Fusion power plant system based on multi-reactor one-machine and horizontal steam generator

Abstract

The invention relates to the technical field of nuclear fusion power generation, in particular to a fusion power plant system based on multiple reactors, one machine and a horizontal steam generator. The following technical scheme is provided mainly for solving the problems that a one-reactor one-machine matching mode adopted by an existing fusion power plant cannot adapt to a large-capacity and high-parameter steam turbine set, the system is complex and high in cost due to the fact that an additional energy storage system is depended on, and economical and stable power generation is difficult to achieve. Comprising a double-pile energy supply unit, a single-unit power generation unit, a loop driving unit and an alternate switching control unit, and the double-pile energy supply unit and the single-unit power generation unit form a switchable energy supply and power generation loop through the alternate switching control unit and the loop driving unit. Through the design of multi-reactor one-machine matching and multi-reactor alternate operation, a high-capacity unit can be adapted without additional energy storage, the problems that an existing scheme is low in efficiency, high in cost and complex in system are solved, and the economical efficiency and reliability of a fusion power plant are remarkably improved.

Description

Technical Field

[0001] This invention relates to the field of nuclear fusion power generation technology, and in particular to a fusion power plant system based on a multi-reactor and a horizontal steam generator. Background Technology

[0002] Nuclear fusion power generation, with its advantages of abundant fuel and clean, pollution-free operation, is an important future development direction in the energy sector. Steam turbines, as mature heat-to-work conversion devices, are widely used in traditional power generation and are also the preferred heat-to-work conversion method for future fusion power plants. Current steam turbine technology is trending towards higher parameters and larger capacities. These units can reduce blade losses, improve efficiency, and have a lower cost per kilowatt, possessing significant technological and economic advantages.

[0003] However, existing fusion power plant designs face two major bottlenecks: First, the current installed capacity of fusion reactors (such as tokamaks) is relatively small (the world's largest is expected to be the ITER project, with a fusion power of approximately 500MW). Existing solutions all adopt a unit-based matching method of "one reactor and one turbine," meaning that the energy output of a single fusion reactor cannot meet the requirements of large-capacity, high-parameter turbine units, making it difficult to enjoy the efficiency and cost advantages of large-capacity units. Second, fusion reactors cannot be continuously ignited for a considerable period of time, and their energy output is pulsed. Existing solutions require the addition of energy storage systems such as molten salt and oil to achieve continuous power generation, resulting in a significant increase in system complexity and construction and operation costs.

[0004] The publicly disclosed patents related to fusion power plants all reflect the above-mentioned design concept of one reactor plus energy storage: for example, CN113012837A and CN112967827B use molten salt energy storage in combination with Rankine cycle, CN112967826A and CN113053544A use oil energy storage in combination with Rankine cycle, and CN111075529B uses oil or molten salt energy storage in combination with Brayton cycle. All of them regulate pulse energy fluctuations through energy storage systems. Although CN105976873A does not have energy storage, it is not suitable for the current pulse operation technology stage for future steady-state fusion reactors.

[0005] In summary, existing fusion power plant solutions suffer from drawbacks such as inability to adapt to large-capacity units, poor economic efficiency, and system complexity due to their single-reactor matching method and reliance on energy storage systems, thus hindering the commercial development of fusion power generation. Therefore, this invention proposes a fusion power plant system based on a multi-reactor, single-unit architecture and a horizontal steam generator. Summary of the Invention

[0006] The purpose of this invention is to address the problems in the background art where the existing fusion power plant's one-unit-one-stall matching method cannot be adapted to large-capacity, high-parameter steam turbine units, and the reliance on additional energy storage systems leads to system complexity, high costs, and difficulty in achieving economical and stable power generation. The invention proposes a fusion power plant system based on multiple-unit-one-stall and horizontal steam generators.

[0007] The technical solution of the present invention is a fusion power plant system based on a multi-reactor and a horizontal steam generator, comprising a dual-reactor power supply unit, a single-unit power generation unit, a loop drive unit, and an alternating switching control unit.

[0008] The dual-stack power supply unit and the single-unit power generation unit form a switchable power supply and power generation circuit through alternating switching control unit and loop drive unit;

[0009] The dual-reactor power supply unit includes a symmetrically structured tokamak reactor A and a tokamak reactor B operating on alternating pulses. Tokamak reactor A is equipped with a blanket A BM01 and a divertor A DM01, while tokamak reactor B is equipped with a blanket B BM02 and a divertor B DM02. The pulse operation cycles of tokamak reactor A and tokamak reactor B are complementary.

[0010] The single-unit power generation unit includes a large-capacity horizontal steam generator MH03, a superheater MH04, a single steam turbine MT01, a condenser MH01, and a feedwater heater MH02.

