CN220041407U - Nuclear power unit system based on fused salt heat storage coupling - Google Patents
Nuclear power unit system based on fused salt heat storage coupling Download PDFInfo
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- CN220041407U CN220041407U CN202320919044.9U CN202320919044U CN220041407U CN 220041407 U CN220041407 U CN 220041407U CN 202320919044 U CN202320919044 U CN 202320919044U CN 220041407 U CN220041407 U CN 220041407U
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- 150000003839 salts Chemical class 0.000 title claims abstract description 126
- 238000005338 heat storage Methods 0.000 title claims abstract description 77
- 230000008878 coupling Effects 0.000 title claims abstract description 21
- 238000010168 coupling process Methods 0.000 title claims abstract description 21
- 238000005859 coupling reaction Methods 0.000 title claims abstract description 21
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 103
- 239000002826 coolant Substances 0.000 claims description 8
- 238000004146 energy storage Methods 0.000 abstract description 5
- 230000005611 electricity Effects 0.000 description 3
- 238000010438 heat treatment Methods 0.000 description 3
- 238000010248 power generation Methods 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000005485 electric heating Methods 0.000 description 1
- 238000004134 energy conservation Methods 0.000 description 1
- 238000005265 energy consumption Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 229920006395 saturated elastomer Polymers 0.000 description 1
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Abstract
The utility model provides a nuclear power unit system based on molten salt heat storage coupling, wherein a second outlet of a first valve in the nuclear power unit system is connected with a molten salt heat storage system, and the molten salt heat storage system comprises a heat exchange subsystem, a heat storage subsystem and a heat release subsystem; the steam outlets of the heat exchange subsystem are respectively connected with the high-temperature molten salt inlet of the heat storage subsystem and the steam inlet of the heat release subsystem, the low-temperature molten salt outlet of the heat storage subsystem is connected with the steam inlet of the heat exchange subsystem, the low-temperature molten salt inlet of the heat storage subsystem is connected with the low-temperature molten salt outlet of the heat release subsystem, the high-temperature molten salt outlet of the heat storage subsystem is connected with the high-temperature molten salt inlet of the heat release subsystem, and the steam outlet of the heat release subsystem is connected with the inlet of the high-pressure cylinder of the steam turbine. According to the utility model, the nuclear power unit and the large-scale fused salt heat energy storage are coupled, so that the flexibility and peak shaving capacity of the nuclear power unit can be obviously improved, and the power grid dispatching requirement can be met.
Description
Technical Field
The utility model belongs to the technical field of new energy conservation, and particularly relates to a nuclear power unit system based on molten salt heat storage coupling.
Background
The statements in this section merely provide background information related to the present disclosure and may not necessarily constitute prior art.
The novel power system takes new energy sources such as wind power generation, photovoltaic power generation and the like as main bodies, and the inherent randomness, fluctuation and intermittence of the new energy source power generation bring challenges to the safe and stable operation of the power system, so that the existing nuclear power unit is required to improve the operation flexibility and have peak shaving capacity. With the increasing of the peak-valley difference of the load of the power system, the large nuclear power unit is necessary to participate in the peak regulation operation of the system. In an electric power system, the heat storage technology is an important means for solving the peak shaving problem, is not limited by regions any more, and has certain superiority.
The fused salt has the advantages of higher use temperature, high thermal stability, high specific heat capacity, high convection heat transfer coefficient, low viscosity, low saturated vapor pressure and the like, is an excellent heat transfer energy storage medium, and the fused salt heat storage technology is started to be applied to the fields of steam heating heat storage and heating and heat supply by valley electricity. Therefore, how to reasonably utilize the heat release process of the heat storage device and couple the nuclear power unit with the heat storage device to increase the system peak shaving capacity is a technical problem to be solved.
Disclosure of Invention
In order to overcome the defects in the prior art, the utility model provides a nuclear power unit system based on molten salt heat storage coupling.
