CN117672559A - Power generation system and method for conducting waste heat export by utilizing supercritical carbon dioxide - Google Patents
Power generation system and method for conducting waste heat export by utilizing supercritical carbon dioxide Download PDFInfo
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- CN117672559A CN117672559A CN202311658417.2A CN202311658417A CN117672559A CN 117672559 A CN117672559 A CN 117672559A CN 202311658417 A CN202311658417 A CN 202311658417A CN 117672559 A CN117672559 A CN 117672559A
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- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 title claims abstract description 204
- 239000001569 carbon dioxide Substances 0.000 title claims abstract description 102
- 229910002092 carbon dioxide Inorganic materials 0.000 title claims abstract description 102
- 239000002918 waste heat Substances 0.000 title claims abstract description 77
- 238000010248 power generation Methods 0.000 title claims abstract description 73
- 238000000034 method Methods 0.000 title claims abstract description 14
- 238000001816 cooling Methods 0.000 claims abstract description 141
- 239000002826 coolant Substances 0.000 claims abstract description 25
- 229910001338 liquidmetal Inorganic materials 0.000 claims description 5
- 150000003839 salts Chemical class 0.000 claims description 5
- 230000005540 biological transmission Effects 0.000 claims description 4
- 238000009795 derivation Methods 0.000 claims description 3
- 230000008859 change Effects 0.000 abstract description 8
- 239000012530 fluid Substances 0.000 abstract description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 11
- 239000007789 gas Substances 0.000 description 7
- 239000000463 material Substances 0.000 description 5
- 230000005611 electricity Effects 0.000 description 4
- 238000000605 extraction Methods 0.000 description 4
- 230000008569 process Effects 0.000 description 4
- 230000008646 thermal stress Effects 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 238000005265 energy consumption Methods 0.000 description 3
- 238000010521 absorption reaction Methods 0.000 description 2
- 230000009471 action Effects 0.000 description 2
- 239000000498 cooling water Substances 0.000 description 2
- 230000002708 enhancing effect Effects 0.000 description 2
- 230000005484 gravity Effects 0.000 description 2
- 230000001172 regenerating effect Effects 0.000 description 2
- 230000001360 synchronised effect Effects 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
- 230000008094 contradictory effect Effects 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 230000035882 stress Effects 0.000 description 1
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
- F01D15/00—Adaptations of machines or engines for special use; Combinations of engines with devices driven thereby
- F01D15/10—Adaptations for driving, or combinations with, electric generators
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
- F01D17/00—Regulating or controlling by varying flow
- F01D17/10—Final actuators
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F25—REFRIGERATION OR COOLING; COMBINED HEATING AND REFRIGERATION SYSTEMS; HEAT PUMP SYSTEMS; MANUFACTURE OR STORAGE OF ICE; LIQUEFACTION SOLIDIFICATION OF GASES
- F25B—REFRIGERATION MACHINES, PLANTS OR SYSTEMS; COMBINED HEATING AND REFRIGERATION SYSTEMS; HEAT PUMP SYSTEMS
- F25B9/00—Compression machines, plants or systems, in which the refrigerant is air or other gas of low boiling point
- F25B9/002—Compression machines, plants or systems, in which the refrigerant is air or other gas of low boiling point characterised by the refrigerant
- F25B9/008—Compression machines, plants or systems, in which the refrigerant is air or other gas of low boiling point characterised by the refrigerant the refrigerant being carbon dioxide
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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
- Y02E30/30—Nuclear fission reactors
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- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- Physics & Mathematics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Thermal Sciences (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Engine Equipment That Uses Special Cycles (AREA)
Abstract
The invention provides a power generation system and a method for conducting waste heat export by utilizing supercritical carbon dioxide, wherein the system comprises a nuclear power generation system and a waste heat export system; the nuclear power generation system includes a reactor; the waste heat guiding-out system comprises a circulating pipeline and a cooling box, wherein a cooling working medium for cooling the reactor is filled in the circulating pipeline, the circulating pipeline passes through the reactor, the circulating pipeline passes through the cooling box, and a coolant for cooling the cooling working medium is arranged in the cooling box; the cooling working medium is supercritical carbon dioxide. The invention uses supercritical carbon dioxide as cooling working medium, the supercritical carbon dioxide is a supercritical fluid, which can avoid the technical problem of reactor safety reduction caused by the reduction of the service life of a reactor pressure vessel by the phase change of the traditional cooling working medium, can replace the traditional passive waste heat leading-out system of the hydraulic working medium reactor, and improves the safety of reactor shutdown.
Description
Technical Field
The invention relates to the technical field of nuclear power generation heat exchange systems, in particular to a power generation system and a method for conducting waste heat export by utilizing supercritical carbon dioxide.
Background
The nuclear power generation system has the advantages of high power density, stable energy, long-term reliable operation, environmental friendliness and the like, so that the nuclear power generation system becomes an important thermoelectric conversion mode in the power generation field, meanwhile, the safety of a nuclear reactor is also attracting attention, and especially the safety derivation of the residual heat of the reactor is related to the integrity of a reactor container and a reactor core structure, and the safety derivation of the residual heat of the reactor core prevents serious accidents.
