CN111075529B - Brayton cycle power generation system suitable for pulse type fusion reactor - Google Patents
Brayton cycle power generation system suitable for pulse type fusion reactor Download PDFInfo
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- CN111075529B CN111075529B CN201811221211.2A CN201811221211A CN111075529B CN 111075529 B CN111075529 B CN 111075529B CN 201811221211 A CN201811221211 A CN 201811221211A CN 111075529 B CN111075529 B CN 111075529B
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K27/00—Plants for converting heat or fluid energy into mechanical energy, not otherwise provided for
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K25/00—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for
- F01K25/08—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for using special vapours
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
- G21D5/04—Reactor and engine not structurally combined
- G21D5/06—Reactor and engine not structurally combined with engine working medium circulating through reactor core
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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Abstract
The invention belongs to the technical field of fusion reactors, and particularly relates to a Brayton cycle power generation system suitable for a pulse type fusion reactor, wherein a main loop comprises a turbine C-02, a compressor C-01, a fusion reactor, a heat exchanger HX-02, a heat exchanger HX-01 and a pipeline for connecting the devices; the outlet of the compressor C-01 is sequentially connected with the fusion reactor, the primary side of the heat exchanger HX-02 and the primary side of the heat exchanger HX-01 and then connected with the inlet of the turbine C-02, the outlet of the turbine C-02 is connected with the inlet of the compressor C-01 to form a closed loop, the structure is simple to control, the temperature, the flow and the pressure of the inlet of the turbine are stable, and the plasma confinement requirement of a future controllable nuclear fusion reactor can be reduced.
Description
Technical Field
The invention belongs to the technical field of fusion reactors, and particularly relates to a Brayton cycle power generation system suitable for a pulse type fusion reactor.
Background
A fusion reactor nuclear power station is a main power station in the future of human society, and is used for restraining deuterium-tritium plasma through a fusion reaction device to generate controllable fusion so as to generate energy, then the fusion energy in a reactor is taken out to the outside of the reactor through a cooling system, and a turbine or a steam turbine is pushed to do work so as to generate electric power. Unlike fission reactors and thermal power plant boilers, it is very difficult to achieve a sustained and stable fusion reaction based on current fusion technology, and the power generated by fusion devices is pulse-type power. The current fission power station and thermal power station technologies cannot utilize pulse type power to generate continuous and stable electric power.
The Brayton cycle power generation system is an efficient power generation system, is a main research direction of the high-temperature gas cooled reactor at present, and the technology is mature day by day. However, unlike the steady-state heat source provided by fission devices such as high temperature gas cooled reactors, the heat source provided by fusion reactors is pulsed, which presents significant challenges to the steady-state operation of turbines and the stable power generation of systems. In order to solve the problem, a Brayton cycle power generation system suitable for a pulse type fusion reactor is designed, and the system can ensure the steady-state operation of a turbine and stably generate power.
Disclosure of Invention
The invention aims to provide a Brayton cycle power generation system suitable for a pulse type fusion reactor, which can adjust the operation state according to the periodic operation of the heat power generated by the pulse power reactor and ensure that the system generates the electric power with stable power.
The technical scheme of the invention is as follows:
a Brayton cycle power generation system suitable for a pulse type fusion reactor comprises a fusion reactor, two heat exchangers HX-02 and HX-01, a turbine C-02 and a compressor C-01 which are sequentially connected with an outlet of the fusion reactor, and pipelines for connecting the above devices;
the outlet of the fusion reactor is connected with the primary side inlet of the heat exchanger HX-02, the primary side outlet of the heat exchanger HX-02 is connected with the primary side inlet of the heat exchanger HX-01, the primary side outlet of the heat exchanger HX-01 is connected with the inlet of the turbine C-02, the outlet of the turbine C-02 is connected with the inlet of the compressor C-01, and the inlet and the outlet of the compressor C-01 are connected with the inlet of the fusion reactor to form a closed loop.
