Self-driven thermoelectric power generation type nuclear emergency power supply system
The self-driven thermoelectric nuclear emergency power system utilizes the temperature difference between the heat source and cold source of the nuclear power plant to generate electricity, solving the problems of limited capacity and short power supply time of nuclear emergency power. It achieves long-term stable power supply in the event of a plant-wide power outage, improves system independence and reduces modification costs.
Patent Information
- Application Number
- CN202511661708.6
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2025-11-13
- Publication Date
- 2026-03-17
AI Technical Summary
Existing nuclear emergency power systems have limited capacity and short power supply time in the event of a plant-wide power outage, making it difficult to meet the demand for stable power supply over a long period of time, and their reliance on external power sources poses a risk of failure.
Design a self-driven thermoelectric nuclear emergency power system that utilizes the temperature difference between the heat source and cold source of a nuclear power plant to generate electricity. The system establishes natural and forced circulation through a thermoelectric generator and a self-driven circulating pump, outputting electrical energy to the nuclear power plant's emergency power system. The circulating pump is driven by the thermoelectric generator, avoiding dependence on external power.
The system can generate electricity continuously for 72 hours after a plant-wide power outage, improving system independence and power supply stability, reducing modification costs, and allowing existing equipment to be used as the cold source to maintain cooling capacity in the long term.
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Figure CN121689467A_ABST
Abstract
Description
Technical Field
[0001] This invention relates to the field of nuclear emergency power technology, and in particular to a self-driven thermoelectric nuclear emergency power supply. Background Technology
[0002] During nuclear power plant operation, a complete power outage is one of the extreme conditions threatening nuclear safety. Highly reliable emergency power supplies are essential to ensure the continuous operation of critical systems and equipment, guaranteeing safe reactor shutdown and residual heat removal. Current mainstream nuclear emergency power solutions primarily rely on battery banks and diesel generator sets. However, batteries have limited capacity and short continuous power supply time, while diesel generators depend on external fuel supply and powered equipment. In scenarios involving extreme disasters and power failures, these systems cannot meet the demand for stable power supply over extended periods, posing a risk of power outages. Among existing technologies, thermoelectric power generation (TEG) offers the potential to provide continuous power to safety-related systems in nuclear power plants; however, current research indicates a technological gap in the engineering application of this TEG-based nuclear emergency power system. Summary of the Invention
[0003] This invention provides a self-driven thermoelectric nuclear emergency power supply system to solve the problems of limited capacity and short power supply time in existing nuclear emergency power supplies.
[0004] The technical solution of the present invention is as follows:
[0005] This invention proposes a self-driven thermoelectric nuclear emergency power system, comprising: a thermoelectric generator, a heat source, a self-driven circulating pump, a nuclear power plant electrical system, and a cooling water tank. The heat exchange unit of the thermoelectric generator is connected to the heat source via pipelines, establishing a natural circulation between the thermoelectric generator and the heat source. The cold-side heat exchange unit of the thermoelectric generator is connected to the cooling water tank via pipelines. The cooling water tank is sequentially connected to the self-driven circulating pump and the thermoelectric generator via pipelines, establishing a forced circulation between the thermoelectric generator and the cooling water tank via the self-driven circulating pump. The thermoelectric generator is electrically connected to the nuclear power plant emergency power system.
[0006] In some embodiments, the thermoelectric generator includes a fixing screw, a clamping plate, a cooling water plate, a sequence of thermoelectric generator plates, and a heating plate. Two clamping plates are connected by a fixing screw. The cooling water plate, the sequence of thermoelectric generator plates, and the heating plate are disposed between the two clamping plates. The cooling water plate and the heating plate are staggered, and the sequence of thermoelectric generator plates is disposed between the cooling water plate and the heating plate. The cold-side heat exchange unit is the cooling water plate, and the hot-side heat exchange unit is the heating plate.
[0007] In some embodiments, the heating plate is made of a hollow metal plate with built-in flow channels and inlets and outlets at both ends, and the cooling water plate is made of a hollow metal plate with built-in flow channels and inlets and outlets.
[0008] In some embodiments, the thermoelectric generator, the heat source, and the pipeline connecting the thermoelectric generator to the heat source are insulated with thermal insulation materials to prevent heat loss.
[0009] In some embodiments, the self-driven circulating pump is a DC power source and is driven by a thermoelectric generator. The thermoelectric generator generates electricity through a heat source and a cooling water tank, part of which is used to power the self-driven circulating pump, and the remainder is converted into AC power and connected to the nuclear power plant's emergency power system.