The cooling working medium of the waste heat leading-out system commonly used in the reactor in the nuclear power generation system is generally water working medium, and the water working medium is used as the cooling working medium, so that the service life of the reactor pressure vessel is reduced, and the safety of the reactor is reduced.
Disclosure of Invention
The invention mainly aims to provide a power generation system and a method for conducting waste heat conduction by using supercritical carbon dioxide, and aims to solve the technical problem that the safety of a reactor is reduced due to the fact that water is used as a cooling working medium in the waste heat conduction system in the existing nuclear power generation system, and the service life of a reactor pressure vessel is shortened.
In order to achieve the above object, the present invention provides a power generation system for performing waste heat removal by using supercritical carbon dioxide, which comprises a nuclear power generation system and a waste heat removal system;
the nuclear power generation system includes a reactor;
the waste heat guiding-out system comprises a circulating pipeline and a cooling box, wherein a cooling working medium for cooling the reactor is filled in the circulating pipeline, the circulating pipeline passes through the reactor, the circulating pipeline passes through the cooling box, and a coolant for cooling the cooling working medium is arranged in the cooling box;
the cooling working medium is supercritical carbon dioxide.
Preferably, the reactor comprises a shell, a heat removal annular cavity is arranged on the side wall of the shell, the circulating pipeline comprises a first pipeline and a second pipeline, one end of the first pipeline is connected with the cooling box, one end of the first pipeline, which is far away from the cooling box, is provided with a branch which is communicated with the upper part of the heat removal annular cavity, one end of the first pipeline, which is far away from the cooling box, is provided with another branch which is communicated with the inlet of the reactor, the bottom of the heat removal annular cavity is communicated with the interior of the reactor, and the outlet of the reactor is communicated with the cooling box through the second pipeline.
Preferably, an intermediate heat exchanger for exchanging heat with the reactor is arranged on the reactor, a cold side and a hot side for exchanging heat are arranged on the intermediate heat exchanger, a core coolant is arranged in the reactor, the intermediate heat exchanger is in contact with the core coolant in the reactor, an inlet of the cold side of the intermediate heat exchanger is communicated with an inlet of the reactor, and an outlet of the cold side of the intermediate heat exchanger is communicated with an outlet of the reactor.
Preferably, the reactor comprises a shell, a heat removal annular cavity is arranged on the side wall of the shell, the circulation pipeline comprises a first pipeline and a second pipeline, one end of the first pipeline is connected with the cooling box, one end of the first pipeline, which is far away from the cooling box, is provided with a branch for being communicated with the upper part of the heat removal annular cavity, one end of the first pipeline, which is far away from the cooling box, is provided with another branch for being communicated with the inlet of the reactor, the outlet of the reactor is communicated with the second pipeline, the outlet of the heat removal annular cavity is communicated with the second pipeline, and the second pipeline is communicated with the cooling box.
Preferably, the nuclear power generation system further comprises a turbine, the reactor is connected with a working medium inlet of the turbine, a working medium outlet of the turbine is connected with a first cooler, the first cooler is connected with a compressor, the compressor is connected with the reactor, and the turbine is connected with a generator in a transmission mode.
Preferably, a first valve is arranged on a connecting pipeline of the reactor and the turbine, a second valve is arranged on a connecting pipeline of the reactor and the compressor, a third valve is arranged on a connecting pipeline of the cooling box and an outlet of the reactor, and a fourth valve is arranged on a connecting pipeline of the cooling box and an inlet of the reactor.
Preferably, the first valve, the second valve, the third valve and the fourth valve are all electric valves.
Preferably, the valve further comprises a UPS power supply, and the first valve, the second valve, the third valve and the fourth valve are all electrically connected with the UPS power supply.
Preferably, valve position sensors for detecting valve position real-time opening signals are arranged on the first valve, the second valve, the third valve and the fourth valve.
Preferably, the system further comprises a regenerator, the turbine is connected with a hot side inlet of the regenerator, a hot side outlet of the regenerator is connected with the first cooler, an outlet of the compressor is connected with a cold side inlet of the regenerator, and a cold side outlet of the regenerator is connected with an inlet of the reactor.
Preferably, the cooling tank is mounted higher than the reactor.
Preferably, a second cooler is arranged in the coolant, and the circulation pipeline passes through the second cooler.
Preferably, a reactor core coolant is arranged in the reactor, and the reactor core coolant is supercritical carbon dioxide, liquid metal or molten salt.
Preferably, the nuclear power generation system is a supercritical carbon dioxide indirect cycle power generation system or a supercritical carbon dioxide direct cycle power generation system.