The system also comprises a temperature control system, wherein the temperature control system comprises a pressure tank TA-01, a high-temperature energy storage container TA-02, a pump PB-01 and a pump PB-02;
an inlet of the pressure tank TA-01 is connected with an outlet of the secondary side of the heat exchanger HX-01, and an outlet of the low-temperature container TA-01 is connected with an inlet of the secondary side of the heat exchanger HX-02;
an inlet of the pressure tank TA-02 is connected with an outlet of the secondary side of the heat exchanger HX-02, and an outlet of the high-temperature container TA-02 is connected with an inlet of the secondary side of the heat exchanger HX-01;
the pump PB-01 is arranged on a pipeline between an outlet of the pressure tank TA-02 and an inlet of the secondary side of the heat exchanger HX-01;
and the pump PB-02 is arranged on a pipeline between the outlet of the pressure tank TA-01 and the inlet of the secondary side of the heat exchanger HX-02.
The temperature control system also comprises a switch valve VG-01 and a switch valve VG-02;
the switch valve VG-01 is arranged on a pipeline between the pump PB-01 and the pressure tank TA-02;
the switch valve VG-02 is arranged on a pipeline between the pump PB-02 and the pressure tank TA-01.
When the outlet of the fusion reactor is a high-temperature outlet, the switch valve VG-01 is closed, the pump PB-01 is closed, the switch valve VG-02 is opened, and the pump PB-02 is opened;
when the outlet of the fusion reactor is a low-temperature outlet, the switch valve VG-02 is closed, the pump PB-02 is closed, the switch valve VG-01 is opened, and the pump PB-01 is opened.
And the coolant introduced into a main loop formed by the fusion reactor, the heat exchanger, the turbine and the compressor is gas.
The gas is helium.
And fluid is introduced into the temperature control system and is liquid metal or salt solution.
The liquid metal is metallic sodium.
The invention has the following remarkable effects:
when the fusion reactor generates heat, the outlet of the primary loop coolant is a high-temperature outlet, the heat generating gap of the fusion reactor is formed, the outlet of the primary loop coolant is a low-temperature outlet, and the system is designed and relevant switch valves are operated, so that the system is switched between two states when the fusion reactor operates.
When the fusion reactor outlet is a high-temperature outlet: high-temperature gas at the outlet of the fusion reactor flows through the primary side of the heat exchanger HX-02, is cooled to the temperature required by the turbine inlet by fluid of a temperature control system in the secondary side of the heat exchanger HX-02, then flows through the primary side of the heat exchanger HX-01, flows to the turbine C-02 to push the turbine to generate electricity, and then is compressed by the compressor C-01 to flow to the inlet of the fusion reactor, so that closed cycle is formed; in the temperature control system, a switch valve VG-01 is closed, a pump PB-01 is closed, a switch valve VG-02 is opened, and a pump PB-02 is opened; the low-temperature fluid sequentially passes through a switch valve VG-02, a pump PB-02 and a heat exchanger HX-02 secondary side from the pressure tank TA-01, then is heated into high-temperature fluid, flows into the pressure tank TA-02 to be stored, and the outlet temperature of the heat exchanger HX-02 primary side is controlled by controlling the rotating speed of the pump PB-02.
When the fusion reactor outlet is a low-temperature outlet: the low-temperature gas at the outlet of the fusion reactor flows through the primary side of a heat exchanger HX-02, then flows through the primary side of a heat exchanger HX-01, is heated to the temperature required by the inlet of a turbine by the fluid of a temperature control system in the secondary side of the heat exchanger HX-0, flows to the C-02 of the turbine to push the turbine to generate electricity, and then is compressed by a compressor C-01 to flow to the inlet of the fusion reactor, so that closed cycle is formed; in the temperature control system, a switch valve VG-02 is closed, a pump PB-02 is closed, a switch valve VG-01 is opened, and a pump PB-01 is opened; high-temperature fluid sequentially passes through a switch valve VG-01, a pump PB-01 and a heat exchanger HX-01 secondary side from a pressure tank TA-02, is cooled into low-temperature fluid, flows into the pressure tank TA-01 and is stored, and the outlet temperature of the heat exchanger HX-01 primary side is controlled by controlling the rotating speed of the pump PB-01.