[0011] The alternating switching control unit includes three-way switching valves PV1A and PV1B for switching the main circuit power supply, and three-way switching valves PV2A and PV2B for switching the auxiliary circuit power supply, as well as several isolation valves and regulating valves.

[0012] Optionally, the complementary pulse operation cycles of the tokamak reactor A and the tokamak reactor B are specifically as follows:

[0013] When Tokamak reactor A is in the t1 ignition and combustion stage, Tokamak reactor B is in the t2 rest stage.

[0014] When Tokamak reactor A enters the t2 rest phase, Tokamak reactor B simultaneously starts the t1 ignition and combustion phase, enabling the single unit to continuously generate power.

[0015] Optionally, the heat storage capacity of the large-capacity horizontal steam generator MH03 can be used to compensate for heat fluctuations during the alternating operation of Tokamak reactor A and Tokamak reactor B.

[0016] Optionally, the power supply and generation circuit includes a main circuit, an auxiliary circuit, and a secondary generation circuit;

[0017] The cladding A BM01 in the main circuit is connected to the superheater MH04 and the horizontal steam generator MH03 in sequence through the isolation valve and the three-way switching valve PV1A, and then returns to the cladding A BM01 through the main circuit pressurization device MP01 and the three-way switching valve PV1B.

[0018] The cladding B BM02 is connected to the superheater MH04 and the horizontal steam generator MH03 in sequence through the isolation valve and the three-way switching valve PV1A, and then returns to the cladding B BM02 through the main circuit pressurization device MP01 and the three-way switching valve PV1B.

[0019] In the auxiliary circuit, the divertor A DM01 is connected to the water heater MH02 through the regulating valve and the three-way switching valve PV2A, and then returns to the divertor A DM01 through the auxiliary circuit pressurizing device MP02 and the three-way switching valve PV2B.

[0020] Divertor B DM02 is connected to feedwater heater MH02 via regulating valve and three-way switching valve PV2A, and then returns to divertor B DM02 via auxiliary circuit pressurization device MP02 and three-way switching valve PV2B;

[0021] In the secondary power generation circuit, the steam generated by the horizontal steam generator MH03 is heated by the heat exchanger MH04 and then drives the steam turbine MT01 to generate electricity. The exhaust steam is condensed by the condenser MH01, pressurized by the secondary feedwater pump MP03, heated by the feedwater heater MH02, and then returned to the horizontal steam generator MH03.

[0022] Optionally, the three-way switching valves PV1A, PV1B, PV2A, and PV2B are all equipped with an auxiliary pilot valve to reduce the valve switching resistance caused by temperature and pressure differences, and to switch the alternating power supply of the two reactors.

[0023] Optionally, it also includes an active temperature control component, which includes a superheated steam water injection pressure reducing valve PV20 installed in the steam channel at the outlet of the superheater MH04. The inlet end of the superheated steam water injection pressure reducing valve PV20 is connected to the bottom of the horizontal steam generator MH03 and is used to draw low-temperature water and inject it into the steam channel to reduce the temperature of the superheated steam.

[0024] Optionally, the active temperature control component also includes an electric heating device installed in the horizontal steam generator MH03. The electric heating device is used for temperature compensation heating and is activated in the hot standby state of the equipment to achieve heat preservation.

[0025] Optionally, it also includes a steam supply parameter adjustment component and an overpressure control component. The steam supply parameter adjustment component includes a bypass valve PV18 and a bypass valve PV19 connected in parallel to the bypass of the superheater MH04. By opening and closing the bypass valves, the steam delivery path is switched, and saturated steam or superheated steam is selectively output.

[0026] Optionally, the overpressure control component includes a pressure relief valve PV39 disposed at the top of the horizontal steam generator MH03 for releasing overpressure steam from the horizontal steam generator MH03;

[0027] It also includes a pressure relief valve PV36 installed in the main circuit supply tank MV01, and two-stage pressure relief valves PV37 and PV38 installed in the main circuit pressure stabilizing tank MV02. The protection pressure of the pressure relief valve PV37 is lower than that of the pressure relief valve PV38, and the output end of the pressure relief valve PV37 is connected to the main circuit supply tank MV01.

[0028] It also includes a pressure relief valve PV32 installed in the auxiliary circuit supply tank MV03, and two-stage pressure relief valves PV33 and PV34 installed in the auxiliary circuit pressure stabilizing tank MV04. The protection pressure of the pressure relief valve PV33 is lower than that of the pressure relief valve PV34, and the output end of the pressure relief valve PV33 is connected to the auxiliary circuit supply tank MV03.

[0029] Optionally, it also includes an optional external steam supply assembly, which includes non-permanent valves PV40 and PV41. Valve PV40 is connected to the saturated steam outlet of the horizontal steam generator MH03, and valve PV41 is connected to the superheated steam outlet of the superheater MH04, for outputting industrial steam to the outside of the power plant.