In addition, the invention also provides a waste heat export method of the power generation system which carries out waste heat export by utilizing supercritical carbon dioxide, which is characterized by comprising the following steps:
the reactor sends a shutdown signal to the UPS;
the UPS power supply controls to close the first valve and the second valve, and the UPS power supply controls to open the third valve and the fourth valve;
the cooling working medium circularly flows in the circulating pipeline, flows through the cooling box for cooling, and then enters the cooling box for cooling after entering the reactor for heat exchange;
the cooling working medium is supercritical carbon dioxide.
The technical scheme adopted in the invention content has the following beneficial effects:
the invention relates to a power generation system and a method for conducting waste heat export by utilizing supercritical carbon dioxide, which uses the supercritical carbon dioxide as a cooling working medium, wherein the supercritical carbon dioxide is a supercritical fluid, is a single-phase fluid state of a special phase state formed after the temperature and the pressure reach a certain state, is in the supercritical state in the operation process of the waste heat export system, does not have a phase change process similar to a water working medium, can avoid the stress and the material change of a reactor pressure vessel caused by the phase change of the water working medium in the common waste heat export system, and improves the service life of the reactor pressure vessel and the safety of reactor shutdown 。
Drawings
Fig. 1 is a schematic diagram showing the composition of a power generation system for waste heat removal using supercritical carbon dioxide according to embodiment 1 of the present invention;
FIG. 2 is a schematic view showing the structure of a reactor in embodiment 1 of the present invention;
fig. 3 is a schematic diagram showing the composition of a power generation system for waste heat removal using supercritical carbon dioxide according to embodiment 2 of the present invention;
FIG. 4 is a schematic view showing the structure of a reactor in embodiment 2 of the present invention;
fig. 5 is a control logic block diagram of a waste heat removal system at shutdown of a power generation system utilizing supercritical carbon dioxide in accordance with the present invention.
The achievement of the objects, functional features and advantages of the present invention will be further described with reference to the accompanying drawings, in conjunction with the embodiments.
Detailed Description
The following description of the embodiments of the present invention will be made clearly and fully with reference to the accompanying drawings, in which it is evident that the embodiments described are only some, but not all embodiments of the invention. All other embodiments, which can be made by those skilled in the art using embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
It should be noted that all directional indicators (such as up, down, left, right, front, and rear … …) in the embodiments of the present invention are merely used to explain the relative positional relationship, movement, etc. between the components in a particular posture (as shown in the drawings), and if the particular posture is changed, the directional indicator is changed accordingly.
In the present invention, unless specifically stated and limited otherwise, the terms "connected," "affixed," and the like are to be construed broadly, and for example, "affixed" may be a fixed connection, a removable connection, or an integral body; can be mechanically or electrically connected; either directly or indirectly, through intermediaries, or both, may be in communication with each other or in interaction with each other, unless expressly defined otherwise. The specific meaning of the above terms in the present invention can be understood by those of ordinary skill in the art according to the specific circumstances.
In addition, if there is a description of "first", "second", etc. in the embodiments of the present invention, the description of "first", "second", etc. is for descriptive purposes only and is not to be construed as indicating or implying a relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defining "a first" or "a second" may explicitly or implicitly include at least one such feature. In addition, the meaning of "and/or" as it appears throughout includes three parallel schemes, for example "A and/or B", including the A scheme, or the B scheme, or the scheme where A and B are satisfied simultaneously. In addition, the technical solutions of the embodiments may be combined with each other, but it is necessary to base that the technical solutions can be realized by those skilled in the art, and when the technical solutions are contradictory or cannot be realized, the combination of the technical solutions should be considered to be absent and not within the scope of protection claimed in the present invention.
The working medium of the passive waste heat leading-out system commonly used in the reactor in the nuclear power generation system is generally water working medium, the passive waste heat leading-out system needs to be provided with a large-capacity cooling water tank, and the cooling process can generate phase change in the reactor container, namely, the cooling water can generate phase change after entering the heat exhausting annular cavity of the reactor, so that the service life of the reactor pressure container can be shortened, and the safety of the reactor is reduced.
The invention provides a supercritical carbon dioxide passive waste heat leading-out system and a supercritical carbon dioxide passive waste heat leading-out method, which utilize supercritical carbon dioxide working medium as cooling working medium and utilize the strong circulation characteristic thereof to realize the safe and low-energy consumption discharge of the waste heat of a reactor core.
Example 1
Referring to fig. 1 to 2, the present invention relates to a power generation system for conducting waste heat export by using supercritical carbon dioxide, which includes a nuclear power generation system and a waste heat export system S02, wherein the nuclear power generation system in this embodiment is a supercritical carbon dioxide direct cycle power generation system S01;
the supercritical carbon dioxide direct cycle power generation system comprises a reactor;
the waste heat guiding-out system comprises a circulating pipeline and a cooling box 8, wherein a cooling working medium for cooling the reactor is filled in the circulating pipeline, the circulating pipeline passes through the reactor 1, the circulating pipeline passes through the cooling box 8, and a coolant for cooling the cooling working medium is arranged in the cooling box 8;
the cooling working medium is supercritical carbon dioxide.
