CN111627576A - Power supply system of Stirling power generation nuclear reactor for marine application - Google Patents
Power supply system of Stirling power generation nuclear reactor for marine application Download PDFInfo
- Publication number
- CN111627576A CN111627576A CN202010514636.3A CN202010514636A CN111627576A CN 111627576 A CN111627576 A CN 111627576A CN 202010514636 A CN202010514636 A CN 202010514636A CN 111627576 A CN111627576 A CN 111627576A
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- stirling engine
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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
- F02—COMBUSTION ENGINES; HOT-GAS OR COMBUSTION-PRODUCT ENGINE PLANTS
- F02G—HOT GAS OR COMBUSTION-PRODUCT POSITIVE-DISPLACEMENT ENGINE PLANTS; USE OF WASTE HEAT OF COMBUSTION ENGINES; NOT OTHERWISE PROVIDED FOR
- F02G1/00—Hot gas positive-displacement engine plants
- F02G1/04—Hot gas positive-displacement engine plants of closed-cycle type
- F02G1/043—Hot gas positive-displacement engine plants of closed-cycle type the engine being operated by expansion and contraction of a mass of working gas which is heated and cooled in one of a plurality of constantly communicating expansible chambers, e.g. Stirling cycle type engines
- F02G1/0435—Hot gas positive-displacement engine plants of closed-cycle type the engine being operated by expansion and contraction of a mass of working gas which is heated and cooled in one of a plurality of constantly communicating expansible chambers, e.g. Stirling cycle type engines the engine being of the free piston type
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F02—COMBUSTION ENGINES; HOT-GAS OR COMBUSTION-PRODUCT ENGINE PLANTS
- F02G—HOT GAS OR COMBUSTION-PRODUCT POSITIVE-DISPLACEMENT ENGINE PLANTS; USE OF WASTE HEAT OF COMBUSTION ENGINES; NOT OTHERWISE PROVIDED FOR
- F02G1/00—Hot gas positive-displacement engine plants
- F02G1/04—Hot gas positive-displacement engine plants of closed-cycle type
- F02G1/043—Hot gas positive-displacement engine plants of closed-cycle type the engine being operated by expansion and contraction of a mass of working gas which is heated and cooled in one of a plurality of constantly communicating expansible chambers, e.g. Stirling cycle type engines
- F02G1/053—Component parts or details
- F02G1/055—Heaters or coolers
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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
- G21C15/14—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
-
- 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
- G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
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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
- G21D5/08—Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
- G21D5/12—Liquid working medium vaporised by reactor coolant
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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
-
- 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)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Combustion & Propulsion (AREA)
- Mechanical Engineering (AREA)
- Engine Equipment That Uses Special Cycles (AREA)
Abstract
The invention discloses a power supply system of a marine application Stirling power generation nuclear reactor, which belongs to the technical field of nuclear reactor engineering and comprises a reactor core, a heat conduction heat pipe, a Stirling engine, a heat dissipation heat pipe, a pressure-resistant shell and a protective container; the reactor core and the Stirling engine are correspondingly arranged and are arranged in the pressure-resistant shell; the outer side of the reactor core is coated with a shielding layer; the heat conduction heat pipe is divided into an evaporation end and a condensation end, the part of the heat conduction heat pipe inserted into the reactor core through the shielding layer is set as the evaporation end, and the part of the heat end inserted into the Stirling engine is set as the condensation end; the heat dissipation heat pipe is arranged between the cold end of the Stirling engine and the pressure-resistant shell; the protective container is sleeved outside the pressure-resistant shell to form an annular flow passage, the top end of the protective container is provided with a seawater outlet, and the seawater outlet is communicated with the annular flow passage. The nuclear reactor power supply system is applied to marine environment and can provide long-term underwater power supply, and can improve the research and development level of deep and open sea equipment and shorten the development period.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor engineering, and particularly relates to a power supply system of a marine Stirling power generation nuclear reactor.
Background
China is vast in breadth, ocean resources are particularly rich, but with the ocean strategy of China gradually going from shallow sea to deep sea, the increase of energy demand and the limitation of the existing energy in the deep sea environment become important factors influencing the development of ocean equipment in China. The nuclear fission does not need oxygen, has high energy density, can run for a long time, and is an ideal energy source choice for deep sea and deep space exploration. At present, various small-sized reactor design schemes are proposed at home and abroad aiming at space application, but relevant research is still few aiming at small-sized nuclear power systems used in marine application, particularly in deep sea environment.