[0010] In some embodiments, a regulating valve and a temperature measuring point are installed on the pipe connecting the cooling water plate and the cooling water tank. The temperature measuring point is used to monitor the working fluid parameters. The cooling water tank is equipped with an emergency water supply interface, which is connected to the fire water tank.
[0011] In some embodiments, the heat source is a steam generator, and the inlet and outlet of the heating plate are connected to the steam generator via pipelines.
[0012] In some embodiments, the heat source is a reactor system, which includes a reactor, a passive waste heat removal heat exchanger, and a steam generator. The reactor is connected to a pressurizer and the passive waste heat removal heat exchanger via pipelines. The passive waste heat removal water tank is connected to the steam generator via pipelines, and the steam generator is connected to the reactor via pipelines. The heating plates of the thermoelectric generator are connected to the pipelines between the reactor and the passive waste heat removal heat exchanger, as well as the pipelines between the passive waste heat removal heat exchanger and the steam generator, via pipelines.
[0013] In some embodiments, a passive waste heat discharge heat exchanger is disposed inside a passive waste heat discharge water tank.
[0014] The implementation of this invention has the following beneficial effects:
[0015] This invention proposes a self-driven thermoelectric nuclear emergency power supply system. This system generates electricity using the temperature difference between the heat source and cold source of a nuclear power plant. Under different nuclear power unit application scenarios, the nuclear emergency power supply possesses continuous natural circulation capability for up to 72 hours after a plant-wide power outage. The circulation pump is powered by the nuclear emergency power supply itself, eliminating the need for an external power source and avoiding the risk of active equipment failure during a plant-wide power outage, thus enhancing system independence. The cold source can be existing equipment such as an internal refueling water tank or a fire-fighting water tank, eliminating the need for new systems, reducing modification costs, and providing a large tank capacity to maintain cooling capacity over a long period. Attached Figure Description
[0016] Figure 1 This is a schematic diagram of a reactor as a heat source in a self-driven thermoelectric nuclear emergency power system according to an embodiment of the present invention.
[0017] Figure 2This is a schematic diagram of a steam generator serving as a heat source for a self-driven thermoelectric nuclear emergency power system according to an embodiment of the present invention.
[0018] Figure 3 This is a schematic diagram of a thermoelectric generator for a self-driven thermoelectric nuclear emergency power system according to an embodiment of the present invention.
[0019] Explanation of reference numerals in the attached diagram: 1. Reactor; 2. Thermoelectric generator; 3. Voltage regulator; 4. Passive waste heat removal heat exchanger; 5. Passive waste heat removal water tank; 6. Steam generator; 7. Self-driven circulating pump; 8. Cooling water tank; 9. Nuclear power plant electrical system; 201. Fixing screw; 202. Clamping plate; 203. Cooling water plate; 204. Thermoelectric generator sequence; 205. Heating plate. Detailed Implementation
[0020] The technical solution of the present invention will be clearly and completely described below with reference to the accompanying drawings and specific embodiments. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.
[0021] like Figures 1 to 3 As shown, the present invention proposes a self-driven thermoelectric nuclear emergency power supply system, which includes a thermoelectric generator 2, a heat source, a cold source and a nuclear power plant electrical system 9. The thermoelectric generator 2 is connected to the heat source and the cold source through pipelines, and the thermoelectric generator 2 is electrically connected to the nuclear power plant electrical system 9.
[0022] The thermoelectric generator 2 includes a fixing screw 201, a clamping plate 202, a cooling water plate 203, a thermoelectric generator sequence 204, and a heating plate 205. The two clamping plates 202 are connected by the fixing screw 201. The cooling water plate 203, the thermoelectric generator sequence 204, and the heating plate 205 are positioned between the two clamping plates 202, with the cooling water plate 203 and the heating plate 205 staggered. The thermoelectric generator sequence 204 is positioned between the cooling water plate 203 and the heating plate 205. The thermoelectric generator 2 is electrically connected to the nuclear power plant's electrical system 9, establishing the temperature difference required for the thermoelectric generator sequence 204 between the cooling water plate 203 and the heating plate 205, and outputting electrical energy to the nuclear power plant's electrical system 9. The DC power output from the thermoelectric conversion device is stabilized by a DC-DC converter, with a portion supplied to the self-driven circulating pump 7 of the cold source. The remaining electrical energy is converted to AC power by a DC-AC inverter and connected to the nuclear power plant's emergency power system. The heating plate 205 can be made of a hollow metal plate with various built-in flow channels and inlets and outlets at both ends, and the cooling water plate 203 can be made of a hollow metal plate with various built-in flow channels and inlets and outlets.
