to equipment not connected to the emergency system, and a normal power generation equipment which generates power using natural energy is connected to the emergency system.

Description

[Technical field]

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

[0002] Nuclear power generation systems are equipped with emergency power sources to maintain the cooling function of the nuclear reactor even when external power sources are lost. For example, Patent Document 1 proposes using a wind power generation device as an emergency power source for a nuclear power plant. [Prior art documents] [Patent documents]

[0003] [Patent Document 1] JP 2004-44508 A Summary of the Invention [Problem to be solved by the invention]

[0004] When a nuclear power generation system is floated on the sea, an undersea cable is laid to electrically connect the float to the power grid on land for power transmission. From the nuclear power generation system's perspective, such an undersea cable connected to the power grid on land is considered an external power source. Therefore, when preparing an emergency power source for such a floating nuclear power generation system, it is natural to install the emergency power source on the float.

[0005] In addition, the power supply system of a nuclear power generation system generally has an emergency system that supplies power to important equipment related to safety, and a normal system that supplies power to normal equipment that does not immediately impair safety even if it becomes inoperable, and in the event of a loss of external power, the emergency power supply basically supplies power only to the emergency system. Therefore, if a nuclear power generation system is made into a floating type, the power supply outside the float is positioned as a normal power supply, and it is difficult to give priority to supplying power from the power supply outside the float to the emergency system rather than the normal system.

[0006] Therefore, the present application discloses a floating nuclear power generation system with a more robust emergency power supply system. [Means for solving the problem]

[0007] In order to solve the above problems, in the present invention, normal power generation equipment that generates electricity using natural energy is connected to an emergency system that can supply power to predetermined equipment for cooling a nuclear reactor in an emergency.

[0008] In detail, the present invention is a floating nuclear power generation system comprising a reactor, a turbine generator driven by steam generated by heat from the reactor, a float on which the reactor and the turbine generator are disposed and which is moored at sea, and an internal power supply system within the float having at least an emergency system capable of supplying power to designated equipment for cooling the reactor in an emergency, and a normal system capable of supplying power to equipment that is not connected to the emergency system, and normal power generation equipment that generates power using natural energy is connected to the emergency system.

[0009] The above-mentioned normal power generation equipment generates electricity from natural energy, so it can generate electricity both in normal times and when external power sources are lost. Therefore, if such normal power generation equipment is connected to an emergency power grid, it is possible to cover part or all of the self-consumption of the floating nuclear power generation system with the power of the normal power generation equipment in normal times, and when external power sources are lost, it is possible to supply the power of the normal power generation equipment to the emergency power grid. Therefore, with such a floating nuclear power generation system, It can be said that the emergency power supply system is more robust.

[0010] In addition, a regular power generating facility installed on the float or in the vicinity of the float may be connected to the emergency system. If the regular power generating facility is installed on the float or in the vicinity of the float, power can be more reliably supplied from the regular power generating facility to the emergency system in the event of loss of external power supply, compared to a case in which the regular power generating facility is installed in a location remote from the float.

[0011] The normal power generation facility may be an offshore wind power generation facility located around the float, and the offshore wind power generation facility may be connected to the emergency system by an electric cable running through the seabed. If the emergency system and the offshore wind power generation facility are connected by an electric cable running through the seabed, the electric cable will not interfere with the float.

[0012] The system may further include an emergency generator capable of supplying power to the emergency system in an emergency. During normal times, the emergency system can supply power from the regular power generating equipment to the regular system via the emergency system. During an emergency, the emergency system may be cut off from the regular system so that the emergency generator and the regular power generating equipment can supply power only to designated equipment. In this way, when an external power source is lost, the regular power generating equipment and the emergency generator work together to supply power to the emergency system. Therefore, such a floating nuclear power generation system can be said to have a stronger emergency power supply system. Effect of the Invention

[0013] The above floating nuclear power generation system has a stronger emergency power supply system. [Brief description of the drawings]

[0014] [Figure 1] FIG. 1 is a schematic diagram showing an arrangement of equipment in a floating nuclear power generation system according to an embodiment. [Diagram 2] FIG. 2 is a schematic diagram showing a system configuration of a floating nuclear power generation system according to an embodiment. [Diagram 3] FIG. 3 is a single-line diagram showing an outline of the power supply system inside the float. [Figure 4] FIG. 4 is a diagram showing a first example of a method for installing a wind power generation facility. [Diagram 5] FIG. 5 is a diagram showing a second example of a method for installing a wind power generation facility. [Figure 6] FIG. 6 is a diagram showing a third example of a method for installing a wind power generation facility. DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS

[0015] Hereinafter, an embodiment of the present invention will be described. The embodiment described below is one aspect of the present invention, and is not intended to limit the technical scope of the present invention.

[0016] <Equipment layout overview> Fig. 1 is a schematic diagram showing the arrangement of equipment in a floating nuclear power generation system 1 according to an embodiment. Fig. 1(A) shows the layout of various equipment provided in the floating nuclear power generation system 1 as viewed from above. Fig. 1(B) shows the layout of various equipment provided in the floating nuclear power generation system 1 as viewed from the side.