The Stirling engine outputs power through a cycle of cooling, compressing, absorbing heat and expanding a working medium (hydrogen or helium) in a cylinder, and the efficiency of energy conversion can reach more than 30%. Further, the stirling engine is an external combustion engine, and can use various fuels as energy sources, such as plant waste heat, geothermal heat, solar energy, nuclear energy, and the like.
According to the application characteristics of the marine environment, the nuclear energy and the efficient energy conversion system of the Stirling heat engine are combined, and the power generation system can provide long-time power supply for deep sea equipment.
Disclosure of Invention
The invention provides a power generation system which can be used for providing long-time power supply for deep sea equipment according to the application characteristics of marine environment and a high-efficiency energy conversion system combining nuclear energy and a Stirling heat engine.
In order to achieve the purpose, the invention adopts the technical scheme that:
a nuclear reactor power supply system for marine application Stirling power generation comprises a reactor core, a heat conduction heat pipe, a Stirling engine, a heat dissipation heat pipe, a pressure-resistant shell and a protection container;
the reactor core and the Stirling engine are correspondingly arranged and are arranged in the pressure-resistant shell;
the outer side of the reactor core is coated with a shielding layer for protecting the Stirling engine and the marine environment from radiation damage of the reactor core;
the heat conduction heat pipe is divided into an evaporation end and a condensation end, the part of the heat conduction heat pipe penetrating through the shielding layer and inserted into the reactor core is set as the evaporation end, and the part of the heat end inserted into the Stirling engine is set as the condensation end and is used for transferring heat generated by the reactor core to the Stirling engine;
the heat dissipation heat pipe is arranged between the cold end of the Stirling engine and the pressure-resistant shell and used for guiding heat of the cold end of the Stirling engine to the wall surface of the pressure-resistant shell so as to ensure that the temperature of the cold end of the Stirling engine is constant;
the protective container is sleeved on the outer side of the pressure-resistant shell and forms an annular flow passage, a seawater outlet is formed in the top end of the protective container, and the seawater outlet is communicated with the annular flow passage.
Furthermore, a radiating fin is arranged in the annular flow passage, and the radiating fin divides the annular flow passage into a plurality of independent flow passages and is used for improving the natural circulation capacity of seawater and increasing the heat exchange area of the wall surface of the pressure shell.
Further, the number and the arrangement mode of the radiating fins are determined according to the maximum power of the reactor core, the energy conversion efficiency of the Stirling engine, the working temperature of the radiating heat pipes and the temperature of the seawater.
Further, the reactor core is a heat pipe cooling fast neutron reactor; the reactor core comprises reactor core fuel, and the reactor core fuel adopts uranium nitride.
Furthermore, the working medium in the heat conduction heat pipe is liquid metal sodium.
Furthermore, the Stirling engine is a free piston type Stirling engine, the operating working medium of the Stirling engine is helium, and the piston is pushed to drive the generator to generate electricity by the aid of repeated change of the volume of the helium along with temperature in the working process.
Furthermore, the working medium of the heat dissipation heat pipe is potassium.
Further, the height of the seawater outlet conduit is calculated from the cooling seawater or the air flow rate.
Further, the nuclear reactor power system may provide a power supply on the order of 10kW for providing power for marine exploration activities.
The invention has the beneficial effects that:
1. the invention provides a nuclear reactor power supply system which is applied to a marine environment and can provide long-term underwater power supply, and can improve the research and development level of deep and open sea equipment and shorten the development period;
2. the free piston Stirling heat engine and the heat pipe cooling reactor are combined, so that the energy density is high, the running time is long, the thermoelectric conversion efficiency is high, the free piston Stirling heat engine can autonomously work in a marine environment, and the free piston Stirling heat engine has a wide application prospect;
3. according to the invention, the reactor and the thermoelectric conversion system are sealed in the pressure-resistant shell, waste heat or reactor core decay heat is led out by utilizing seawater which naturally circulates outside the pressure-resistant shell, the reactor is not limited by ocean conditions, and the reactor has higher inherent safety.
Drawings
FIG. 1 is a schematic diagram of the present invention of a marine application Stirling power nuclear reactor power system layout;
fig. 2 is a schematic view of a heat dissipation fin structure according to the present invention.
Wherein, 1, a reactor core; 2. a heat conducting heat pipe; 3. a stirling engine; 4. a heat-dissipating heat pipe; 5. a pressure-resistant housing; 6. a protective container; 7. a seawater inlet; 8. a seawater outlet; 9. a heat dissipating fin; 10. core fuel; 11. and a shielding layer.