To achieve the above object, one or more embodiments of the present utility model provide the following technical solutions:
the utility model provides a nuclear power unit system based on molten salt heat storage coupling, which comprises a reactor, a steam generator, a first valve, a steam turbine high-pressure cylinder, a steam-water separator reheater, a second valve, a steam turbine low-pressure cylinder and a condenser, wherein the reactor, the steam generator and the first valve are sequentially connected;
the second outlet of the first valve is connected with a molten salt heat storage system, and the molten salt heat storage system comprises a heat exchange subsystem, a heat storage subsystem and a heat release subsystem;
the steam outlets of the heat exchange subsystem are respectively connected with the high-temperature molten salt inlet of the heat storage subsystem and the steam inlet of the heat release subsystem, the low-temperature molten salt outlet of the heat storage subsystem is connected with the steam inlet of the heat exchange subsystem, the low-temperature molten salt inlet of the heat storage subsystem is connected with the low-temperature molten salt outlet of the heat release subsystem, the high-temperature molten salt outlet of the heat storage subsystem is connected with the high-temperature molten salt inlet of the heat release subsystem, and the steam outlet of the heat release subsystem is connected with the inlet of the high-pressure cylinder of the steam turbine.
Further, the heat exchange subsystem includes a plurality of primary steam-molten salt heat exchangers.
Further, the heat release subsystem comprises a seventh valve, a third circulating water pump, a fifth valve and a molten salt-water supply heat exchanger which are sequentially connected;
the steam outlet of the molten salt-water supply heat exchanger is connected with the inlet of the high-pressure cylinder of the steam turbine through a sixth valve;
an inlet of the seventh valve is connected with a steam outlet of the heat exchange subsystem, and an outlet of the seventh valve is also connected with a condenser.
Further, the heat storage subsystem comprises a low-temperature heat storage module and a high-temperature heat storage module, wherein an inlet of the high-temperature heat storage module is connected with a steam outlet of the heat exchange subsystem, and an outlet of the high-temperature heat storage module is connected with a high-temperature molten salt inlet of the molten salt-water supply heat exchanger; and an inlet of the low-temperature heat storage module is connected with a high-temperature molten salt outlet of the molten salt-water supply heat exchanger, and an outlet of the low-temperature heat storage module is connected with a steam inlet of the heat exchange subsystem.
Further, the low-temperature heat storage module comprises a low-temperature molten salt storage tank, a low-temperature molten salt pump and a low-temperature molten salt valve which are sequentially connected.
Further, the high-temperature heat storage module comprises an electric heating, a high-temperature molten salt storage tank, a high-temperature molten salt pump and a high-temperature molten salt valve which are sequentially connected.
Furthermore, the nuclear power unit system further comprises a generator, and the high-pressure cylinder of the steam turbine and the low-pressure cylinder of the steam turbine are connected with the generator.
Further, the nuclear power unit system further comprises a main coolant pump, wherein the input end of the main coolant pump is connected with the steam generator, and the output end of the main coolant pump is connected with the reactor.
Further, the nuclear power unit system further comprises a low-pressure heater, a deaerator and a high-pressure heater;
the steam outlets of the high-pressure cylinder and the low-pressure cylinder of the steam turbine are respectively connected with the steam inlets of the high-pressure heater and the low-pressure heater;
the air outlet of the steam-water separator reheater is connected with the air inlet of the deaerator;
the water supply inlet of the high-pressure heater is connected with the water supply outlet of the deaerator through a second circulating water pump, and the water supply outlet of the high-pressure heater is respectively connected with the water supply inlet of the steam generator and the water supply inlet of the deaerator;
the water supply inlet of the low-pressure heater is connected with the outlet of the first circulating water pump, the inlet of the first circulating water pump is connected with the water supply outlet of the condenser, and the water supply outlet of the low-pressure heater is connected with the water supply inlet of the deaerator.
Further, the high-pressure heater is a multi-stage high-pressure heater, a water supply inlet of the first-stage high-pressure feed water heater is connected with an outlet of the second circulating water pump, and an inlet of the second circulating water pump is connected with a feed water outlet of the deaerator; the water supply outlet of the last-stage high-pressure feed water heater is connected with the inlet of the steam generator and the inlet of the deaerator, and the steam inlets of the high-pressure heaters of each stage are connected with the steam exhaust port of the high-pressure cylinder of the steam turbine;
the low-pressure heater is a multi-stage low-pressure heater, a water supply inlet of the first-stage low-pressure heater is connected with an outlet of the first circulating water pump, and an inlet of the first circulating water pump is connected with a water supply outlet of the condenser; the water supply outlet of the last stage of low-pressure water supply heater is connected with the water supply inlet of the deaerator, and the steam inlet of each stage of low-pressure water supply heater is connected with the steam discharge port of the low-pressure cylinder of the steam turbine.