[0017] The floating nuclear power generation system 1 is a floating power generation system that can be floated on the sea. For this purpose, the floating nuclear power generation system 1 includes a float 2. As can be seen from FIG. 1(A), the float 2 is a streamlined float. However, the float 2 is not a ship intended to navigate autonomously on the sea. The float 2 floats on the sea in a moored state in order to transmit the electricity generated by the floating nuclear power generation system 1 to land. The float 2 floats on the sea in a state where only one end in the longitudinal direction is moored and the other end is not moored in order to suppress resistance to the tidal current. For this reason, the float 2 floats on the sea like a windsock. That is, when the float 2 receives a tidal current, it floats on the sea in a position where the moored part naturally faces the upstream side of the tidal current.

[0018] Since the float 2 has such a streamlined shape, in this embodiment, for convenience, the moored portion of the float 2 in the longitudinal direction is referred to as the "bow side" and the unmoored portion is referred to as the "stern side". Therefore, in Fig. 1, the left side of the page is the "bow side" and the right side of the page is the "stern side". Fig. 1(B) shows the internal configuration of the floating nuclear power generation system 1 as viewed from the port side of the float 2.

[0019] In this embodiment, a streamlined float 2 is exemplified, but the float 2 may be a non-streamlined float. The float 2 used in the floating nuclear power generation system 1 may be, for example, a cylindrical float that is circular when viewed from above, a rectangular parallelepiped float that is square when viewed from above, or floats of various other shapes.

[0020] As shown in FIG. 1, the floating nuclear power generation system 1 includes a nuclear reactor 3 disposed near the center of a float 2, and a turbine generator 4 disposed closer to the bow than the nuclear reactor 3. The nuclear reactor 3 generates steam by boiling water with heat generated by nuclear fission. The turbine generator 4 generates electricity by rotating a generator with a steam-driven turbine. Note that in this embodiment, a floating nuclear power generation system 1 using a boiling water reactor (BWR) that drives the turbine generator 4 with steam from the nuclear reactor 3 is illustrated as an example, but the floating nuclear power generation system 1 may be any other type of floating nuclear power generation system. The power system 1 is, for example, a pressurized water reactor (PWR). Alternatively, various other methods may be used.

[0021] The floating nuclear power generation system 1 includes various equipment and the like in addition to the float 2, the reactor 3, and the turbine generator 4 described above. The floating nuclear power generation system 1 includes, for example, 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 includes a desalination device 9, an IC / PCCS pool 10, various equipment areas 12, a living area 13, and a waste treatment room 24, which are arranged aft of the reactor 3. The floating nuclear power generation system 1 also includes a condensate storage tank 14 arranged between the reactor 3 and the turbine generator 4. The floating nuclear power generation system 1 also includes a laydown area 18 and an auxiliary equipment area 19, which are arranged near the bow of the float 2. A main transformer 20 and an auxiliary boiler 21 are provided in the auxiliary equipment area 19. The floating nuclear power generation system 1 also includes a light oil tank 23 on the deck near the bow of the float 2. The floating nuclear power generation system 1 also includes a bow ballast tank 25, a bottom ballast tank 26, a stern ballast tank 27, and a side ballast tank 28 for controlling the attitude of the float 2.

[0022] In the reactor equipment areas 5 and 7, various reactor equipment to be installed outside the containment vessel of the reactor 3 is disposed. The devices disposed in the reactor equipment areas 5 and 7 include, for example, pumps and valves of various reactor cooling equipment such as an emergency core cooling system and a residual heat removal system, pumps and valves of a pool water cooling system that cools the fuel pool, compressed air equipment for control, ventilation and air conditioning equipment, an emergency diesel generator that serves as an emergency power source, DC power supply equipment using storage batteries, and various other equipment.

[0023] The pit 6 is a pit for temporarily storing various items during periodic inspections and fuel replacement. Examples of items to be stored in the pit 6 include a steam separator and a steam dryer that are placed above the nuclear fuel inside the reactor 3.

[0024] The fuel pool 8 is a pool for storing unused or spent nuclear fuel. The nuclear fuel in the reactor 3 is in the form of fuel assemblies. For this reason, the fuel pool 8 is provided with racks for storing the fuel assemblies at appropriate intervals. In addition, a fuel exchange machine for transferring the fuel assemblies between the reactor 3 and the fuel pool 8 is provided at the top of the fuel pool 8.

[0025] The desalination device 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 that contains almost no salt from a river, as is the case with facilities on land. For this reason, the floating nuclear power generation system 1 is provided with a desalination device 9 that removes salt from seawater to desalinate it, in order to secure reactor cooling water and various other types of water. As a desalinization method for the desalination device 9, various methods such as reverse osmosis membrane method and evaporation method can be applied.

[0026] An IC heat exchanger and a PCCS heat exchanger are arranged in the IC / PCCS pool 10. The IC heat exchanger is an isolation condenser (IC) equipment, and is used for all AC power sources. In the event of a loss of power or other accident that causes the containment vessel to be isolated, the PCCS cools the reactor 3. The PCCS heat exchanger is a piece of equipment in the Passive Containment Cooling System (PCCS), and cools the steam that is released into the containment vessel in the event of a severe accident.