[0030] In summary, this application includes at least one of the following beneficial technical effects:

[0031] 1. This invention breaks through the limitations of the existing "one reactor per unit" approach and adopts a scientific multi-reactor matching scheme. The number of reactors is determined according to the principle that the number of reactors is an integer multiple (at least 2) of the reactor output efficiency; the number of reactors * reactor output efficiency * power conversion efficiency = design power level of the power plant. This approach can be directly adapted to existing mature large-capacity generator sets. Compared with a single reactor paired with a small-capacity unit, the blade height loss of the first few stages of the regulating stage of the large-capacity unit is lower, the power generation efficiency is higher, and the cost per kW is significantly reduced.

[0032] 2. This invention abandons the existing design that relies on independent energy storage systems such as molten salt and oil to balance pulse energy fluctuations. Instead, it adopts an energy balancing scheme using a large-capacity horizontal steam generator with multiple stacks operating alternately. The alternating operation of multiple stacks ensures continuous and uninterrupted heat input. Combined with the large water storage capacity of the horizontal steam generator itself, the amount of energy storage that needs to be adjusted can be significantly reduced. The problem of energy pulse fluctuations can be solved solely by the heat storage of the steam generator itself, eliminating the need for independent large-scale energy storage devices. This design not only reduces the purchase and installation costs of energy storage equipment but also reduces the plant footprint, lowers the complexity of system control and maintenance, and significantly improves the reliability of system operation.

[0033] 3. This invention does not rely on high-power, low-maturity fusion reactors. It can achieve the target power generation by combining existing, relatively mature, low-power fusion devices. It makes full use of existing mature technologies, avoids the technical bottlenecks of high-power fusion reactors, reduces the construction risks and technical difficulties of fusion power plants, and helps to promote fusion power generation from the laboratory to practical applications.

[0034] 4. The large-capacity horizontal steam generator provides substantial heat storage capacity, enabling passive temperature buffering and mitigating temperature fluctuations without the need for manual external adjustments. An auxiliary heater further enhances temperature control and maintains heat in hot standby mode, further stabilizing the system temperature. For overheated steam, the PV20 desuperheating valve is activated to draw low-temperature water for cooling, effectively preventing damage to the turbine from overheating. This dual regulation mechanism can handle various environmental disturbances and occasional operating conditions, significantly reducing the impact of temperature fluctuations on the power generation system and ensuring long-term stable turbine operation.

[0035] 5. It has the ability to selectively output saturated steam and superheated steam, and can switch the steam delivery path by adjusting the superheater bypass valve to adapt to different types of steam turbine units; at the same time, it can adjust the exhaust steam humidity of the steam turbine unit by adjusting the superheat of the inlet steam, thereby improving the unit's operational safety and adaptability. In addition, by adding valves and pipelines, it can use the switched saturated steam or superheated steam to provide industrial steam to the vicinity of the plant site, further expanding the system's energy utilization scenarios and increasing economic added value.

[0036] 6. This invention employs a two-stage overpressure protection design for primary loop containers containing radioactive materials, especially pressurized tanks. The primary overpressure protection valves, pressure relief valves PV37 and PV33, do not directly discharge into the plant space but are connected to the corresponding supply tank. The secondary protection valves, pressure relief valves PV38 and PV34, are activated only when the pressure becomes uncontrollable to discharge the radioactive material. This design minimizes the risk of accidental release of radioactive materials and significantly improves the system's radioactive safety protection level compared to conventional single-stage overpressure protection, meeting the stringent safety regulations of nuclear power plants.

[0037] 7. Using a three-way valve with an auxiliary bypass valve as the core switching component can effectively reduce the valve switching resistance caused by temperature and pressure differences, ensuring smooth and uninterrupted switching when multiple reactors are alternately supplying power. The simple and reliable switching scheme ensures the continuous connection of power supply and generation circuits, avoids power generation interruption due to switching failures, and further enhances the continuous power supply capability of the power plant.

[0038] 8. The large-capacity horizontal steam generator selected in this invention has a water storage capacity that can not only buffer energy fluctuations but also meet the continuous energy supply requirements of multiple reactors and one unit. Compared with the vertical steam generator, the horizontal structure has higher heat storage capacity and is better suited to the heat output characteristics of the fusion reactor pulse operation, providing hardware guarantee for system energy balance and temperature stability, and further improving the operational stability and reliability of the entire power generation system.