(1) The system is provided with a temperature control system, so that the temperature of the turbine inlet of the main loop can be effectively stabilized. The device can adapt to the characteristic of power fluctuation of a fusion reactor and can generate continuous and stable electric power;
(3) because the temperature control system arranged by the system can correspondingly adjust according to the fact that the fusion reactor has no thermal power so as to stabilize the temperature of the turbine inlet, the pulse operation of the fusion reactor in the future can also continuously and stably generate electricity. The technical development route of fusion reactor heat power is short-period pulse operation, long-period pulse operation and steady-state operation, and the fusion reactor has the highest technical requirement on stable heat power and is most difficult to realize. The technology can utilize the pulse power of the fusion reactor, so that the technical requirements of a future controllable nuclear fusion reactor can be greatly reduced, and the service time of the controllable fusion technology is greatly advanced;
(4) as the technology adopts the Brayton cycle system, compared with the common pressurized water reactor, the technology has no series of equipment such as a two-loop, a three-loop and the like, thereby saving a large amount of equipment and construction cost. Meanwhile, the system has high power generation efficiency because the fusion reactor outlet coolant (with high temperature and high pressure) is directly utilized to drive the turbine to generate power;
(5) the adopted equipment is the equipment with mature market technology at present and has no manufacturing difficulty.
Drawings
FIG. 1 is a schematic diagram of a Brayton cycle power generation system suitable for a pulse type fusion reactor.
Detailed Description
The invention is further illustrated by the accompanying drawings and the detailed description.
As shown in FIG. 1, the invention provides a Brayton cycle power generation system suitable for a pulse type fusion reactor, which comprises a main loop and a temperature control system;
the main loop is mainly used for taking away the energy in the fusion reactor to a turbine and generating electricity;
the temperature control system is mainly used for controlling the temperature of the turbine inlet;
the main steam generation system comprises a turbine C-02, a compressor C-01, a heat exchanger HX-02, valves and pipelines for connecting the devices.
The temperature control system comprises a pressure tank TA-01, a pressure tank TA-02, a pump TA-01 and a pump TA-02;
a switch valve VG-01 and a switch valve VG-02;
and a pipeline connecting the above devices.
The compressor C-01 is a power source of a helium coolant circulating flow with a main loop of 12MPa, and mainly aims to press the coolant (helium) into the fusion reactor and take out energy in the fusion reactor;
the turbine C-02 is a power source for the rotation of a rotor of the power generation device, and when high-temperature and high-pressure gas (12MPa, 400 ℃ helium gas) at a turbine inlet flows into the turbine C-02, kinetic energy and internal energy of a coolant are converted into kinetic energy of the rotor of the power generator to generate power;
the heat exchanger HX-02 is mainly used for exchanging heat between the coolant on the primary side of the heat exchanger HX-02 and the low-temperature fluid (liquid metal sodium at 350 ℃) in the secondary side of the heat exchanger HX-02 from a temperature control system when the outlet of the fusion reactor is high-temperature coolant (helium at 500 ℃); cooling helium at 500 ℃ on the primary side of the heat exchanger HX-02 to 400 ℃, then flowing the helium to an inlet of a turbine C-02 through the primary side of the heat exchanger HX-01, heating cryogenic fluid (liquid metal sodium at 350 ℃) on the secondary side of the heat exchanger HX-02 to 450 ℃ and flowing the cryogenic fluid into a pressure tank TA-02 for storage;
the heat exchanger HX-01 is mainly used for exchanging heat between a coolant on the primary side of the heat exchanger HX-01 and a high-temperature fluid (liquid metal sodium at 450 ℃) from a temperature control system in the secondary side of the heat exchanger HX-02 when a low-temperature coolant (helium at 300 ℃) is arranged at the outlet of the fusion reactor; the coolant on the primary side of the heat exchanger HX-01 is heated to 400 ℃ and then flows to the inlet of the turbine C-02, and the high-temperature fluid (liquid metal sodium at 450 ℃) on the secondary side of the heat exchanger HX-02 is cooled to 350 ℃ and flows into the pressure tank TA-01 to be stored;
the pump PB-01 is positioned between the pressure tank TA-02 and the heat exchanger HX-01 and is mainly used for providing power required by high-temperature fluid (liquid metal sodium at 450 ℃) flowing out of the pressure tank TA-02 and flowing into the pressure tank TA-01 after passing through the heat exchanger HX-01;
pump PB-02 is located between pressure tank TA-01 and heat exchanger HX-02 and is used primarily to provide the motive force required for cryogenic fluid (liquid sodium metal at 350 ℃) to flow from pressure tank TA-01, through heat exchanger HX-02, and into pressure tank TA-02.