[0027] In the various equipment area 12, a central control room for operating the floating nuclear power generation system 1, an entrance / exit control room for controlling entrance / exit to the radiation controlled area, and various other equipment are provided. The emergency diesel generator and DC power supply equipment described above may be provided in the various equipment area 12 instead of the reactor equipment areas 5 and 7.

[0028] The accommodation area 13 is provided with accommodation facilities for the operators and others staying on the floating nuclear power system 1. Examples of the accommodation facilities include individual rooms with berths, a dining room with cooking equipment, bathing facilities, recreational facilities, and various other facilities.

[0029] Various facilities for treating radioactive waste are installed in the waste treatment room 24. Examples of radioactive waste treated 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 various operations. These wastes are reduced in volume in the waste treatment room 24 by evaporation and concentration, compression, incineration, etc., and stored within the float 2, and then transported from the float 2.

[0030] 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 an emergency core cooling system, and is used to supply water to the condenser during normal operation and to inject water into the reactor 3 in an emergency.

[0031] The laydown area 18 is a work space for disassembling and inspecting various large 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 equipment can be easily transported using crane equipment installed above the operating floor.

[0032] Various types of auxiliary equipment, such as a main transformer 20 and an auxiliary boiler 21, are arranged in the auxiliary equipment area 19. The main transformer 20 is a transformer for stepping up 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 heat generated by burning diesel fuel.

[0033] The floating nuclear power generation system 1 is moored on the sea by an anchor chain 22 attached to the bow side of the float 2. As described above, when the floating nuclear power generation system 1 receives a tidal current, it floats on the sea with the moored part naturally facing the upstream side of the tidal 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 float 2 toward the seabed, similar to the anchor chain 22. For this reason, it is reasonable to place the main transformer 20 for stepping up the electricity generated by the turbine generator 4 to the voltage of the power grid near the bow of the float 2 close to the submarine cable, as shown in Figure 1. do.

[0034] In addition, the auxiliary boiler 21 is used to provide steam for the ground of the turbine generator 4 and to heat the steam equipment around the turbine during startup of the floating nuclear power generation system 1. For this reason, it is reasonable to place the auxiliary boiler 21 near the turbine generator 4 as well.

[0035] For this reason, the floating nuclear power generation system 1 adopts a configuration in which the main transformer 20 and the auxiliary boiler 21 are arranged in an auxiliary equipment area 19 provided on the bow side of the float 2. Also, in the floating nuclear power generation system 1, a light oil tank 23 for storing light oil to be supplied to the auxiliary boiler 21 is arranged above the auxiliary equipment area 19. Note that in the auxiliary equipment area 19, not only the main transformer 20 and the auxiliary boiler 21 but also switching equipment such as a line switch (LS) for opening and closing the electrical connection between the submarine cable and the main transformer 20 can be installed. may be installed.

[0036] The bow ballast tank 25, the bottom ballast tank 26, the stern ballast tank 27, and the side ballast tank 28 are tanks for receiving ballast water for controlling the attitude of the float 2. The ballast water in the bow ballast tank 25, the bottom ballast tank 26, and the stern ballast tank 27 can also be used as seawater for cooling the reactor 3 in an emergency of the floating nuclear power generation system 1. Water can be naturally injected into the bow ballast tank 25, the bottom ballast tank 26, and the stern ballast tank 27 by the water pressure of seawater, for example, by opening a water intake provided on the bottom of the float 2. A pump or the like may be used in combination for water injection, if necessary. In addition, water can be discharged from the bow ballast tank 25, the bottom ballast tank 26, and the stern ballast tank 27 by a pump or an ejector.

[0037] The outline of the equipment layout of the floating nuclear power generation system 1 according to this embodiment has been described above, but the above-mentioned equipment layout is only an example, and other equipment layouts may be adopted. Next, an outline of the system configuration of the floating nuclear power generation system 1 will be described.

[0038] <System configuration overview> 2 is a schematic diagram showing a system configuration of a floating nuclear power generation system 1 according to an embodiment. The floating nuclear power generation system 1 is mainly composed of a reactor system R and a turbine system T. The above-mentioned reactor 3 is a main device of the reactor system R. Also, the above-mentioned turbine generator 4 is a main device of the turbine system T.

[0039] The reactor system R containing the reactor 3 is equipped with various equipment such as a containment vessel 3A, nuclear fuel 3B, control rods 3C, a recirculation pump 3D, and a pressure vessel 3E. The turbine system T containing the turbine generator 4 is equipped with various equipment such as a condenser 4C, circulating water piping 4D, a circulating water pump 4E, and a feed water pump 4F in addition to the turbine 4A and generator 4B that constitute the turbine generator 4.