[0023] To prevent heat loss from the hot and cold ends through various equipment or pipelines in the system, the thermoelectric generator 2, the heat source, and the connecting pipelines and fittings must all be rigorously insulated with thermal insulation materials. The thermoelectric conversion device adopts a double-layer sealed structure, filled with thermal insulation material to reduce heat loss and prevent radioactive leakage.
[0024] The cold source includes a self-driven circulating pump 7 and a cooling water tank 8. The cooling water plate 203 of the thermoelectric generator 2 is connected to the cooling water tank 8 via pipelines. The cooling water tank 8 is connected in sequence to the self-driven circulating pump 7 and the thermoelectric generator 2 via pipelines. The working fluid of the cold source comes from the cooling water tank 8, such as the fire-fighting water tank in the nuclear power plant. Forced circulation is established between the cold source and the cooling water plate 203 in the thermoelectric generator 2 through the self-driven circulating pump 7. The self-driven circulating pump 7 in the nuclear emergency power system requires DC power, which is driven by the thermoelectric generator 2.
[0025] The heat source includes reactor 1 system or steam generator 6, and a natural circulation can be established between the heat source and the heating plate 205 in the thermoelectric generator 2. Figure 2 As shown, in the design using the steam generator 6 as the heat source, the inlet and outlet of the heating plate 205 are connected to the steam generator 6 through pipelines, and a natural circulation is formed between the heating plate 205 and the steam generator 6.
[0026] like Figure 1 As shown, in the design using reactor 1 as the heat source, the reactor 1 system includes reactor 1, pressurizer 3, passive waste heat removal heat exchanger 4, passive waste heat removal water tank 5, and steam generator 6. Reactor 1 is connected to pressurizer 3 and passive waste heat removal heat exchanger 4 via pipelines. Passive waste heat removal water tank 5 is connected to steam generator 6 via pipelines. Steam generator 6 is connected to reactor 1 via pipelines. Passive waste heat removal heat exchanger 4 is located inside passive waste heat removal water tank 5. The heating plate 205 of thermoelectric generator 2 is connected to the pipelines between reactor 1 and passive waste heat removal heat exchanger 4, as well as the pipelines between passive waste heat removal heat exchanger 4 and steam generator 6, via pipelines.
[0027] The above system design ensures that the hot and cold working fluids can continue to circulate even in the event of a plant-wide power outage, establishing the temperature difference required for the thermoelectric generator sequence 204 between the cooling water plate 203 and the heating plate 205, and outputting electrical energy to the nuclear power plant's electrical system 9. The flow direction of the fluid within the nuclear emergency power system loop is not limited to the attached... Figure 1 Appendix Figure 2 The flow direction is shown in the figure.
[0028] This invention proposes a self-driven thermoelectric nuclear emergency power supply system. For the thermoelectric generator 2 installed on the heat source side, a bypass branch needs to be added between the hot and cold pipe sections of the heat source. Specifically, the cooled pipe section of the steam generator 6 is the cold pipe section, and the uncooled pipe section is the hot pipe section. A heating plate 205 for the thermoelectric conversion device is installed, and the thermoelectric conversion device is connected to the bypass branch of the main pipeline via a flange to ensure sealing and seismic resistance.
[0029] For the system installation on the cold source side, a self-driven circulating pump 7 needs to be installed on the cold-side loop of the cooling water tank 8. The pump parameters are matched to the coolant flow rate and resistance requirements, and the motor adopts a waterproof and moisture-proof design to adapt to the environment inside the containment. The cooling water plate 203 of the thermoelectric generator 2 is connected to the cooling water tank 8 through a pipeline, using a straight-through heat exchange. When the water quality is substandard, an intermediate heat exchanger can be used. The pipeline is equipped with a flow regulating valve and temperature measuring points to monitor the cold-side working fluid parameters. The cooling water tank 8 of the cold source is equipped with an emergency water supply interface, which is connected to the fire water tank to ensure the reliability of the cold source during long-term operation.
[0030] The nuclear emergency power supply system proposed in this invention, when applied in the primary loop of an AP1000 nuclear power plant, exhibits a maximum device temperature difference of 228°C, a maximum conversion efficiency of 5.71%, a maximum power output of 27.7 kWe, and a cumulative power generation of 901 kWh within 72 hours after an accident. Under the design parameters of the Hualong One unit, the nuclear emergency power supply system has a maximum device temperature difference of 203°C, a maximum conversion efficiency of 5.63%, a maximum power output of 23.65 kWe, and a cumulative power generation of 61 kWh within 8 hours after an accident, with relatively low output power from 8 to 72 hours. Therefore, the nuclear emergency power supply system proposed in this invention overcomes the shortcomings of existing technologies and provides stable power to nuclear power plants under accident conditions.