The one or more of the above technical solutions have the following beneficial effects:
(1) According to the utility model, the nuclear power unit and the large-scale fused salt heat energy storage are coupled, so that the flexibility and peak shaving capacity of the nuclear power unit can be obviously improved, and the power grid dispatching requirement is met; the nuclear reactor operates at a constant power level, providing heat to the molten salt heat storage system. The molten salt heat storage system will provide heat in accordance with the amount of power generated required and the system can be designed to respond quickly to changes in power demand.
(2) The utility model utilizes the heat energy storage coupling of the nuclear power unit and the fused salt, the fused salt temperature interval is wider, the larger temperature difference is provided, the energy storage density has obvious advantages, and the energy consumption loss is small.
Additional aspects of the utility model will be set forth in part in the description which follows and, in part, will be obvious from the description, or may be learned by practice of the utility model.
Drawings
The accompanying drawings, which are included to provide a further understanding of the utility model and are incorporated in and constitute a part of this specification, illustrate embodiments of the utility model and together with the description serve to explain the utility model.
Fig. 1 is a schematic structural diagram of a nuclear power unit system based on molten salt heat storage coupling in embodiment 1.
Detailed Description
The utility model will be further described with reference to the drawings and examples.
Example 1
The utility model provides a nuclear power unit system based on molten salt heat storage coupling, which comprises a reactor 1, a main coolant pump 2, a steam generator 3, a first valve 4, a turbine high-pressure cylinder 5, a steam-water separator reheater 6, a second valve 7, a turbine low-pressure cylinder 8, a generator 9, a condenser 10, a first circulating water pump 11, a multi-stage low-pressure heater 12, a deaerator 13, a second circulating water pump 14 and a multi-stage high-pressure heater 15, wherein the main coolant pump is arranged in the reactor;
in the nuclear power unit system, a steam outlet of a steam generator 3 is connected with an inlet of a first valve 4, a first outlet of the first valve 4 is connected with an air inlet of a high-pressure cylinder 5 of a steam turbine, an air outlet of the high-pressure cylinder 5 of the steam turbine is connected with an air inlet of a steam-water separator reheater 6 and an inlet of a multistage high-pressure heater 15, an air outlet of the steam-water separator reheater 6 is connected with an air inlet of a second valve 7 and an air inlet of a deaerator 13, the second valve 7 is connected with an air inlet of a low-pressure cylinder 8 of the steam turbine, an air outlet of the low-pressure cylinder 8 of the steam turbine is connected with air inlets of a condenser 10 and a low-pressure heater 12, and the high-pressure cylinder 5 of the steam turbine and the low-pressure cylinder 8 of the steam turbine are connected with a generator 9;
the low-pressure feed water heater 12 is four low-pressure feed water heaters which are sequentially connected in series according to the feed water flow direction, a feed water inlet of the first-stage low-pressure heater 12 is connected with an outlet of the first circulating water pump 11, an inlet of the first circulating water pump 11 is connected with a feed water outlet of the condenser 10, a feed water outlet of the last-stage low-pressure feed water heater 12 is connected with a feed water inlet of the deaerator 13, and steam inlets of all stages of low-pressure feed water heaters 12 are connected with steam outlets of the low-pressure cylinder 8 of the steam turbine;
the high-pressure feed water heater 15 is two high-pressure feed water heaters which are sequentially connected in series according to the feed water flow direction, a feed water inlet of the first-stage high-pressure feed water heater 15 is connected with an outlet of the second circulating water pump 14, and an inlet of the second circulating water pump 14 is connected with a feed water outlet of the deaerator 13; the water supply outlet of the last-stage high-pressure water supply heater 15 is connected with the inlet of the steam generator 3 and the inlet of the deaerator 13, and the steam inlets of the high-pressure heaters 15 of each stage are connected with the steam outlet of the high-pressure cylinder 5 of the steam turbine;
the second outlet of the first valve 4 is connected with the molten salt heat storage system; the molten salt heat storage system comprises a heat exchange subsystem, a heat storage subsystem and a heat release subsystem.