[0040] The containment vessel 3A is a vessel that contains the pressure vessel 3E that contains the nuclear fuel 3B and the like, and plays a role in containing radioactive materials released from the pressure vessel 3E in the event of a meltdown accident of the reactor 3, etc. The containment vessel 3A may be made of concrete, or may be made of the steel material that constitutes the float 2. The containment vessel 3A contains the pressure vessel 3E that contains the reactor 3 in its center, and forms an upper dry well 3M above the pressure vessel 3E and a lower dry well 3N below the pressure vessel 3E. The containment vessel 3A also has a suppression pool 3H around the lower dry well 3N.

[0041] The pressure vessel 3E is a vessel containing the nuclear fuel 3B, etc., and contains water and It serves to contain the steam. Several hundred nuclear fuels 3B are arranged in the center of the pressure vessel 3E in the form of fuel assemblies to form the main body of the reactor 3. In the main body of the reactor 3, control rods 3C that can be moved 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. When the control rods 3C are withdrawn from the reactor 3 and the reactor 3 goes into a critical state, the reactor 3 continues to generate heat. When the control rods 3C are inserted into the reactor 3 and the reactor 3 goes into a subcritical state, the heat generated by the reactor 3 gradually decreases.

[0042] The pressure vessel 3E is provided with a recirculation pump 3D. The recirculation pump 3D is responsible for removing heat from the reactor 3 and controlling the reactor output by forcibly circulating water, which is a reactor coolant, in the liquid phase inside the pressure vessel 3E. In the floating nuclear power generation system 1 of this embodiment, an advanced boiling water reactor (ABWR) is assumed, so in FIG. 2 the recirculation pump 3D is provided in the pressure vessel 3E, but the floating nuclear power generation system 1 is not limited to this. The floating nuclear power generation system 1 may have a recirculation system in which a recirculation pump and circulation piping are arranged outside the pressure vessel 3E, for example.

[0043] A main steam pipe 3L is connected to the pressure vessel 3E to send steam generated in the pressure vessel 3E to a turbine generator 4 of a turbine system T. Since the main steam pipe 3L is a pipe connecting the inside and outside of the containment vessel 3A, main steam isolation valves 3J, 3K are provided near the penetrations of the containment vessel 3A to enable isolation of the containment vessel 3A. A safety relief valve 3F is provided midway along 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, 3K are closed. The end of an exhaust pipe 3G downstream of the safety relief valve 3F is disposed in a suppression pool 3H.

[0044] The turbine 4A and the generator 4B constituting 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. A condenser 4C for condensing the steam that has passed through the turbine 4A is provided below the turbine 4A. A number of thin tubes that form part of the path of the circulating water piping 4D that connects the water intake and the water discharge port provided below the water line on the exterior surface of the float 2 are provided in the condenser 4C, and the steam is condensed by the cold heat of seawater pumped by the circulating water pump 4E provided on the path of the circulating water piping 4D. Therefore, the power for rotating the generator 4B is applied to the impeller due to the pressure difference between the steam supplied from the reactor 3 through the main steam pipe 3L and the inside of the condenser 4C. This causes the generator 4B to rotate and generate electricity. The condensed water condensed in the condenser 4C is fed again into the pressure vessel 3E via the feed water piping 4G by the feed water pump 4F.

[0045] Note that FIG. 2 merely shows an outline of the reactor system R and the turbine system T, and in reality, a wide variety of equipment is provided. For example, important equipment 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% bypass, in which the entire amount of main steam at rated output is sent directly to the condenser 4C without passing through the turbine 4A, or may have a bypass capacity lower than that. In addition, important equipment such as a feedwater flow rate control valve, a condensate demineralizer, and a feedwater heater are provided in the feedwater piping 4G. In addition, piping for an emergency core cooling system is provided inside and outside the containment vessel 3A. In addition, the turbine 4A is a combination of a high-pressure turbine and multiple low-pressure turbines.

[0046] 2, each device is illustrated in a single system, but each device of the floating nuclear power generation system 1 is multiplexed. For example, multiple circulating water pumps 4E and multiple feed water pumps 4F are provided.

[0047] In the reactor system R, the position of the control rod 3C is adjusted so that the reactor 3 maintains a specified reactor power. In the turbine system T, the opening of the steam control valve is adjusted so that the turbine generator 4 maintains a predetermined rotation speed, and the feedwater flow rate of the feedwater pump 4F is adjusted so that the reactor 3 maintains a predetermined water level. With this configuration, the floating nuclear power generation system 1 transmits the thermal energy generated by the nuclear reaction in the reactor 3 as electrical energy to the power grid via the generator 4B, which is synchronized with the grid frequency.

[0048] The outline of the system configuration of the floating nuclear power generation system 1 according to this embodiment has been described above. Next, a power supply system of the floating nuclear power generation system 1 will be described. Fig. 3 is a single-line diagram showing an outline of the power supply system in the float 2.

[0049] The power supply system in the floating nuclear power generation system 1 is mainly divided into a normal system and an emergency system. The emergency system is a system that can supply power from an emergency generator when external power is lost. For this reason, important equipment related to safety is connected to the emergency system. On the other hand, the normal system is a system that will lose power when external power is lost. For this reason, the normal system is connected to normal equipment that will not immediately affect safety even if it becomes inoperable.