[0031] The above embodiments merely illustrate several implementation methods of the present invention, and their descriptions are relatively specific and detailed, but they should not be construed as limiting the scope of the present invention. It should be noted that those skilled in the art can make various modifications and improvements without departing from the concept of the present invention, and these all fall within the protection scope of the present invention. Therefore, the protection scope of this patent should be determined by the appended claims.
Claims
1. A self-driven thermoelectric nuclear emergency power supply system, characterized in that, The system includes: a thermoelectric generator (2), a heat source, a self-driven circulating pump (7), a nuclear power plant electrical system (9), and a cooling water tank (8). The heat exchange unit of the thermoelectric generator (2) is connected to the heat source through a pipeline, and a natural circulation is established between the thermoelectric generator (2) and the heat source. The cold heat exchange unit of the thermoelectric generator (2) is connected to the cooling water tank (8) through a pipeline. The cooling water tank (8) is connected to the self-driven circulating pump (7) and the thermoelectric generator (2) in sequence through a pipeline. A forced circulation is established between the thermoelectric generator (2) and the cooling water tank (8) through the self-driven circulating pump (7). The thermoelectric generator (2) is electrically connected to the nuclear power plant emergency power supply system.
2. The self-driven thermoelectric nuclear emergency power supply system according to claim 1, characterized in that, The thermoelectric generator (2) includes a fixing screw (201), a clamping plate (202), a cooling water plate (203), a thermoelectric generator sequence (204), and a heating plate (205). The two clamping plates (202) are connected by the fixing screw (201). The cooling water plate (203), the thermoelectric generator sequence (204), and the heating plate (205) are arranged between the two clamping plates (202). The cooling water plate (203) and the heating plate (205) are arranged alternately. The thermoelectric generator sequence (204) is provided between the cooling water plate (203) and the heating plate (205). The cold-side heat exchange unit is the cooling water plate (203), and the hot-side heat exchange unit is the heating plate (205).
3. A self-driven thermoelectric nuclear emergency power supply system according to claim 2, characterized in that, The heating plate (205) is made of a hollow metal plate with built-in flow channels and inlets and outlets at both ends, and the cooling water plate (203) is made of a hollow metal plate with built-in flow channels and inlets and outlets.
4. A self-driven thermoelectric nuclear emergency power supply system according to claim 3, characterized in that, The thermoelectric generator (2), the heat source, and the pipeline connecting the thermoelectric generator (2) to the heat source are insulated with heat-insulating materials to prevent heat loss.
5. A self-driven thermoelectric nuclear emergency power supply system according to claim 4, characterized in that, The self-driven circulating pump (7) is a DC power source and is driven by a thermoelectric generator (2). The thermoelectric generator (2) generates electricity through a heat source and a cooling water tank (8), part of which is used to power the self-driven circulating pump (7), and the rest is converted into AC power and connected to the nuclear power plant emergency power system.
6. A self-driven thermoelectric nuclear emergency power supply system according to claim 5, characterized in that, A regulating valve and a temperature measuring point are installed on the pipe connecting the cooling water plate (203) and the cooling water tank (8). The temperature measuring point is used to monitor the working fluid parameters. An emergency water supply interface is provided in the cooling water tank (8), and the emergency water supply interface is connected to the fire water pool.
7. A self-driven thermoelectric nuclear emergency power supply system according to claim 6, characterized in that, The heat source is a steam generator (6), and the inlet and outlet of the heating plate (205) are connected to the steam generator (6) through pipelines.
8. A self-driven thermoelectric nuclear emergency power supply system according to claim 6, characterized in that, The heat source is a reactor (1) system, which includes a reactor (1), a passive waste heat discharge heat exchanger (4), and a steam generator (6). The reactor (1) is connected to a pressurizer (3) and the passive waste heat discharge heat exchanger (4) through pipelines. The passive waste heat discharge water tank (5) is connected to the steam generator (6) through pipelines. The steam generator (6) is connected to the reactor (1) through pipelines. The heating plate (205) of the thermoelectric generator (2) is connected to the pipeline between the reactor (1) and the passive waste heat discharge heat exchanger (4), as well as the pipeline between the passive waste heat discharge heat exchanger (4) and the steam generator (6) through pipelines.
9. A self-driven thermoelectric nuclear emergency power supply system according to claim 8, characterized in that, The passive waste heat discharge heat exchanger (4) is installed inside the passive waste heat discharge water tank (5).