The steam inlet of the heat exchange subsystem is connected with the second outlet of the first valve 4; the steam outlet of the heat exchange subsystem is connected with the inlet of the seventh valve 28; the low-temperature molten salt outlet and the low-temperature molten salt inlet of the molten salt heat storage subsystem are respectively connected with the low-temperature molten salt inlet of the heat exchange subsystem and the low-temperature molten salt outlet of the heat release subsystem; the high-temperature molten salt outlet and the high-temperature molten salt inlet of the molten salt heat storage subsystem are respectively connected with the high-temperature molten salt inlet of the heat release subsystem and the high-temperature molten salt outlet of the heat exchange subsystem; the working medium inlet and the working medium outlet of the heat release subsystem are respectively connected with the fifth valve 26 and the inlet of the high-pressure cylinder 5 of the steam turbine.
Specifically, in the present embodiment, the heat exchange subsystem includes a number of primary steam-molten salt heat exchangers 16;
the heat storage subsystem comprises a low-temperature molten salt storage tank 17, a low-temperature molten salt pump 18, a low-temperature molten salt valve 19, an electric heater 20, a high-temperature molten salt storage tank 21, a high-temperature molten salt pump 22 and a high-temperature molten salt valve 23;
the heat release subsystem comprises a fused salt-feedwater heat exchanger 24, a third circulating water pump 25, a fifth valve 26, a sixth valve 27 and a seventh valve 28;
in the heat exchange subsystem, a steam inlet of the main steam-molten salt heat exchanger 16 is connected with a second outlet of the first valve 4, an inlet of the first valve 4 is connected with a steam outlet of the steam generator 3, a steam outlet of the main steam-molten salt heat exchanger 16 is connected with an inlet of the seventh valve 28, and an outlet of the seventh valve 28 is connected with the condenser 10;
in the molten salt heat storage subsystem, a molten salt outlet of a low-temperature molten salt tank 17 is connected with an inlet of a low-temperature molten salt pump 18, an outlet of the low-temperature molten salt pump 18 is connected with an inlet of a low-temperature molten salt valve 19, and an outlet of the low-temperature molten salt valve 19 is connected with a steam inlet of a main steam-molten salt heat exchanger 16; the steam outlet of the main steam-molten salt heat exchanger 16 is connected with the inlet of the electric heater 20, the outlet of the electric heater 20 is connected with the inlet of the high-temperature molten salt tank 21, and the molten salt outlet of the high-temperature molten salt tank 21 is connected with the high-temperature molten salt inlet of the heat release subsystem through the high-temperature molten salt pumps 22 and 23; the molten salt inlet of the low-temperature molten salt storage tank 17 is connected with the low-temperature molten salt outlet of the heat release subsystem;
in the heat release subsystem, a high-temperature molten salt inlet of the molten salt-water supply heat exchanger 24 is connected with a high-temperature molten salt outlet of the molten salt heat storage subsystem, and a low-temperature molten salt outlet of the molten salt-water supply heat exchanger 24 is connected with a low-temperature molten salt inlet of the molten salt heat storage subsystem; the water supply inlet of the molten salt-water supply heat exchanger 24 is connected with the outlet of a fifth valve 26, the inlet of the fifth valve 26 is connected with the outlet of a third circulating water pump 25, the inlet of the third circulating water pump 25 is connected with the outlet of a seventh valve 28, the steam outlet of the molten salt-water supply heat exchanger (24) is connected with the inlet of a sixth valve 27, and the steam outlet of the sixth valve 27 is connected with the inlet of a high-pressure cylinder 5 of the steam turbine;
in this embodiment, the working process and principle of the nuclear power unit system based on molten salt heat storage coupling are as follows:
when the nuclear power unit needs to reduce load and adjust peak, the power of the reactor is kept unchanged, the steam valve 4 is opened, the flow of main steam is led out through adjusting the opening of the steam adjusting valve 4, part of the main steam led out from the main steam of the steam generator 3 enters the heat exchange subsystem, the low-temperature molten salt valve 19 is opened in the heat exchange subsystem, after heat exchange with the low-temperature molten salt, the electric heater 20 is opened again, the medium-temperature molten salt is heated to high-temperature molten salt, and heat is stored in the high-temperature molten salt storage tank 21 in a high-temperature molten salt mode, so that the purpose of reducing load and adjusting peak is achieved.