[0050] Specifically, as shown in Fig. 3, in the power supply system in the floating nuclear power generation system 1, among the M / Cs (Metal Clads) which are 6.9kV AC busbars, M / Cs A-1, A-2, B-1, and B-2 belong to the normal system, and M / CCs, D, E, and F belong to the emergency system. In addition, among the P / Cs (Power Centers) which are 480V AC busbars, the P / CCs under the M / CCs belong to the emergency system, and the other P / Cs belong to the normal system or the emergency system in correspondence with the higher-level M / Cs.

[0051] Important equipment connected to emergency systems such as the M / CC and P / CC includes various equipment such as the residual heat removal system (RHR), reactor component cooling system (RCW), control rod drive mechanism (CRD, FMCRD), reactor component cooling seawater system (RSW), ventilation and air conditioning component emergency cooling water system (HECW), 125V DC charger, IA (control air) compressor, and other equipment, as shown in Figure 3. Equipment such as the residual heat removal system and reactor component cooling system are essential equipment for maintaining the cooling capacity of the reactor not only during operation but also during shutdown, and are therefore important equipment that must be operational immediately after a reactor scram accompanied by a loss of external power.

[0052] On the other hand, as shown in Figure 3, normal equipment connected to the normal system such as M / C A-1 includes various equipment such as feedwater pumps (FWP), high-pressure condensate pumps (HPCP), low-pressure condensate pumps (LPCP), turbine auxiliary cooling systems (TCW), recirculation pumps (RIP), and other equipment. Some equipment such as feedwater pumps and high-pressure condensate pumps are desirable to be in an operational state at all times, but they are not necessarily required to be operational immediately after a reactor scram accompanied by a loss of external power. For example, the cooling capacity of the main condenser is higher than that of the emergency core cooling system (ECCS), so it is preferable from the viewpoint of ensuring the cooling capacity of the reactor that condensation-related equipment such as circulating water pumps and feedwater pumps are in an operational state. However, condensation-related equipment such as circulating water pumps and feedwater pumps consume a large amount of power, so it is not realistic to cover the power of the equipment with emergency power sources, and the emergency core cooling system (ECCS) is designed to be able to sufficiently cool the core C. Therefore, in the floating nuclear power generation system 1, these facilities are connected to the normal power system, and when external power is lost, the connection between the emergency system and the normal system is disconnected by a circuit breaker, so that the emergency power supply, which has limited output, can cover the power of the emergency system when external power is lost.

[0053] There are several patterns for the path of power supply to the power supply system in the floating nuclear power generation system 1. The first pattern is, for example, a pattern in which power is not being generated in the floating nuclear power generation system 1, and the power supply is supplied to the starting transformer (A-STr, BS In the first pattern, power is supplied to each M / C via Line 1 and Line 2. In Fig. 3, a 275kV transmission line is shown as an example, so the startup transformer steps down the 275kV to 6.9kV. In the first pattern, power may be received from both Line 1 and Line 2, or only one of them may be received depending on circumstances such as maintenance and inspection of the transmission lines.

[0054] The second pattern is, for example, a pattern in which the floating nuclear power generation system 1 is generating electricity, and while transmitting power from the main generator MGe of the turbine system T to the power transmission lines (Line1, Line2) via the main transformer MTr, a part of the power from the main generator MGe is supplied to each M / C via the in-house transformers (A-HTr, B-HTr). In FIG. 3, the main generator MGe is 27 kV, so the main transformer steps up 27 kV to 275 kV, and the in-house transformer steps down 27 kV to 6.9 kV. In addition, in this pattern, when the turbine generator 4 can bypass the entire amount of main steam (100% bypass operation), there are also cases where all of the power from the main generator MGe is supplied to each M / C via the in-house transformers (A-HTr, B-HTr) without transmitting power to the power transmission lines (Line1, Line2).

[0055] The third pattern is, for example, a pattern in which the external power source is lost due to a system accident on the power transmission line (Line 1, Line 2) side, and in a normal nuclear power plant, power is directly supplied from a diesel generator (DG), which is an emergency power source, to the M / C of the emergency system. When the voltage of the M / C of the emergency system drops in a normal nuclear power plant, in the case of the M / CC illustrated in FIG. 3, the diesel generator (DG connected to the M / CC) immediately starts automatically when the voltage of the M / CC drops and starts supplying power to the M / CC. However, in the floating nuclear power generation system 1 of this embodiment, in addition to power supply by the diesel generator, power can be supplied to the emergency system by regular power generation equipment that generates power from natural energy.

[0056] That is, in the floating nuclear power generation system 1, in addition to diesel generators (DG), wind power generation equipment (WTG) and photovoltaic power generation equipment (PV) are connected to each M / CC, D, E, F, as shown by "※" in Fig. 3. Also, each M / CC, D, E, F is equipped with a connection port for an external power source (EXP). The connection port for the external power source is provided, for example, in the event that the floating nuclear power generation system 1 experiences a power loss, and is used when receiving a supply of power from another ship moored to the float 2.