Detailed Description
The invention provides a power supply system of a Stirling power generation nuclear reactor for marine application. The technical solution of the present invention is described in detail below with reference to the accompanying drawings so that it can be more easily understood and appreciated.
Example 1
A nuclear reactor power supply system (as shown in figure 1) for marine application Stirling power generation comprises a reactor core 1, a heat-conducting heat pipe 2, a Stirling engine 3, a heat-radiating heat pipe 4, a pressure-resistant shell 5 and a protective container 6;
the reactor core 1 and the Stirling engine 3 are correspondingly arranged and are arranged in the pressure-resistant shell 5;
the outer side of the reactor core 1 is coated with a shielding layer 11 for protecting the Stirling engine 3 and the marine environment from radiation damage of the reactor core 1;
the heat conduction heat pipe 2 is divided into an evaporation end and a condensation end, the part of the heat conduction heat pipe 2, which penetrates through the shielding layer 11 and is inserted into the reactor core 1, is set as the evaporation end, and the part of the heat end, which is inserted into the Stirling engine 3, is set as the condensation end, and is used for transferring heat generated by the reactor core 1 to the Stirling engine 3;
the heat dissipation heat pipe 4 is arranged between the cold end of the Stirling engine 3 and the pressure-resistant shell 5 and used for guiding heat at the cold end of the Stirling engine 3 to the wall surface of the pressure-resistant shell 5 so as to ensure that the temperature of the cold end of the Stirling engine 3 is constant;
and the annular flow channel is internally provided with a radiating fin 9, and the radiating fin 9 divides the annular flow channel into a plurality of independent flow channels for improving the natural circulation capacity of seawater and increasing the heat exchange area of the wall surface of the pressure shell 5.
The number and the arrangement mode of the radiating fins 9 are determined according to the maximum power of the reactor core 1, the energy conversion efficiency of the Stirling engine 3, the working temperature of the radiating heat pipes 4 and the temperature of the seawater.
In the embodiment, the reactor core 1 is a heat pipe cooling fast neutron reactor; the core 1 comprises core fuel 10, and the core fuel 10 adopts uranium nitride.
The Stirling engine 3 is a free piston type Stirling engine, the operating working medium of the Stirling engine is helium, and the volume of the helium is repeatedly changed along with the temperature in the working process to push a piston and drive a generator to generate electricity.
In this embodiment, the working medium in the heat conducting heat pipe 2 is liquid metal sodium, the working temperature is 900-. The heat-conducting heat pipe 2 and the heat-radiating heat pipe 4 are matched to operate, and a stable temperature difference can be formed between the hot end of the Stirling engine 3 and the condensation.
The protective container 6 is sleeved outside the pressure shell 5 and forms an annular flow passage (as shown in fig. 2), a seawater outlet 8 is arranged at the top end of the protective container 6, and the seawater outlet 8 is communicated with the annular flow passage. Wherein, seawater enters from a seawater inlet 7 at the bottom, is heated by the wall surface of the pressure-resistant shell 5, and then rises in temperature to form a natural circulation flow driving pressure head, and flows out from a seawater outlet 8 at the top of the protective container 6; the height of the seawater outlet 8 pipe is calculated from the cooling seawater or air flow.
When the reactor power supply system works normally, the reactor power supply system is completely immersed in seawater, and the wall surface of the pressure-resistant shell 5 is cooled by the seawater to lead out waste heat; after the nuclear reactor is shut down, the wall surface of the pressure casing 5 may be cooled by seawater or natural convection of air to lead out the core decay heat.
The nuclear reactor power supply system provided by the embodiment can provide power supply of 10kW level and provide power for ocean exploration activities.
The working principle of the embodiment is as follows:
the nuclear fuel in the reactor core 1 generates heat through nuclear fission reaction, the temperature of the reactor is increased, after the heat conduction heat pipe 2 is heated, the internal working medium is evaporated and absorbs heat to be changed into sodium vapor, the sodium vapor flows to the hot end of the Stirling engine 3 to be condensed, and the liquid sodium flows back into the reactor core 1 again to absorb heat. Therefore, the heat conducting heat pipe 2 continuously transfers the heat of the reactor core to the hot end of the Stirling heat engine 3, and the heat radiating heat pipe 4 continuously transfers the heat of the cold end to the wall surface of the pressure vessel and leads the heat out of the environment through the natural circulation of seawater outside the wall surface. The working medium in the Stirling heat engine is continuously heated, expanded or cooled and contracted to push the piston to do work, and the piston pushes the generator to generate electricity. The seawater naturally circulates and flows through an annular flow passage between the pressure-resistant shell 5 and the protective container 6, the pressure-resistant shell 5 is cooled, and the heated temperature of the seawater rises and flows out from a seawater outlet 8.