Referring to fig. 1-2, the reactor 1 includes a housing a01, a heat-removal annular cavity a03 is disposed on a side wall of the housing a01, the circulation pipeline includes a first pipeline 12 and a second pipeline 11, one end of the first pipeline 12 is connected with the cooling tank 8, a branch is arranged at one end of the first pipeline 12 far from the cooling tank 8 and is connected with an upper portion of the heat-removal annular cavity a03, another branch is arranged at one end of the first pipeline 12 far from the cooling tank 8 and is connected with an inlet of the reactor 1, a bottom of the heat-removal annular cavity a03 is communicated with an interior of the reactor 1, and an outlet of the reactor 1 is connected with the cooling tank through the second pipeline 11. The reactor contains in-reactor components A02, and the arrow direction in FIG. 2 is the flow direction of supercritical carbon dioxide in the residual heat removal system when in operation.
Referring to fig. 1-2, the supercritical carbon dioxide direct cycle power generation system in this embodiment further includes a turbine 2, the reactor 1 is connected to a working medium inlet of the turbine 2, a working medium outlet of the turbine 2 is connected to a first cooler 5, the first cooler 5 is connected to a compressor 6, the compressor 6 is connected to the reactor 1, and the turbine 2 is in transmission connection with a generator 3. The first valve 1-1 is arranged on the connecting pipeline of the reactor 1 and the turbine 2, the second valve 1-2 is arranged on the connecting pipeline of the reactor 1 and the compressor 6, the third valve 1-3 is arranged on the connecting pipeline of the cooling box 8 and the outlet of the reactor 1, the third valve 1-3 is arranged on the second pipeline 11 in the embodiment, the fourth valve 1-4 is arranged on the connecting pipeline of the cooling box 8 and the inlet of the reactor 1, and the fourth valve in the embodiment is arranged on the first pipeline 12. The embodiment further comprises a UPS power supply 9, wherein the first valve 1-1, the second valve 1-2, the third valve 1-3 and the fourth valve 1-4 are all electric valves, and the first valve, the second valve, the third valve and the fourth valve are all electrically connected with the UPS power supply 9, and the UPS power supply 9 can be connected with the generator 3 to supply power and store energy for the UPS power supply. Valve position sensors for detecting valve position real-time opening signals are arranged on the first valve, the second valve, the third valve and the fourth valve.
Referring to fig. 1-2, the present embodiment further includes a regenerator 4, the turbine 2 is connected to a hot side inlet of the regenerator 4, a hot side outlet of the regenerator 4 is connected to the first cooler 5, an outlet of the compressor 6 is connected to a cold side inlet of the regenerator 4, and a cold side outlet of the regenerator 4 is connected to an inlet of the reactor 1. The cooling box 8 is arranged at a position higher than the reactor 1 to form a closed passive waste heat cooling circulation loop. The coolant is internally provided with a second cooler 7, the circulating pipeline passes through the second cooler 7, and the coolant in the cooling tank 8 is water.
The working flow of the power generation system for conducting waste heat export by utilizing supercritical carbon dioxide comprises the following steps: the high-temperature high-pressure supercritical carbon dioxide working medium flowing out of the reactor 1 enters the turbine 2 to do work to drive the generator 3 to generate electricity, heat energy is converted into electric energy, the exhaust gas after the work is sent into the hot side inlet of the regenerator 4 to preheat the cold side working medium, the exhaust gas is sent into the first cooler 5 to be further cooled, the cooled low-temperature low-pressure carbon dioxide working medium is sent into the compressor 6 to be pressurized, the pressurized low-temperature high-pressure carbon dioxide working medium is sent into the cold side of the regenerator 4 to be preheated, the preheated working medium is sent into the reactor 1 to absorb heat, the high-temperature high-pressure working medium after the heat absorption is sent into the turbine 2 to do work to generate electricity, and the closed supercritical carbon dioxide single-stage regenerative Brayton cycle is completed. The nuclear power generation system in this embodiment may also be a supercritical carbon dioxide brayton cycle of other cycle configurations, such as: the supercritical carbon dioxide recompression brayton cycle, the supercritical carbon dioxide indirect cooling brayton cycle, the supercritical carbon dioxide reheat brayton cycle, and the like.
The invention also relates to a waste heat leading-out method utilizing the system, which comprises the following steps:
the reactor sends a shutdown signal to the UPS;
the UPS power supply controls to close the first valve and the second valve, and the UPS power supply controls to open the third valve and the fourth valve;
the cooling working medium circularly flows in the circulating pipeline, flows through the cooling box for cooling, and then enters the cooling box for cooling after entering the reactor for heat exchange;
the cooling working medium is supercritical carbon dioxide.