[0057] The frequency of AC power generated by a wind power generation facility (WTG) varies depending on the rotation speed of the wind turbine, the gear ratio of the transmission, etc. In addition, the voltage and current of DC power generated by a photovoltaic power generation facility (PV) vary depending on the amount of sunlight incident on the solar panel, etc. For this reason, in this embodiment, a large storage battery facility P3 is provided midway in a circuit connecting the busbar of the M / C to a converter P1 of the photovoltaic power generation facility (PV) and a converter P2 of the wind power generation facility (WTG), and AC power is supplied from the storage battery facility P3 to the busbar of the M / C via an inverter P4.

[0058] Since the wind power generation equipment and the solar power generation equipment generate electricity using natural energy, they generate electricity not only in emergency situations but also in normal situations. In the floating nuclear power generation system 1 according to this embodiment, the wind power generation equipment and the solar power generation equipment are directly connected to the M / CC, D, E, and F of the emergency system, so that part or all of the self-consumption of the floating nuclear power generation system 1 is covered by the power of the wind power generation equipment and the solar power generation equipment in normal situations. In addition, when the normal system is blacked out due to loss of external power supply, the wind power generation equipment and the solar power generation equipment connected to the M / CC, D, E, and F of the emergency system supply power to the M / C of the emergency system as an emergency power supply via the storage battery equipment P3. Therefore, as long as at least one of the wind power generation equipment and the solar power generation equipment is generating electricity or the storage battery equipment P3 has a remaining charge, it is possible to continue supplying power to the M / C of the emergency system even if the external power supply is lost. In addition, the wind power generation equipment and the solar power generation equipment are directly connected to the M / CC, D, E, and F of the emergency system, so that the wind power generation equipment and the solar power generation equipment are directly connected to the M / CC, D, E, and F of the emergency system. In addition, in the case where the normal system is blacked out due to loss of external power supply, the wind power generation equipment and the solar power generation equipment supply power to the M / C of the emergency system as an emergency power supply via the storage battery equipment P3. Even if both photovoltaic power generation facilities stop generating power and furthermore the storage battery facility P3 loses its remaining charge, it is possible to continue supplying power to the M / C of the emergency system using power from the diesel generator which supplies power when it detects a drop in the voltage of the M / C of the emergency system.

[0059] The capacity of the tank for storing fuel (diesel) for the diesel generator is limited. Therefore, if the loss of external power supply continues for an unexpectedly long period of time, there is a risk that the fuel will run out. In this regard, in the floating nuclear power generation system 1 according to the present embodiment, natural energy power generation equipment, such as wind power generation equipment and solar power generation equipment, which do not require fuel, are connected to the M / C of the emergency system, and further, a storage battery equipment P3 is provided, so that it is possible to suppress as much as possible the possibility of a power outage in the emergency system due to the fuel running out of the diesel generator, which may occur in a normal nuclear power plant. In addition, in the floating nuclear power generation system 1 according to the present embodiment, regular power generation equipment, such as wind power generation equipment and solar power generation equipment, which generate power during normal times, are connected to the M / C of the emergency system via the storage battery equipment P3, so that it is possible to prevent the M / C of the emergency system from temporarily running out of power even if the external power supply is lost. Furthermore, with the floating nuclear power generation system 1 according to this embodiment, in addition to the diesel generator that can provide the power required in an emergency when the external power source is lost, other power generation equipment such as wind power generation equipment and solar power generation equipment can be used, so it is easy to secure the surplus power required to operate the normal system equipment even when the external power source is lost.

[0060] Furthermore, in this embodiment, a large-scale storage battery equipment P3 is provided in the middle of the circuit connecting the busbar of the emergency M / C with the converter P1 of the photovoltaic power generation equipment (PV) and the converter P2 of the wind power generation equipment (WTG), so that during normal times (patterns 1 and 2), the storage battery equipment P3 can be kept in a fully charged state and the power generated by the wind power generation equipment (WTG) and the photovoltaic power generation equipment (PV) can be supplied to electrical equipment inside and outside the floating nuclear power generation system 1. Furthermore, during a loss of external power supply (pattern 3), not only the power of the diesel generator (DG) but also the stored power of the storage battery equipment P3 and the power generated by the wind power generation equipment (WTG) and the photovoltaic power generation equipment (PV) can be supplied to each load of the emergency M / C. For this reason, in this embodiment, the capacity of the storage battery equipment P3 is set as follows.

[0061] For example, if a loss of coolant accident (LOCA) occurs in floating nuclear power system 1 and large pumps such as the high-pressure water injection system of the emergency core cooling system (ECCS) are activated, the power consumed by these large pumps to inject water in the initial period (15 minutes after the accident occurs) is estimated to be about 1.5 MWh (6 MW x 0.25 h) for each of the four systems (C, D, E, F).The power consumed by various emergency loads such as the residual heat removal system and auxiliary cooling system in the continuous core cooling after the initial period has passed is estimated to be about 110 MWh (1.5 MWh + 1505 kW x 72 h) for each of the four systems (C, D, E, F), assuming that this occurs within 72 hours after the accident occurs.