When the nuclear power unit needs to raise load and peak regulation, the power of the reactor is kept unchanged, the opening of the water supply valve 26 is adjusted to control the flow of the led water supply, the water supply from the outlet of the condenser 10 enters the heat release subsystem to exchange heat with the high-temperature molten salt, the heat in the molten salt is returned to the nuclear power unit in a mode of raising the water supply temperature to become steam, and the steam flow is controlled by adjusting the opening of the steam valve 27, so that the aim of raising load and peak regulation is fulfilled.
According to the nuclear power unit system based on fused salt heat storage coupling, when the nuclear power unit participates in power grid peak shaving and needs to reduce load, heat or valley electricity is stored in the fused salt heat storage system in a high-temperature fused salt mode by leading out part of main steam from the unit and entering a heat exchange subsystem and a valley electricity heating steam mode; when the unit participates in the peak regulation of the power grid and needs to increase the load, part of water is introduced from the condenser to enter the heat release subsystem, and after heat exchange, heat is returned to the nuclear power unit in the form of steam, so that the load of the nuclear power unit is increased. By adding the fused salt heat storage system, when the nuclear power unit requires low-load operation, the reactor power is unchanged, the loads of the high-pressure cylinder of the steam turbine and the low-pressure cylinder of the steam turbine are reduced, the heat storage medium is used for storing high-grade energy, the peak load regulation range and the flexibility of the nuclear power unit are increased, and the deep peak regulation requirement can be realized; when the nuclear power unit is required to run under high load, the reactor power is unchanged, the high-temperature molten salt is utilized to release heat to heat condensed water to form steam, the steam returns to the nuclear power unit, the load of the steam turbine is improved, the energy utilization efficiency is improved, and the overall efficiency of the unit is improved.
While the foregoing description of the embodiments of the present utility model has been presented in conjunction with the drawings, it should be understood that it is not intended to limit the scope of the utility model, but rather, it is intended to cover all modifications or variations within the scope of the utility model as defined by the claims of the present utility model.
Claims (10)
1. The nuclear power unit system based on molten salt heat storage coupling is characterized by comprising a reactor (1), a steam generator (3), a first valve (4), a steam turbine high-pressure cylinder (5), a steam-water separator reheater (6), a second valve (7), a steam turbine low-pressure cylinder (8) and a condenser (10) which are connected in sequence;
the second outlet of the first valve (4) is connected with a molten salt heat storage system, and the molten salt heat storage system comprises a heat exchange subsystem, a heat storage subsystem and a heat release subsystem;
the steam outlets of the heat exchange subsystem are respectively connected with the high-temperature molten salt inlet of the heat storage subsystem and the steam inlet of the heat release subsystem, the low-temperature molten salt outlet of the heat storage subsystem is connected with the steam inlet of the heat exchange subsystem, the low-temperature molten salt inlet of the heat storage subsystem is connected with the low-temperature molten salt outlet of the heat release subsystem, the high-temperature molten salt outlet of the heat storage subsystem is connected with the high-temperature molten salt inlet of the heat release subsystem, and the steam outlet of the heat release subsystem is connected with the inlet of the high-pressure cylinder (5) of the steam turbine.
2. A nuclear power generating unit system based on molten salt heat storage coupling as claimed in claim 1, wherein the heat exchange subsystem comprises a number of main steam-molten salt heat exchangers (16).
3. A nuclear power unit system based on molten salt heat storage coupling according to claim 1, characterized in that the heat release subsystem comprises a seventh valve (28), a third circulating water pump (25), a fifth valve (26) and a molten salt-feedwater heat exchanger (24) connected in sequence;
the steam outlet of the fused salt-water supply heat exchanger (24) is connected with the inlet of the high-pressure cylinder (5) of the steam turbine through a sixth valve (27);
an inlet of the seventh valve (28) is connected with a steam outlet of the heat exchange subsystem, and an outlet of the seventh valve (28) is also connected with a condenser (10).