In the fusion nuclear power station, the fusion reactor is operated in a pulse mode, namely the fusion reactor periodically operates alternately between heating power and non-heating power (for example, the fusion reactor has an operation period of 2000s, the first 1000s of heating power and the subsequent 1000s of non-heating power). The working medium used in the pressure tank TA-01 and the pressure tank TA-02 is 0.14MPa liquid metal sodium; the volumes of the pressure tank TA-01 and the pressure tank TA-02 are about 850m3The outer side is coated with a heat insulating material; the pressure tank TA-01 stores low-temperature liquid metal sodium, the working temperature is 250 ℃, and the pressure tank TA-02 stores high-temperature liquid metal sodium, the working temperature is 350 ℃. When the fusion reactor has thermal power, the outlet of the fusion reactor is a high-temperature outlet at 500 ℃, and the inlet of the fusion reactor is stabilized at 300 ℃. When the fusion reactor has no thermal power, the fusion reactor outlet and inlet are both 300 ℃.
When the fusion reactor has thermal power, closing a switch valve VG-01, closing a pump PB-01, opening a switch valve VG-02, opening a pump PB-02, wherein a high-temperature coolant (500 ℃, 12MPa and 200kg/s helium) is arranged at the outlet of the fusion reactor, flows into the primary side of a heat exchanger HX-02 and is cooled to the temperature (400 ℃) required by the inlet of a turbine C-02 by a cold fluid (350 ℃, 800kg/s liquid metal sodium) from a temperature control system at the secondary side of the heat exchanger HX-01, and then flows into the turbine C-02 for power generation by high-temperature and high-pressure helium at 400 ℃; cold fluid (350 ℃, 800kg/s liquid metal sodium) in the secondary side of the heat exchanger HX-02 is heated by high-temperature coolant at the primary side and then flows into the pressure tank TA-02 for storage;
when the fusion reactor has no thermal power, opening a switch valve VG-01, opening a pump PB-01, closing the switch valve VG-02, closing the pump PB-02, wherein a low-temperature coolant (300 ℃, 12MPa, 200kg/s helium) is arranged at the outlet of the fusion reactor, flows into the primary side of a heat exchanger HX-01 after passing through the primary side of the heat exchanger HX-02, is heated to the temperature (400 ℃) required by the inlet of a turbine C-02 by a thermal fluid (450 ℃, 800kg/s liquid metal sodium) from a temperature control system at the secondary side of the heat exchanger HX-01, and then flows into the turbine C-02 to generate electricity; the hot fluid (450 ℃, 800kg/s liquid metal sodium) in the secondary side of the heat exchanger HX-01 is cooled by the primary side cryogenic coolant and then flows into the pressure tank TA-01 for storage.