[0039] In summary, this invention, through its multi-reactor matching and multi-reactor alternating operation design, can adapt to large-capacity units without additional energy storage, solving the problems of low efficiency, high cost, and system complexity of existing solutions, and significantly improving the economy and reliability of fusion power plants. Attached Figure Description

[0040] Figure 1 This is a principle block diagram of Example 1;

[0041] Figure 2 This is a principle block diagram of Example 2;

[0042] Figure 3 This is a principle block diagram of Embodiment 3;

[0043] Figure 4 This is a principle block diagram of Embodiment 4;

[0044] Figure 5 This is a principle block diagram of Example 5;

[0045] Figure label:

[0046] 1-1. Cladding A BM01; 1-2. Divertor A DM01; 2-1. Cladding B BM02; 2-2. Divertor B DM02; 3-1. Horizontal Steam Generator MH03; 3-2. Superheater MH04; 3-3. Single Steam Turbine MT01; 3-4. Condenser MH01; 3-5. Feedwater Heater MH02; 4-1. Main Circuit Pressurization Device MP01; 4-2. Auxiliary Circuit Pressurization Device MP02; 5-1. Main Circuit Feed Tank MV01; 5-2. Auxiliary Circuit Feed Tank MV03; 6-1. Main Circuit Pressure Stabilizer MV02; 6-2. Auxiliary Circuit Pressure Stabilizer MV04; 7-1. Secondary Circuit Feedwater Pump MP03. Detailed Implementation

[0047] The technical solution of the present invention will now be clearly and completely described with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments.

[0048] The components of the embodiments of the invention described and shown in the accompanying drawings can typically be arranged and designed in a variety of different configurations. Therefore, the following detailed description of the embodiments of the invention provided in the drawings is not intended to limit the scope of the claimed invention, but merely to illustrate selected embodiments of the invention.

[0049] Example 1:

[0050] like Figure 1 As shown, the present invention proposes a fusion power plant system based on a multi-reactor and a horizontal steam generator, including a dual-reactor power supply unit, a single-unit power generation unit, a loop drive unit, and an alternating switching control unit.

[0051] The dual-reactor power supply unit and the single-unit power generation unit form a switchable power supply and power generation circuit through alternating switching control units and loop drive units;

[0052] The single-unit power generation unit includes a large-capacity horizontal steam generator MH03 3-1, a superheater MH04 3-2, a single steam turbine MT01 3-3, a condenser MH01 3-4, and a feedwater heater MH02 3-5;

[0053] Specifically, the large-capacity horizontal steam generator MH03 3-1 has a greater heat storage capacity than the vertical steam generator. Its own water storage capacity can directly alleviate system energy fluctuations. With the dual-reactor alternating operation, there is no need to add independent energy storage systems such as molten salt or oil. It can compensate for the heat fluctuations between the alternating operation of Tokamak reactor A and Tokamak reactor B by relying solely on its own thermal inertia. There is no need to add additional molten salt or oil energy storage devices, thus reducing system complexity.

[0054] The alternating switching control unit includes three-way switching valves PV1A and PV1B for main circuit power supply switching and three-way switching valves PV2A and PV2B for auxiliary circuit power supply switching, as well as several isolation valves and regulating valves. Each of the three-way switching valves PV1A, PV1B, PV2A, and PV2B is equipped with an auxiliary pilot valve, which can effectively reduce the valve switching resistance caused by temperature and pressure differences, ensuring smooth and uninterrupted switching during alternating power supply from the two reactors. Furthermore, a state interlocking mechanism is provided between the three-way switching valves to strictly ensure the correctness of circuit switching. In the attached diagram, 1, 2, and 3 around the three-way switching valves represent the three ports of the three-way switching valves, respectively.

[0055] The dual-reactor power supply unit includes a structurally symmetrical tokamak reactor A and a tokamak reactor B operating on alternating pulses. Tokamak reactor A is equipped with a blanket A BM01 1-1 and a divertor A DM01 1-2, while tokamak reactor B is equipped with a blanket B BM02 2-1 and a divertor B DM02 2-2. The pulse operation cycles of tokamak reactor A and tokamak reactor B are complementary. Specifically, when tokamak reactor A is in the t1 ignition and combustion stage, tokamak reactor B is in the t2 rest stage. When tokamak reactor A enters the t2 rest stage, tokamak reactor B simultaneously starts the t1 ignition and combustion stage, enabling continuous power generation for the single unit.

[0056] This embodiment adopts a "2 reactors and 1 generator" multi-reactor matching scheme. The number of reactors is selected in accordance with the principle that "the number of reactors is 1 / an integer multiple of the reactor output efficiency of 2" and "number of reactors * reactor output efficiency * power conversion efficiency = design power plant level". The power conversion efficiency of the fusion device is taken as 0.3 under the current technical level, and the reactor output efficiency is taken as 0.5. The two 500MW fusion power tokamak reactors are combined to output 150MW of electricity, giving priority to the existing mature 150MW generator power level, avoiding the problems of low efficiency and high cost of small capacity units.