The specific flow of the steps is as follows:
when the reactor 1 is shut down and needs to be put into a waste heat leading-out system to realize cooling, a UPS power supply controls to close a first valve 1-1 and a second valve 1-2 and open a third valve 1-3 and a fourth valve 1-4, and supercritical carbon dioxide cooling working medium in the waste heat leading-out system S02 is divided into two branches from a first pipeline 12 to enter the reactor, and one branch is connected into an inlet of the reactor 1 and enters a reactor core; the other branch enters the heat extraction annular cavity A03 of the reactor 1 to realize annular uniform cooling of the reactor shell A01, then the heat extraction annular cavity A01 is converged with the supercritical carbon dioxide cooling working medium at the inlet of the reactor 1 to flow out from the outlet of the reactor, the carbon dioxide working medium heated by the reactor core is heated and boosted, the density of the working medium becomes small, natural circulation buoyancy is formed in a pipeline and rises to the high-position cooling box 8, the heat exchange between the carbon dioxide working medium and water in the cooling box is realized by utilizing the second cooler 7, the cooling of the cooling working medium is realized, the temperature and the pressure of the cooled carbon dioxide working medium are reduced, the density of the working medium is increased, and the working medium enters the reactor 1 to be continuously heated under the action of gravity, so that a closed passive waste heat cooling circulation loop is formed. The invention uses supercritical carbon dioxide as a circulating cooling working medium, utilizes the characteristic of high density difference of the supercritical carbon dioxide to form strong natural circulating waste heat leading-out capability, replaces active waste heat leading-out, greatly reduces the energy consumption during the waste heat leading-out under accident conditions, and can also carry out waste heat leading-out work when a UPS (uninterrupted power supply) control valve is used for realizing power failure and shutdown, thereby greatly enhancing the safety of the system.
In order to further ensure the safety of the system by ensuring the opening and closing conditions of the valves, a corresponding control system can be arranged. Referring to fig. 5, valve position sensors may be disposed on the first valve 1-1, the second valve 1-2, the third valve 1-3 and the fourth valve 1-4, and a valve controller may be disposed, when a reactor shutdown signal is transmitted to a UPS power source, the UPS signal processor in the UPS power source converts the shutdown signal into a valve actuation command signal, the valve actuation command is to close the first valve 1-1 and the second valve 1-2, open the third valve 1-3 and the fourth valve 1-4, the actuation command is transmitted to the valve controller, each valve position sensor transmits a valve position real-time opening signal to a data port while each valve is actuated, the valve controller transmits the actuation command to the data port, the data port is connected with a data processor, the data processor compares whether the actuation command and the valve position real-time opening signal are consistent, so as to compare whether each valve is completely opened according to the actuation command, if not consistent, the valve position real-time opening signal is fed back to the valve controller through the data port, and the valve controller controls each valve to be opened according to the command.
In the embodiment, the supercritical carbon dioxide direct cycle power generation system S01 is matched with the waste heat leading-out system S02, the supercritical carbon dioxide can directly enter a reactor for heat exchange as a cooling working medium, the cooling working medium is the same as the original reactor core coolant, and the problem of introducing a new working medium does not exist. When the reactor is shut down normally or is shut down in an accident, and a waste heat leading-out system is needed to be connected, the supercritical carbon dioxide cooling working medium in the waste heat leading-out system S02 enters the reactor in two branches, so that synchronous cooling of internal components and a reactor cylinder body can be realized, cooling is uniform, the problem of thermal stress and the problem of material fatigue life caused by uneven temperature distribution are avoided, meanwhile, the problem of thermal stress and the problem of material fatigue life caused by phase change of a water working medium are avoided due to the fact that the supercritical carbon dioxide does not exist in the system, the safety of the reactor can be greatly improved, the integrity of the reactor is ensured, and the probability of serious accident occurrence is reduced.
The nuclear power generation system in this embodiment is a supercritical carbon dioxide direct cycle power generation system, and may be other cycle reactors, including a liquid metal reactor, a molten salt reactor, a high-temperature gas cooled reactor, and the like in a fourth generation nuclear reactor power generation system.
Example 2
Referring to fig. 3 to 4, the present invention relates to a power generation system for conducting waste heat export by using supercritical carbon dioxide, which includes a nuclear power generation system and a waste heat export system S04, wherein the nuclear power generation system in this embodiment is a supercritical carbon dioxide indirect cycle power generation system S03;
the supercritical carbon dioxide direct cycle power generation system comprises a reactor;
the waste heat guiding-out system comprises a circulating pipeline and a cooling box 8, wherein a cooling working medium for cooling the reactor is filled in the circulating pipeline, the circulating pipeline passes through the reactor 1, the circulating pipeline passes through the cooling box 8, and a coolant for cooling the cooling working medium is arranged in the cooling box 8;
the cooling working medium is supercritical carbon dioxide.