Claims (7)
1. The utility model provides a brayton cycle power generation system suitable for pulse type fusion reactor which characterized in that: comprises a fusion reactor, two heat exchangers HX-02 and HX-01, a turbine C-02 and a compressor C-01 which are sequentially connected with an outlet of the fusion reactor, and a pipeline for connecting the devices;
the outlet of the fusion reactor is connected with the primary side inlet of a heat exchanger HX-02, the primary side outlet of the heat exchanger HX-02 is connected with the primary side inlet of a heat exchanger HX-01, the primary side outlet of the heat exchanger HX-01 is connected with the inlet of a turbine C-02, the outlet of the turbine C-02 is connected with the inlet of a compressor C-01, and the outlet of the compressor C-01 is connected with the inlet of the fusion reactor to form a closed loop;
the system also comprises a temperature control system, wherein the temperature control system comprises a pressure tank TA-01, a pressure tank TA-02, a pump PB-01 and a pump PB-02;
an inlet of the pressure tank TA-01 is connected with an outlet of the secondary side of the heat exchanger HX-01, and an outlet of the low-temperature container TA-01 is connected with an inlet of the secondary side of the heat exchanger HX-02;
an inlet of the pressure tank TA-02 is connected with an outlet of the secondary side of the heat exchanger HX-02, and an outlet of the pressure tank TA-02 is connected with an inlet of the secondary side of the heat exchanger HX-01;
the pump PB-01 is arranged on a pipeline between an outlet of the pressure tank TA-02 and an inlet of the secondary side of the heat exchanger HX-01;
and the pump PB-02 is arranged on a pipeline between the outlet of the pressure tank TA-01 and the inlet of the secondary side of the heat exchanger HX-02.
2. The brayton cycle power generation system for a pulse type fusion reactor as claimed in claim 1, wherein: the temperature control system also comprises a switch valve VG-01 and a switch valve VG-02;
the switch valve VG-01 is arranged on a pipeline between the pump PB-01 and the pressure tank TA-02;
the switch valve VG-02 is arranged on a pipeline between the pump PB-02 and the pressure tank TA-01.
3. The brayton cycle power generation system for a pulse type fusion reactor as claimed in claim 2, wherein:
when the outlet of the fusion reactor is a high-temperature outlet, the switch valve VG-01 is closed, the pump PB-01 is closed, the switch valve VG-02 is opened, and the pump PB-02 is opened;
when the outlet of the fusion reactor is a low-temperature outlet, the switch valve VG-02 is closed, the pump PB-02 is closed, the switch valve VG-01 is opened, and the pump PB-01 is opened.
4. The brayton cycle power generation system for a pulse type fusion reactor as claimed in claim 1, wherein: and the coolant introduced into a main loop formed by the fusion reactor, the heat exchanger, the turbine and the compressor is gas.
5. The system of claim 4, wherein the gas is helium.
6. The brayton cycle power generation system for a pulse type fusion reactor as claimed in claim 1, wherein: and fluid is introduced into the temperature control system and is liquid metal or salt solution.
7. The system of claim 6, wherein the liquid metal is sodium metal.
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| CN112967826A (en) * | 2021-02-03 | 2021-06-15 | 中国能源建设集团广东省电力设计研究院有限公司 | Oil energy storage decoupling power generation system and method for fusion reactor |
| CN112967827B (en) * | 2021-02-03 | 2022-07-15 | 中国能源建设集团广东省电力设计研究院有限公司 | Fused salt energy storage coupling power generation system and method for fusion reactor |
| CN113012837A (en) * | 2021-02-03 | 2021-06-22 | 中国能源建设集团广东省电力设计研究院有限公司 | Fused salt energy storage decoupling power generation system and method for fusion reactor |
| CN113053544B (en) * | 2021-02-03 | 2022-11-22 | 中国能源建设集团广东省电力设计研究院有限公司 | Oil energy storage coupling power generation system and method for fusion reactor |
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