[0057] In this embodiment, the power supply and generation circuit includes a main circuit, an auxiliary circuit, and a secondary generation circuit;

[0058] In the main circuit, the cladding A BM01 1-1 is connected to the superheater MH04 3-2 and the horizontal steam generator MH03 3-1 in sequence via an isolation valve and a three-way switching valve PV1A, and then returns to the cladding ABM01 1-1 via the main circuit pressurization device MP01 4-1 and the three-way switching valve PV1B; the cladding B BM02 2-1 is connected to the superheater MH04 3-2 and the horizontal steam generator MH03 3-1 in sequence via an isolation valve and a three-way switching valve PV1A, and then returns to the cladding B BM02 2-1 via the main circuit pressurization device MP01 4-1 and the three-way switching valve PV1B.

[0059] In the auxiliary circuit, divertor A DM01 1-2 is connected to feedwater heater MH02 3-5 via regulating valve and three-way switching valve PV2A, and then returns to divertor A DM01 1-2 via auxiliary circuit pressurization device MP02 4-2 and three-way switching valve PV2B; divertor B DM02 2-2 is connected to feedwater heater MH02 3-5 via regulating valve and three-way switching valve PV2A, and then returns to divertor B DM02 2-2 via auxiliary circuit pressurization device MP02 4-2 and three-way switching valve PV2B; three-way switching valves PV1A, PV1B, PV2A, and PV2B are all equipped with auxiliary pilot valves to reduce valve switching resistance caused by temperature and pressure differences, and to switch the alternating power supply of the two reactors;

[0060] In the secondary power generation circuit, the steam produced by the horizontal steam generator MH03 3-1 is heated by the heat exchanger MH04 3-2 and then drives the steam turbine MT01 to generate electricity. The exhaust steam is condensed by the condenser MH01 3-4, pressurized by the secondary feedwater pump MP03 7-1, and heated by the feedwater heater MH02 3-5 before returning to the horizontal steam generator MH03 3-1. Through the combined power supply of the two reactors, the overall output efficiency is ≥1. Even if the output efficiency of a single reactor is <1, the power plant can still stably reach the design power level. Moreover, the blade height loss of the first few stages, such as the regulating stage, of the 150MW large-capacity steam turbine is lower, and the power generation efficiency is higher than that of two 75MW small-capacity steam turbines with the same parameters.

[0061] Basic operating principle explanation:

[0062] Starting at time t1, the tokamak reactor A ignites and generates energy, and the working fluid in the blanket A BM01 1-1 and the divertor ADM01 1-2 is heated.

[0063] The working fluid in the cladding A BM01 1-1 enters the superheater MH04 3-2 and the horizontal steam generator MH03 3-1 successively through the isolation valve PV02, the three-way switching valve PV1A, and the isolation valve PV05. After releasing heat, it enters the main circuit pressurization device MP01 4-1 through the valve PV07 for pressurization, and then returns to the cladding A BM01 1-1 through PV08, PV09, PV10, PV1B and PV01.

[0064] The working fluid in divertor A DM01 1-2 enters the feed water heater MH02 3-5 via PV22, PV2A and PV25, releases heat to heat the feed water, and then enters the auxiliary circuit pressurization device MP02 4-2 via PV26. After pressurization, it returns to divertor A DM01 1-2 via PV27, PV28, PV29, PV2B and PV21.

[0065] At this point, the working fluid in the power generation circuit is heated in the horizontal steam generator MH03 3-1 to produce saturated steam. After passing through PV12, it enters the superheater MH04 3-2 for further heating, producing superheated steam. This superheated steam then enters the turbine MT01 via PV13, driving the turbine unit to generate electricity. The exhaust steam, having done work, enters the condenser MH01 via PV14, condenses into liquid, and then enters the secondary loop feedwater pump MP03 7-1 via PV15 for pressurization. After passing through PV16 and PV17, it enters the feedwater heater MH02 3-5, where its temperature is raised. Finally, it returns to the horizontal evaporator MH03 via PV11. See Table 1 for details.

[0066] Table 1. Status of the three-way switching valve at time t1

[0067] ;

[0068] After time t1 ends, time t2 begins. At this time, the pulse of tokamak reactor A enters the extinction phase, and tokamak reactor B begins to ignite and burn.

[0069] The working fluid in the cladding B BM022-1 enters the superheater MH04 3-2 and the horizontal steam generator MH03 3-1 successively through the isolation valve PV04, the three-way switching valve PV1A, and the isolation valve PV05. After releasing heat, it enters the main circuit pressurization device MP014-1MP01 through the valve PV07 for pressurization, and then returns to the cladding B BM02 2-1 through PV08, PV09, PV10, PV1B and PV03.