The technical solutions of the present invention are fully described above, it should be noted that the specific embodiments of the present invention are not limited by the above description, and all technical solutions formed by equivalent or equivalent changes in structure, method, or function according to the spirit of the present invention by those skilled in the art are within the scope of the present invention.
Claims (9)
1. A nuclear reactor power system for stirling power generation for marine applications, comprising: the reactor core comprises a reactor core (1), a heat-conducting heat pipe (2), a Stirling engine (3), a heat-radiating heat pipe (4), a pressure-resistant shell (5) and a protective container (6);
the reactor core (1) and the Stirling engine (3) are arranged correspondingly and arranged in the pressure casing (5);
the outer side of the reactor core (1) is coated with a shielding layer (11) for protecting the Stirling engine (3) and the marine environment from radiation damage of the reactor core (1);
the heat-conducting heat pipe (2) is divided into an evaporation end and a condensation end, the heat-conducting heat pipe (2) penetrates through the shielding layer (11) and is inserted into the inner part of the reactor core (1) to be set as the evaporation end, and the hot end part inserted into the Stirling engine (3) is set as the condensation end and is used for transferring heat generated by the reactor core (1) to the Stirling engine (3);
the heat dissipation heat pipe (4) is arranged between the cold end of the Stirling engine (3) and the pressure-resistant shell (5) and used for guiding heat at the cold end of the Stirling engine (3) to the wall surface of the pressure-resistant shell (5) so as to ensure that the temperature of the cold end of the Stirling engine (3) is constant;
the protective container (6) is sleeved on the outer side of the pressure shell (5) and forms an annular flow passage, a seawater outlet (8) is formed in the top end of the protective container (6), and the seawater outlet (8) is communicated with the annular flow passage.
2. A stirling power generating nuclear reactor power supply system for marine applications according to claim 1, wherein heat dissipating fins (9) are provided in the annular flow passage, and the heat dissipating fins (9) divide the annular flow passage into a plurality of independent flow passages for improving natural circulation of seawater and increasing the heat exchange area of the pressure casing (5) wall surface.
3. A marine stirling power generating nuclear reactor power system according to claim 2, wherein the number and arrangement of the heat dissipating fins (9) is determined by the maximum power of the core (1), the stirling engine (3) energy conversion efficiency, the operating temperature of the heat dissipating heat pipes (4) and the seawater temperature.
4. A marine application stirling power generating nuclear reactor power system according to claim 1 wherein the core (1) is a heat pipe cooled fast neutron reactor; the reactor core (1) comprises reactor core fuel (10), and the reactor core fuel (10) adopts uranium nitride.
5. A marine application stirling power generating nuclear reactor power supply system according to claim 1, characterised in that the working fluid in the heat conducting heat pipe (2) is liquid metal sodium.
6. A stirling nuclear power reactor power supply system for marine applications according to claim 1, wherein the stirling engine (3) is a free piston stirling engine, the operating medium of which is helium, and the volume of the helium repeatedly changes with temperature during operation to drive the piston to drive the generator to generate electricity.
7. A marine application stirling power generating nuclear reactor power supply system according to claim 1, characterised in that the working fluid of the heat-dissipating heat pipes (4) is potassium.
8. A marine application stirling power generating nuclear reactor power supply system according to claim 1, wherein the height of the seawater outlet (8) conduit is calculated from the cooling seawater or air flow.