4. A nuclear power generating unit system based on molten salt heat storage coupling as claimed in claim 3, wherein the heat storage subsystem comprises a low temperature heat storage module and a high temperature heat storage module, the inlet of the high temperature heat storage module is connected with the steam outlet of the heat exchange subsystem, and the outlet is connected with the high temperature molten salt inlet of the molten salt-water supply heat exchanger (24); and an inlet of the low-temperature heat storage module is connected with a high-temperature molten salt outlet of the molten salt-water supply heat exchanger (24), and an outlet of the low-temperature heat storage module is connected with a steam inlet of the heat exchange subsystem.
5. The nuclear power generating unit system based on molten salt heat storage coupling as claimed in claim 4, wherein the low-temperature heat storage module comprises a low-temperature molten salt storage tank (17), a low-temperature molten salt pump (18) and a low-temperature molten salt valve (19) which are sequentially connected.
6. The nuclear power generating unit system based on molten salt heat storage coupling as claimed in claim 4, wherein the high-temperature heat storage module comprises an electric heater (20), a high-temperature molten salt storage tank (21), a high-temperature molten salt pump (22) and a high-temperature molten salt valve (23) which are sequentially connected.
7. The nuclear power unit system based on molten salt heat storage coupling according to claim 1, further comprising a generator (9), wherein the high-pressure cylinder (5) and the low-pressure cylinder (8) of the steam turbine are connected with the generator (9).
8. The nuclear power unit system based on molten salt heat storage coupling according to claim 1, further comprising a main coolant pump (2), wherein an input end of the main coolant pump (2) is connected with a steam generator (3), and an output end of the main coolant pump is connected with a reactor (1).
9. A nuclear power unit system based on molten salt heat storage coupling according to claim 1, characterized in that it further comprises a low pressure heater (12), a deaerator (13) and a high pressure heater (15);
the steam outlets of the high-pressure cylinder (5) and the low-pressure cylinder (8) of the steam turbine are respectively connected with the steam inlets of the high-pressure heater (15) and the low-pressure heater (12);
the air outlet of the steam-water separator reheater (6) is connected with the air inlet of the deaerator (13);
the water supply inlet of the high-pressure heater (15) is connected with the water supply outlet of the deaerator (13) through a second circulating water pump (14), and the water supply outlet of the high-pressure heater (15) is respectively connected with the water supply inlet of the steam generator (3) and the water supply inlet of the deaerator (13);
the water supply inlet of the low-pressure heater (12) is connected with the outlet of the first circulating water pump (11), the inlet of the first circulating water pump (11) is connected with the water supply outlet of the condenser (10), and the water supply outlet of the low-pressure heater (12) is connected with the water supply inlet of the deaerator (13).
10. The nuclear power unit system based on molten salt heat storage coupling according to claim 9, wherein the high-pressure heater (15) is a multi-stage high-pressure heater, a water supply inlet of the first-stage high-pressure heater (15) is connected with an outlet of a second circulating water pump (14), and an inlet of the second circulating water pump (14) is connected with a water supply outlet of the deaerator (13); the water supply outlet of the last-stage high-pressure heater (15) is connected with the inlet of the steam generator (3) and the inlet of the deaerator (13), and the steam inlets of the high-pressure heaters (15) of each stage are connected with the steam discharge port of the high-pressure cylinder (5) of the steam turbine;
the low-pressure heater (12) is a multi-stage low-pressure heater, a water supply inlet of the first-stage low-pressure heater (12) is connected with an outlet of the first circulating water pump (11), and an inlet of the first circulating water pump (11) is connected with a water supply outlet of the condenser (10); the water supply outlet of the last-stage low-pressure heater (12) is connected with the water supply inlet of the deaerator (13), and the steam inlets of the low-pressure heaters (12) of each stage are all connected with the steam exhaust port of the low-pressure cylinder (8) of the steam turbine.
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| CN202320919044.9U CN220041407U (en) | 2023-04-21 | 2023-04-21 | Nuclear power unit system based on fused salt heat storage coupling |
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| CN202320919044.9U CN220041407U (en) | 2023-04-21 | 2023-04-21 | Nuclear power unit system based on fused salt heat storage coupling |
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