[0070] The working fluid in divertor B DM02 2-2 enters the feed water heater MH02 3-5 via PV24, PV2A and PV25, releases heat to heat the feed water, and then enters the auxiliary circuit pressurization device MP02 4-2 via PV26. After pressurization, it returns to divertor B DM02 2-2 via PV27, PV28, PV29, PV2B and PV23.

[0071] The working fluid in the power generation circuit is heated in the horizontal steam generator MH03 3-1 to produce saturated steam. After passing through PV12, it enters the superheater MH04 3-2 for further heating to produce superheated steam. After passing through PV13, it enters the steam turbine MT01 to drive the steam turbine unit to generate electricity. The exhaust steam that has done work enters the condenser MH01 through PV14 and is condensed into liquid. After passing through PV15, it enters the feedwater pump MP01 for pressurization. After passing through PV16 and PV17, it enters the feedwater heater MH02 3-5, where it is heated to increase the temperature. After passing through PV11, it returns to the horizontal evaporator MH03.

[0072] At time t2, the pulse in tokamak reactor B enters the shutdown phase, tokamak A begins ignition and combustion, and the entire device enters the next cycle; see Table 2 for details:

[0073] Table 2. Status of the three-way switching valve at time t2

[0074] ;

[0075] Furthermore, the system includes an active temperature control component. This component comprises a superheated steam spray pressure reducing valve PV20 installed in the steam outlet channel of superheater MH04 3-2. The inlet of PV20 is connected to the bottom of the horizontal steam generator MH033-1, used to draw low-temperature water and spray it into the steam channel to reduce the temperature of the overheated steam. The active temperature control component also includes an electric heating device installed in the horizontal steam generator MH03 3-1. The electric heating device is mainly used for rapid temperature compensation heating and can also be used for heat preservation in the hot standby state of the equipment. The temperature control adopts a dual design of "passive plus active control". It utilizes the thermal inertia of the large-capacity horizontal steam generator to achieve passive buffering (large adjustment range, slow response), and auxiliary heating and spray de-cooling to achieve active and precise adjustment (small adjustment range, fast response). It can cope with various environmental disturbances and occasional operating conditions, reducing the impact on the power generation circuit.

[0076] Specifically, it also includes a steam supply parameter adjustment component and an overpressure control component. The steam supply parameter adjustment component includes bypass valves PV18 and PV19 connected in parallel to the bypass of superheater MH04 3-2. By opening and closing the bypass valves, the steam delivery path is switched, and saturated steam or superheated steam is selectively output. The overpressure control component includes a pressure relief valve PV39 located at the top of the horizontal steam generator MH03 3-1, which is used to release overpressure steam from the horizontal steam generator MH03 3-1. This design can be adapted to different types of steam turbine units and can also control the exhaust steam humidity of the steam turbine unit by adjusting the inlet steam superheat, thus broadening the equipment's adaptability.

[0077] As one implementation, the fusion power plant system also includes a pressure relief valve PV36 installed in the main circuit supply tank MV01 5-1, and two-stage pressure relief valves PV37 and PV38 installed in the main circuit pressure stabilizing tank MV02 6-1. The protection pressure of the pressure relief valve PV37 is lower than that of the pressure relief valve PV38, and the output end of the pressure relief valve PV37 is connected to the main circuit supply tank MV01 5-1.

[0078] Furthermore, the fusion power plant system also includes a pressure relief valve PV32 installed in the auxiliary loop supply tank MV03 5-2, and two-stage pressure relief valves PV33 and PV34 installed in the auxiliary loop pressure stabilizing tank MV04 6-2. The protection pressure of pressure relief valve PV33 is lower than that of pressure relief valve PV34, and the output end of pressure relief valve PV33 is connected to the auxiliary loop supply tank MV03 5-2. The two-stage overpressure protection design is for the primary loop container containing radioactive materials. When the primary overpressure occurs, the material is discharged to the supply tank to avoid direct release of radioactive materials. The secondary valve is only activated to discharge into the plant space when the pressure cannot be controlled, thereby minimizing the risk of radioactive leakage.

[0079] Furthermore, it also includes an optional external steam supply component, which includes unscheduled valves PV40 and PV41. Valve PV40 is connected to the saturated steam outlet of the horizontal steam generator MH03 3-1, and valve PV41 is connected to the superheated steam outlet of the superheater MH04 3-2, for outputting industrial steam to the outside of the power plant. This component can broaden the system's energy utilization scenarios and increase economic added value.

[0080] Example 2:

[0081] like Figure 2 As shown, based on Embodiment 1, this embodiment has the same technical solution as Embodiment 1, except that a valve group is used to replace the three-way switching valve in Embodiment 1.