[0062] For this reason, in this embodiment, the storage capacity of one storage battery equipment P3 is set to 118 MWh. By providing such storage battery equipment P3 in each of M / CC, D, E, and F, a storage battery equipment with a total capacity of 472 MWh is provided within the float 2. In this embodiment, by providing storage battery equipment with such a capacity within the float 2, it is possible to cool the core C for approximately 72 hours even in the case where the external power source is lost and electric power from the emergency diesel generator or natural energy cannot be obtained.

[0063] It is preferable to install such a large-capacity storage battery facility, for example, below the turbine generator 4 where there is relatively more free space within the float 2. By installing a large-capacity storage battery facility in such a location, the bias of the center of gravity toward the relatively heavy reactor 3 within the float 2 can be shifted toward the turbine generator 4, thereby making it possible to more appropriately position the center of gravity of the float 2.

[0064] As such a large-capacity storage battery facility, for example, a relatively safe storage battery facility such as a lithium titanate secondary battery is suitable. In the case of a lithium titanate secondary battery, a ready-made product that is standardized to the size of a ship container has a total length of 7.5 m, a total width of 2.5 m, a total height of 3.5 m, and a storage capacity of about 500 kWh (weight is about 5.5 t). In order to secure a total capacity of 472 MWh with such ready-made products, a total of 960 of the ready-made products are required. However, if a space of, for example, a total length of 120 m, a total width of 70 m, and a total height of 12 m is secured, it is possible to store a total of 960 units (16 units for 120 m in the total length direction, 20 units for 70 m in the total width direction, and 3 units (3 stages) for about 12 m in the total height direction), and such a space can be secured relatively easily below the turbine generator 4 in the float 2. Therefore, depending on the available space in the float 2, it is also possible to arrange a storage battery facility with an even larger storage capacity. When a total of 960 storage battery units, each weighing approximately 5.5 tons, are arranged under the turbine generators 4, it is possible to somewhat reduce the buoyancy of the entire float 2. As a result, the float 2 sinks more than when such storage battery units are not installed, lowering the center of gravity of the float 2 and making it possible to stabilize the attitude of the float 2. Therefore, compared to when such storage battery units are not installed, the rocking of the float 2 is suppressed, enabling stable operation of each piece of equipment in the floating nuclear power generation system 1.

[0065] In consideration of charging a battery storage facility with such a storage capacity, it is preferable that the photovoltaic power generation facility (PV) and wind power generation facility (WTG) also have a power generation capacity that matches the storage capacity of the battery storage facility. For example, for one of the four systems M / CC, D, E, and F, if the power generation capacity of the photovoltaic power generation facility (PV) is about 500 kW and the power generation capacity of the wind power generation facility (WTG) is about 5 MW, these are considered to be power generation capacities that match the storage capacity of the battery storage facility.

[0066] Also, for example, in the case of a system configuration in which the battery capacity of the storage battery equipment P3 is extremely small and it is better to use a diesel generator (DG) in conjunction when the external power supply is lost, the diesel generator (DG) may be started at the same time as the external power supply is lost, and the diesel generator (DG) may be operated in parallel to each of the M / CC, D, E, and F of the emergency system supplied with power from the storage battery equipment P3. In this case, adjustments are made by the inverter of the storage battery equipment P3 and the automatic voltage regulator (AVR) and speed governor of the diesel generator so that the voltage and frequency of the M / C are at appropriate values.

[0067] Next, a method for installing the wind power generation facility will be described.

[0068] <First example of wind power generation facility layout> FIG. 4 is a diagram showing a first example of a method for installing a wind power generation facility. FIG. 4(A) shows a view of the floating body 2 from above, and FIG. 4(B) shows a view of the floating body 2 from the side. As described above, the floating body 2 is moored by the anchor chain 22 on the sea, and therefore floats like a windsock. Therefore, the floating body 2 floats on the sea with the bow moored by the anchor chain 22 naturally facing the upstream side of the tidal current, and rotates around the mooring part by the anchor chain 22 as shown in FIG. 4. Therefore, in this first example, the wind power generation facility 101 is installed outside the rotation range of the wind power generation facility 101. In FIG. 4, the wind power generation facility 101 is illustrated as a floating offshore wind power generation facility moored to the seabed by a cable, but the wind power generation facility 101 may be a bottom-mounted offshore wind power generation facility.

[0069] By installing the wind power generation equipment 101 in this manner, it is possible to easily install the wind power generation equipment 101 around the floating body 2. In addition, the floating body 2 moored by the anchor chain 22 will not come into contact with the wind power generation equipment 101.

[0070] In the case of this first example, the electric wire connecting the M / C of the emergency system and the wind power generation facility 101 is suspended from the wind power generation facility 101 to the seabed together with a cable that moors the wind power generation facility 101 at one end, The other end of the wire is suspended from the floating body 2 to the seabed together with the anchor chain 22 that moored the floating body 2. Therefore, the electric wire connecting the floating body 2 and the wind power generation facility 101 does not interfere with the floating body 2 due to the rotation of the floating body 2.