Referring to fig. 3 to 4, in this embodiment, an intermediate heat exchanger 10 for exchanging heat with the reactor is disposed on the reactor 1, a cold side and a hot side for exchanging heat are disposed on the intermediate heat exchanger 10, a core coolant is disposed in the reactor 1, the intermediate heat exchanger 10 contacts with the core coolant in the reactor, an inlet of the cold side of the intermediate heat exchanger 10 is connected with an inlet of the reactor 1, and an outlet of the cold side of the intermediate heat exchanger 10 is connected with an outlet of the reactor. The reactor 1 comprises a shell A01, a heat removal annular cavity A03 is arranged on the side wall of the shell A01, the circulating pipeline comprises a first pipeline 12 and a second pipeline 11, one end of the first pipeline 12 is connected with the cooling box 8, one end of the first pipeline 12, which is far away from the cooling box, is divided into a branch and communicated with the upper part of the heat removal annular cavity A03, one end of the first pipeline 12, which is far away from the cooling box 8, is divided into another branch and communicated with the inlet of the reactor 1, the outlet of the reactor 1 is communicated with the second pipeline 11, the outlet of the heat removal annular cavity A03 is communicated with the second pipeline 11, and the second pipeline 11 is communicated with the cooling box 8. The presence of the in-reactor component a02 in the reactor, the arrow direction in fig. 4, is the flow direction of the supercritical carbon dioxide therein when the waste heat removal system is in operation.
Referring to fig. 3 to 4, the supercritical carbon dioxide direct cycle power generation system in this embodiment further includes a turbine 2, the reactor 1 is connected to a working medium inlet of the turbine 2, a working medium outlet of the turbine 2 is connected to a first cooler 5, the first cooler 5 is connected to a compressor 6, the compressor 6 is connected to the reactor 1, and the turbine 2 is in transmission connection with a generator 3. The first valve 1-1 is arranged on the connecting pipeline of the reactor 1 and the turbine 2, the second valve 1-2 is arranged on the connecting pipeline of the reactor 1 and the compressor 6, the third valve 1-3 is arranged on the connecting pipeline of the cooling box 8 and the outlet of the reactor 1, the third valve 1-3 is arranged on the second pipeline 11 in the embodiment, the fourth valve 1-4 is arranged on the connecting pipeline of the cooling box 8 and the inlet of the reactor 1, and the fourth valve in the embodiment is arranged on the first pipeline 12. The embodiment further comprises a UPS power supply 9, wherein the first valve 1-1, the second valve 1-2, the third valve 1-3 and the fourth valve 1-4 are all electric valves, and the first valve, the second valve, the third valve and the fourth valve are all electrically connected with the UPS power supply 9, and the UPS power supply 9 can be connected with the generator 3 to supply power and store energy for the UPS power supply. Valve position sensors for detecting valve position real-time opening signals are arranged on the first valve, the second valve, the third valve and the fourth valve.
Referring to fig. 1-2, the present embodiment further includes a regenerator 4, the turbine 2 is connected to a hot side inlet of the regenerator 4, a hot side outlet of the regenerator 4 is connected to the first cooler 5, an outlet of the compressor 6 is connected to a cold side inlet of the regenerator 4, and a cold side outlet of the regenerator 4 is connected to an inlet of the reactor 1. The cooling box 8 is arranged at a position higher than the reactor 1 to form a closed passive waste heat cooling circulation loop. The coolant is internally provided with a second cooler 7, the circulating pipeline passes through the second cooler 7, and the coolant in the cooling tank 8 is water.
The difference of the application of the waste heat leading-out system S04 in this embodiment to the supercritical carbon dioxide indirect cycle power generation system S03 is that, unlike the application of the waste heat leading-out system S03 to the supercritical carbon dioxide direct cycle power generation system, this embodiment provides an intermediate heat exchanger 10 to realize heat exchange with the reactor core coolant in the reactor, and the reactor core coolant is not limited to the supercritical carbon dioxide working medium, and can be liquid metal, molten salt or high-temperature gas, etc., so that the invention can be matched with various reactor types and has a wider application range.
The working flow of the power generation system for conducting waste heat export by utilizing supercritical carbon dioxide comprises the following steps: the high-temperature high-pressure supercritical carbon dioxide working medium flowing out of the reactor 1 enters the turbine 2 to do work to drive the generator 3 to generate electricity, heat energy is converted into electric energy, the exhaust gas after the work is sent into the hot side inlet of the regenerator 4 to preheat the cold side working medium, the exhaust gas is sent into the first cooler 5 to be further cooled, the cooled low-temperature low-pressure carbon dioxide working medium is sent into the compressor 6 to be pressurized, the pressurized low-temperature high-pressure carbon dioxide working medium is sent into the cold side of the regenerator 4 to be preheated, the preheated working medium is sent into the reactor 1 to absorb heat, the high-temperature high-pressure working medium after the heat absorption is sent into the turbine 2 to do work to generate electricity, and the closed supercritical carbon dioxide single-stage regenerative Brayton cycle is completed. The nuclear power generation system in this embodiment may also be a supercritical carbon dioxide brayton cycle of other cycle configurations, such as: the supercritical carbon dioxide recompression brayton cycle, the supercritical carbon dioxide indirect cooling brayton cycle, the supercritical carbon dioxide reheat brayton cycle, and the like.