[0082] The main circuit and auxiliary circuit each use a valve group consisting of two interlocked shut-off valves to replace the corresponding three-way switching valve. The valve group interlocking control ensures that only a single unit circuit is connected at any given time, achieving a circuit switching function that is completely equivalent to the three-way switching valve.

[0083] Example 3:

[0084] like Figure 3 As shown, based on the above embodiment one, this embodiment has the same technical solution as embodiment one. The difference is that it adopts a simplified energy utilization design, does not perform graded energy utilization of the cladding and divertor, replaces the original divertor with the cladding structure, and only utilizes the single energy source of the cladding.

[0085] Example 4:

[0086] like Figure 4 As shown, based on the above embodiment one, this embodiment has the same technical solution as embodiment one, the difference being that the installation form of the steam-water separation device of the horizontal steam generator is adjusted, and the built-in steam-water separation device in embodiment one is changed to an external independent device.

[0087] Example 5:

[0088] like Figure 5 As shown, based on the above embodiment one, this embodiment has the same technical solution as embodiment one, the difference being that the number of extraction and regeneration stages of the steam-water circuit of the conventional island Rankine cycle is changed.

[0089] With the power conversion efficiency of the fusion device (η=0.3) and the reactor output efficiency (η) dc =0.5) is used as a demonstration scheme for comparison and explanation.

[0090] The design features of using multiple stacks and one machine, and the use of multiple stacks and one machine, by increasing the number of stacks, although the output efficiency (η) of a single stack is increased. dc =t1 / (t1+t2)) is less than 1, but the overall output efficiency of the multi-stack combination in this scheme is greater than or equal to 1.

[0091] The performance of this solution (Example 1) was compared with that of common solutions, and the following data table was obtained:

[0092] Table 3 Comparison of Fusion Power Plant Stacker Matching Technology Schemes

[0093] ;

[0094] The data table above shows that, for the same output power, the cost of two sets (one reactor, one turbine, and one large-scale energy storage system) is higher than that of two reactors, one turbine, and no energy storage system. Therefore, the cost per kW is lower. Considering that the efficiency of one 300MW steam turbine is higher than that of two 150MW steam turbines with the same steam parameters, and that the blade height loss of the first few stages of the regulating stage in large-capacity units is lower, the advantages are even more pronounced.

[0095] The above specific embodiments are merely several optional embodiments of the present invention. Based on the technical solutions of the present invention and the relevant teachings of the above embodiments, those skilled in the art can make various alternative improvements and combinations to the above specific embodiments.

Claims

1. A fusion power plant system based on a multi-reactor and a horizontal steam generator, characterized in that, It includes a dual-reactor power supply unit, a single-unit power generation unit, a loop drive unit, and an alternating switching control unit; the dual-reactor power supply unit and the single-unit power generation unit form a switchable power supply and power generation loop through the alternating switching control unit and the loop drive unit. The dual-reactor power supply unit includes a symmetrically structured tokamak reactor A and a tokamak reactor B operating on alternating pulses. Tokamak reactor A is equipped with a blanket A BM01 (1-1) and a divertor A DM01 (1-2), while tokamak reactor B is equipped with a blanket B BM02 (2-1) and a divertor B DM02 (2-2). The pulse operation cycles of tokamak reactor A and tokamak reactor B are complementary. The single-unit power generation unit includes a large-capacity horizontal steam generator MH03 (3-1), a superheater MH04 (3-2), a single steam turbine MT01 (3-3), a condenser MH01 (3-4), and a feedwater heater MH02 (3-5). The alternating switching control unit includes three-way switching valves PV1A and PV1B for switching the main circuit power supply, and three-way switching valves PV2A and PV2B for switching the auxiliary circuit power supply, as well as several isolation valves and regulating valves.

2. A fusion power plant system based on a multi-reactor and a horizontal steam generator according to claim 1, characterized in that, The complementary pulse operation cycles of Tokamak reactor A and Tokamak reactor B are specifically as follows: When Tokamak reactor A is in the t1 ignition and combustion stage, Tokamak reactor B is in the t2 rest stage. When Tokamak reactor A enters the t2 rest phase, Tokamak reactor B simultaneously starts the t1 ignition and combustion phase, enabling the single unit to continuously generate power.

3. A fusion power plant system based on a multi-reactor and a horizontal steam generator according to claim 1, characterized in that, The heat storage capacity of the large-capacity horizontal steam generator MH03(3-1) is used to compensate for heat fluctuations during the alternating operation of tokamak reactor A and tokamak reactor B.