[0071] <Second example of wind power generation facility layout> FIG. 5 is a diagram showing a second example of a method for installing a wind power generation facility. FIG. 5(A) shows a view of the floating body 2 as seen from above, and FIG. 5(B) shows a view of the floating body 2 as seen from the side. In this second example, a wind power generation facility 101 is connected to the stern side of the floating body 2. In FIG. 5, two wind power generation facilities 101 are connected in series to the stern side of the floating body 2, but the number of wind power generation facilities 101 may be one or three or more. In this second example, it is assumed that the wind power generation facility 101 is limited to a floating type and is not moored to the seabed.

[0072] The float 2 rotates around the part moored by the anchor chain 22. However, since the rotation is caused by the tidal current, if the floating wind power generation equipment 101, which is not moored to the seabed, is connected to the stern side of the float 2, the wind power generation equipment 101 will naturally be located downstream of the float 2. Therefore, the wind power generation equipment 101 will not hinder the rotation of the float 2.

[0073] If the wind power generation equipment 101 is installed in this manner, it can be easily installed around the floating body 2. In addition, the floating body 2 moored by the anchor chain 22 will not come into contact with the wind power generation equipment 101. Furthermore, if the floating body 2 is released from its mooring by the anchor chain 22 and towed by a tugboat or the like, the wind power generation equipment 101 together with the floating body 2 can be transported over the sea.

[0074] In this first example, the electric wires connecting the M / C of the emergency system and the wind power generation equipment 101 are directly stretched between the floating body 2 and the wind power generation equipment 101 without going through the seabed. When the floating body 2 rotates, the wind power generation equipment 101 also moves in the same manner, so the electric wires connecting the floating body 2 and the wind power generation equipment 101 do not interfere with the floating body 2 or the wind power generation equipment 101.

[0075] <Third example of wind power generation facility layout> Fig. 6 is a diagram showing a third example of a method for installing a wind power generation facility. Fig. 6(A) shows a diagram of the floating body 2 as viewed from above, and Fig. 6(B) shows a diagram of the floating body 2 as viewed from the side. In this third example, a wind power generation facility 101 is mounted on the floating body 2. In Fig. 6, two wind power generation facilities 101 are mounted on the floating body 2, but the number of wind power generation facilities 101 may be one or three or more.

[0076] If the wind power generation facility 101 is installed in this manner, it is easy to connect the M / C of the emergency system to the wind power generation facility 101. In addition, there is no need to install a float for the wind power generation facility 101 around the floating body 2. Therefore, the wind power generation facility 101 has no effect on the movement of the floating body 2.

[0077] <Other examples of power generation facility layout> The installation method of the wind power generation facility is not limited to the above three examples. The wind power generation facility may be installed in a form that appropriately combines the above three examples, for example. The solar power generation facility may also be installed on the sea as in the first and second examples of the wind power generation facility layout, but it is more reasonable to install it on the upper surface (deck) of the floating body 2 as in the third example of the wind power generation facility layout. [Explanation of symbols]

[0078] R·Reactor system: T·Turbine system: F·Floating float: C·Core: 1·Floating nuclear power system: 2·Float: 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 Facilities Area:13··Accommodation Area:14··Condensate Storage Tank:18··Laydown Area:19··Ancillary Facilities Area:20··Main Transformer:21··Auxiliary Boiler:22··Anchor Chain:23··Light Oil Tank:24··Waste Treatment Room:25··Bow Ballast Tank:26··Bottom Ballast Tank:27··Stern Ballast Tank:28··Side Ballast Tank:3A··Containment Vessel:3B··Nuclear Fuel:3C··Control Rods:3D··Recirculation Pump: 3E··Pressure vessel: 3F··Safety relief valve: 3G··Exhaust pipe: 3H··Suppression pool: 3J··Main steam isolation valve: 3K··Main steam isolation valve: 3L··Main steam pipe: 3M··Upper dry well: 3N··Lower dry well: 4A··Turbine: 4B··Generator: 4C··Condenser: 4D··Circulating water piping: 4E··Circulating water pump: 4F··Feedwater pump: 4G··Feedwater piping: 101··Wind power generation equipment: 102··Solar power generation equipment: P1, P2··Converter: P3··Battery storage equipment: P4··Inverter

Claims

1. 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 disposed and which is moored on the sea; A power supply system within the float includes an emergency system capable of supplying power to a predetermined equipment for cooling the reactor in an emergency, and a normal system capable of supplying power to equipment not connected to the emergency system, A regular power generation facility that generates power using natural energy is connected to the emergency system. Floating nuclear power system.

2. The emergency system is connected to the normal power generation equipment arranged on the float or in the vicinity of the float.

2. The floating nuclear power system according to claim 1.

3. The regular power generation facility is an offshore wind power generation facility arranged around the floating body, The offshore wind power generation facility is connected to the emergency system by an electric wire passing through the seabed.

3. The floating nuclear power system according to claim 2.

4. Further comprising an emergency generator capable of supplying power to the emergency system in an emergency, The emergency system includes: During normal operation, the electric power of the regular power generating facility can be supplied to the regular power system via the emergency power system, In an emergency, the emergency generator and the regular power generating equipment are disconnected from the regular power grid, so that power is supplied from the emergency generator and the regular power generating equipment only to the specified equipment.

2. The floating nuclear power system according to claim 1.

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