When the reactor 1 is shut down and needs to be put into a waste heat leading-out system to realize cooling, a UPS power supply controls to close a first valve 1-1 and a second valve 1-2 and open a third valve 1-3 and a fourth valve 1-4, and supercritical carbon dioxide cooling working medium in the waste heat leading-out system S02 is divided into two branches from a first pipeline 12 to enter the reactor, and one branch is connected into an inlet of the reactor 1 and enters a reactor core; the other branch enters the heat extraction annular cavity A03 of the reactor 1 to realize annular uniform cooling of the reactor shell A01, then the heat extraction annular cavity A01 is converged with the supercritical carbon dioxide cooling working medium at the inlet of the reactor 1 to flow out from the outlet of the reactor, the carbon dioxide working medium heated by the reactor core is heated and boosted, the density of the working medium becomes small, natural circulation buoyancy is formed in a pipeline and rises to the high-position cooling box 8, the heat exchange between the carbon dioxide working medium and water in the cooling box is realized by utilizing the second cooler 7, the cooling of the cooling working medium is realized, the temperature and the pressure of the cooled carbon dioxide working medium are reduced, the density of the working medium is increased, and the working medium enters the reactor 1 to be continuously heated under the action of gravity, so that a closed passive waste heat cooling circulation loop is formed. The invention uses supercritical carbon dioxide as a circulating cooling working medium, utilizes the characteristic of high density difference of the supercritical carbon dioxide to form strong natural circulating waste heat leading-out capability, replaces active waste heat leading-out, greatly reduces the energy consumption during the waste heat leading-out under accident conditions, and can also carry out waste heat leading-out work when a UPS (uninterrupted power supply) control valve is used for realizing power failure and shutdown, thereby greatly enhancing the safety of the system.
In order to further ensure the safety of the system by ensuring the opening and closing conditions of the valves, a corresponding control system can be arranged. Referring to fig. 5, valve position sensors may be disposed on the first valve 1-1, the second valve 1-2, the third valve 1-3 and the fourth valve 1-4, and a valve controller may be disposed, when a reactor shutdown signal is transmitted to a UPS power source, the UPS signal processor in the UPS power source converts the shutdown signal into a valve actuation command signal, the valve actuation command is to close the first valve 1-1 and the second valve 1-2, open the third valve 1-3 and the fourth valve 1-4, the actuation command is transmitted to the valve controller, each valve position sensor transmits a valve position real-time opening signal to a data port while each valve is actuated, the valve controller transmits the actuation command to the data port, the data port is connected with a data processor, the data processor compares whether the actuation command and the valve position real-time opening signal are consistent, so as to compare whether each valve is completely opened according to the actuation command, if not consistent, the valve position real-time opening signal is fed back to the valve controller through the data port, and the valve controller controls each valve to be opened according to the command.
In the embodiment, the supercritical carbon dioxide indirect cycle power generation system S03 is matched with the waste heat guide-out system S02, the supercritical carbon dioxide can directly enter a reactor for heat exchange as a cooling working medium, the cooling working medium is the same as the original reactor core coolant, and the problem of introducing a new working medium does not exist. When the reactor is shut down normally or is shut down in an accident, and a waste heat leading-out system is needed to be connected, the supercritical carbon dioxide cooling working medium in the waste heat leading-out system S04 enters the reactor in two branches, so that synchronous cooling of internal components and a reactor cylinder body can be realized, cooling is uniform, the problem of thermal stress and the problem of material fatigue life caused by uneven temperature distribution are avoided, meanwhile, the problem of thermal stress and the problem of material fatigue life caused by phase change of the supercritical carbon dioxide are avoided, the safety of the reactor can be greatly improved, the integrity of the reactor is ensured, and the probability of serious accidents is reduced.
The nuclear power generation system in this embodiment is a supercritical carbon dioxide indirect cycle power generation system, and may be other cycle reactors, including a liquid metal reactor, a molten salt reactor, a high-temperature gas cooled reactor, and the like in a fourth generation nuclear reactor power generation system.
The foregoing description is only of the preferred embodiments of the present invention, and is not intended to limit the scope of the invention, but rather is intended to cover any equivalents of the structures or equivalent processes disclosed herein or in the alternative, which may be employed directly or indirectly in other related arts.
Claims (15)
1. The utility model provides a utilize supercritical carbon dioxide to carry out power generation system of waste heat derivation which characterized in that: the system comprises a nuclear power generation system and a waste heat leading-out system;
the nuclear power generation system includes a reactor;
the waste heat guiding-out system comprises a circulating pipeline and a cooling box, wherein a cooling working medium for cooling the reactor is filled in the circulating pipeline, the circulating pipeline passes through the reactor, the circulating pipeline passes through the cooling box, and a coolant for cooling the cooling working medium is arranged in the cooling box;
the cooling working medium is supercritical carbon dioxide.