4. A fusion power plant system based on a multi-reactor and a horizontal steam generator according to claim 1, characterized in that, The power supply and generation circuits include a main circuit, an auxiliary circuit, and a secondary power generation circuit. The cladding A BM01 (1-1) in the main circuit is connected to the superheater MH04 (3-2) and the horizontal steam generator MH03 (3-1) in sequence through the isolation valve and the three-way switching valve PV1A, and then returns to the cladding A BM01 (1-1) through the main circuit pressurization device MP01 (4-1) and the three-way switching valve PV1B. The cladding B BM02 (2-1) is connected to the superheater MH04 (3-2) and the horizontal steam generator MH03 (3-1) in sequence through the isolation valve and the three-way switching valve PV1A, and then returns to the cladding B BM02 (2-1) through the main circuit pressurization device MP01 (4-1) and the three-way switching valve PV1B. In the auxiliary circuit, the divertor A DM01 (1-2) is connected to the water heater MH02 (3-5) through the regulating valve and the three-way switching valve PV2A, and then returns to the divertor A DM01 (1-2) through the auxiliary circuit pressurizing device MP02 (4-2) and the three-way switching valve PV2B. Divertor B DM02 (2-2) is connected to water heater MH02 (3-5) via regulating valve and three-way switching valve PV2A, and then returns to divertor B DM02 (2-2) via auxiliary circuit pressurization device MP02 (4-2) and three-way switching valve PV2B. The steam generated by the horizontal steam generator MH03 (3-1) in the secondary power generation circuit is heated by the heat exchanger MH04 (3-2) and then drives the steam turbine MT01 to generate electricity. The exhaust steam is condensed by the condenser MH01 (3-4), pressurized by the secondary feedwater pump MP03 (7-1), heated by the feedwater heater MH02 (3-5), and then returned to the horizontal steam generator MH03 (3-1).

5. A fusion power plant system based on a multi-reactor and a horizontal steam generator according to claim 4, characterized in that, The three-way switching valves PV1A, PV1B, PV2A, and PV2B are all equipped with auxiliary pilot valves to reduce valve switching resistance caused by temperature and pressure differences, and to switch the alternating power supply of the two reactors.

6. A fusion power plant system based on a multi-reactor and a horizontal steam generator according to claim 1, characterized in that, It also includes an active temperature control component, which includes a superheated steam spray pressure reducing valve PV20 installed in the steam channel at the outlet of the superheater MH04 (3-2). The inlet end of the superheated steam spray pressure reducing valve PV20 is connected to the bottom of the horizontal steam generator MH03 (3-1) and is used to draw low-temperature water into the steam channel to reduce the temperature of the superheated steam.

7. A fusion power plant system based on a multi-reactor and a horizontal steam generator according to claim 6, characterized in that, The active temperature control component also includes an electric heating device installed in the horizontal steam generator MH03 (3-1). The electric heating device is used for temperature compensation heating and is activated in the hot standby state of the equipment to achieve heat preservation.

8. A fusion power plant system based on a multi-reactor and a horizontal steam generator according to claim 1, characterized in that, It also includes a steam supply parameter adjustment component and an overpressure control component. The steam supply parameter adjustment component includes a bypass valve PV18 and a bypass valve PV19 connected in parallel to the bypass of the superheater MH04 (3-2). By opening and closing the bypass valves, the steam delivery path is switched, and saturated steam or superheated steam is selectively output.

9. A fusion power plant system based on a multi-reactor and a horizontal steam generator according to claim 8, characterized in that, The overpressure control component includes a pressure relief valve PV39 located at the top of the horizontal steam generator MH03 (3-1) for releasing overpressure steam from the horizontal steam generator MH03 (3-1); It also includes a pressure relief valve PV36 installed in the main circuit supply tank MV01 (5-1), and a two-stage pressure relief valve PV37 and a pressure relief valve PV38 installed in the main circuit pressure stabilizing tank MV02 (6-1). The protection pressure of the pressure relief valve PV37 is lower than that of the pressure relief valve PV38, and the output end of the pressure relief valve PV37 is connected to the main circuit supply tank MV01 (5-1). It also includes a pressure relief valve PV32 installed in the auxiliary circuit supply tank MV03 (5-2), and a two-stage pressure relief valve PV33 and a pressure relief valve PV34 installed in the auxiliary circuit pressure stabilizing tank MV04 (6-2). The protection pressure of the pressure relief valve PV33 is lower than that of the pressure relief valve PV34, and the output end of the pressure relief valve PV33 is connected to the auxiliary circuit supply tank MV03 (5-2).

10. A fusion power plant system based on a multi-reactor and a horizontal steam generator according to claim 1, characterized in that, It also includes an optional external steam supply assembly, which includes non-permanent valves PV40 and PV41. Valve PV40 is connected to the saturated steam outlet of the horizontal steam generator MH03 (3-1), and valve PV41 is connected to the superheated steam outlet of the superheater MH04 (3-2) for supplying industrial steam to the outside of the power plant.

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