2. The power generation system for waste heat removal using supercritical carbon dioxide as claimed in claim 1, wherein: the reactor comprises a shell, a heat removal annular cavity is arranged on the side wall of the shell, the circulating pipeline comprises a first pipeline and a second pipeline, one end of the first pipeline is connected with the cooling box, one end of the first pipeline, which is far away from the cooling box, is provided with a branch pipe which is communicated with the upper part of the heat removal annular cavity, one end of the first pipeline, which is far away from the cooling box, is provided with another branch pipe which is communicated with the inlet of the reactor, the bottom of the heat removal annular cavity is communicated with the interior of the reactor, and the outlet of the reactor is communicated with the cooling box through the second pipeline.
3. The power generation system for waste heat removal using supercritical carbon dioxide as claimed in claim 1, wherein: the reactor is provided with an intermediate heat exchanger for heat exchange of the reactor, the intermediate heat exchanger is provided with a cold side and a hot side for heat exchange, a reactor core coolant is arranged in the reactor, the intermediate heat exchanger is in contact with the reactor core coolant in the reactor, an inlet of the cold side of the intermediate heat exchanger is communicated with an inlet of the reactor, and an outlet of the cold side of the intermediate heat exchanger is communicated with an outlet of the reactor.
4. The power generation system for waste heat removal using supercritical carbon dioxide as claimed in claim 1, wherein: the reactor comprises a shell, a heat removal annular cavity is arranged on the side wall of the shell, the circulating pipeline comprises a first pipeline and a second pipeline, one end of the first pipeline is connected with the cooling box, one end of the first pipeline, which is far away from the cooling box, is provided with a branch pipe which is communicated with the upper part of the heat removal annular cavity, one end of the first pipeline, which is far away from the cooling box, is provided with another branch pipe which is communicated with the inlet of the reactor, the outlet of the reactor is communicated with the second pipeline, the outlet of the heat removal annular cavity is communicated with the second pipeline, and the second pipeline is communicated with the cooling box.
5. The power generation system for waste heat removal using supercritical carbon dioxide as claimed in claim 1, wherein: the nuclear power generation system further comprises a turbine, the reactor is connected with a working medium inlet of the turbine, a working medium outlet of the turbine is connected with a first cooler, the first cooler is connected with a compressor, the compressor is connected with the reactor, and the turbine is connected with a generator in a transmission mode.
6. The power generation system for waste heat removal using supercritical carbon dioxide as claimed in claim 5, wherein: the cooling device comprises a reactor, a compressor, a cooling box, a turbine, a cooling box, a first valve, a second valve, a third valve, a fourth valve and a fourth valve, wherein the first valve is arranged on a connecting pipeline of the reactor and the turbine, the second valve is arranged on a connecting pipeline of the reactor and the compressor, the third valve is arranged on a connecting pipeline of the cooling box and an outlet of the reactor, and the fourth valve is arranged on a connecting pipeline of the cooling box and an inlet of the reactor.
7. The power generation system for waste heat removal using supercritical carbon dioxide as claimed in claim 6, wherein: the first valve, the second valve, the third valve and the fourth valve are all electric valves.
8. The power generation system utilizing supercritical carbon dioxide for waste heat removal as claimed in claim 7, wherein: the valve further comprises a UPS power supply, and the first valve, the second valve, the third valve and the fourth valve are electrically connected with the UPS power supply.
9. The power generation system for waste heat removal using supercritical carbon dioxide as claimed in claim 6, wherein: valve position sensors for detecting valve position real-time opening signals are arranged on the first valve, the second valve, the third valve and the fourth valve.
10. The power generation system for waste heat removal using supercritical carbon dioxide as claimed in claim 5, wherein: the heat exchanger further comprises a heat regenerator, the turbine is connected with a hot side inlet of the heat regenerator, a hot side outlet of the heat regenerator is connected with the first cooler, an outlet of the compressor is connected with a cold side inlet of the heat regenerator, and a cold side outlet of the heat regenerator is connected with an inlet of the reactor.
11. The power generation system for waste heat removal using supercritical carbon dioxide as claimed in claim 1, wherein: the cooling tank is installed at a position higher than the reactor.
12. The power generation system for waste heat removal using supercritical carbon dioxide as claimed in claim 1, wherein: and a second cooler is arranged in the coolant, and the circulating pipeline passes through the second cooler.
13. The power generation system for waste heat removal using supercritical carbon dioxide as claimed in claim 1, wherein: and a reactor core coolant is arranged in the reactor, and the reactor core coolant is supercritical carbon dioxide, liquid metal or molten salt.
14. The power generation system for waste heat removal using supercritical carbon dioxide as claimed in claim 1, wherein: the nuclear power generation system is a supercritical carbon dioxide indirect cycle power generation system or a supercritical carbon dioxide direct cycle power generation system.
15. A waste heat removal method of a power generation system using supercritical carbon dioxide as claimed in claim 8, comprising the steps of:
the reactor sends a shutdown signal to the UPS;
the UPS power supply controls to close the first valve and the second valve, and the UPS power supply controls to open the third valve and the fourth valve;
the cooling working medium circularly flows in the circulating pipeline, flows through the cooling box for cooling, and then enters the cooling box for cooling after entering the reactor for heat exchange;
the cooling working medium is supercritical carbon dioxide.
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