9. A marine application stirling power generating nuclear reactor power system according to claim 1 wherein the nuclear reactor power system is capable of providing a power supply on the order of 10kW for providing power for marine exploration activities.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010514636.3A CN111627576A (en) | 2020-06-08 | 2020-06-08 | Power supply system of Stirling power generation nuclear reactor for marine application |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010514636.3A CN111627576A (en) | 2020-06-08 | 2020-06-08 | Power supply system of Stirling power generation nuclear reactor for marine application |
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| CN111627576A true CN111627576A (en) | 2020-09-04 |
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| CN202010514636.3A Pending CN111627576A (en) | 2020-06-08 | 2020-06-08 | Power supply system of Stirling power generation nuclear reactor for marine application |
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Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112331369A (en) * | 2020-11-21 | 2021-02-05 | 西安交通大学 | Ocean silent type heat pipe reactor power system |
| CN112885494A (en) * | 2021-01-26 | 2021-06-01 | 哈尔滨工程大学 | Reactor power supply system based on star-type Stirling engine |
| CN112943477A (en) * | 2021-03-24 | 2021-06-11 | 西安交通大学 | Novel compact space nuclear reactor power supply |
| CN113047949A (en) * | 2021-03-12 | 2021-06-29 | 哈尔滨工程大学 | Split-cylinder free piston generator based on PID closed-loop control |
| CN113217222A (en) * | 2021-04-12 | 2021-08-06 | 中国原子能科学研究院 | Stirling engine system for coupling liquid metal cooling reactor |
| CN113593734A (en) * | 2021-07-27 | 2021-11-02 | 西安交通大学 | Motor-driven micro-miniature nuclear power system |
| CN114121315A (en) * | 2021-11-12 | 2022-03-01 | 西安交通大学 | Heat management system for cooling reactor by pulsating heat pipe |
| CN115206569A (en) * | 2022-08-02 | 2022-10-18 | 哈尔滨工程大学 | Nuclear reactor dual-mode energy conversion system for underwater unmanned vehicle |
| CN116230261A (en) * | 2023-02-14 | 2023-06-06 | 上海交通大学 | Power supply system suitable for miniature ocean reactor |
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| US20180033501A1 (en) * | 2016-08-01 | 2018-02-01 | Kabushiki Kaisha Toshiba | Nuclear reactor and a method of heat transfer from a core |
| CN109147966A (en) * | 2018-09-06 | 2019-01-04 | 中国原子能科学研究院 | A kind of heat-pipe cooling type nuclear reactor power-supply system based on uranium hydrogen yttrium fuel and dynamic heat to electricity conversion |
| CN110739090A (en) * | 2019-10-14 | 2020-01-31 | 哈尔滨工程大学 | passive waste heat removal system of heat pipe stack cooled by wall surface of pressure container |
| CN110853786A (en) * | 2019-11-08 | 2020-02-28 | 西安交通大学 | Spherical self-expanding nuclear reactor power supply used on surface of planet |
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| US20180033501A1 (en) * | 2016-08-01 | 2018-02-01 | Kabushiki Kaisha Toshiba | Nuclear reactor and a method of heat transfer from a core |
| CN109147966A (en) * | 2018-09-06 | 2019-01-04 | 中国原子能科学研究院 | A kind of heat-pipe cooling type nuclear reactor power-supply system based on uranium hydrogen yttrium fuel and dynamic heat to electricity conversion |
| CN110739090A (en) * | 2019-10-14 | 2020-01-31 | 哈尔滨工程大学 | passive waste heat removal system of heat pipe stack cooled by wall surface of pressure container |
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Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112331369A (en) * | 2020-11-21 | 2021-02-05 | 西安交通大学 | Ocean silent type heat pipe reactor power system |
| CN112885494A (en) * | 2021-01-26 | 2021-06-01 | 哈尔滨工程大学 | Reactor power supply system based on star-type Stirling engine |
| CN112885494B (en) * | 2021-01-26 | 2022-08-02 | 哈尔滨工程大学 | Reactor power supply system based on star-type Stirling engine |
| CN113047949A (en) * | 2021-03-12 | 2021-06-29 | 哈尔滨工程大学 | Split-cylinder free piston generator based on PID closed-loop control |
| CN113047949B (en) * | 2021-03-12 | 2021-09-21 | 哈尔滨工程大学 | Split-cylinder free piston generator based on PID closed-loop control |
| CN112943477A (en) * | 2021-03-24 | 2021-06-11 | 西安交通大学 | Novel compact space nuclear reactor power supply |
| CN113217222A (en) * | 2021-04-12 | 2021-08-06 | 中国原子能科学研究院 | Stirling engine system for coupling liquid metal cooling reactor |
| CN113593734A (en) * | 2021-07-27 | 2021-11-02 | 西安交通大学 | Motor-driven micro-miniature nuclear power system |
| CN114121315A (en) * | 2021-11-12 | 2022-03-01 | 西安交通大学 | Heat management system for cooling reactor by pulsating heat pipe |
| CN115206569A (en) * | 2022-08-02 | 2022-10-18 | 哈尔滨工程大学 | Nuclear reactor dual-mode energy conversion system for underwater unmanned vehicle |
| CN116230261A (en) * | 2023-02-14 | 2023-06-06 | 上海交通大学 | Power supply system suitable for miniature ocean reactor |
| CN116230261B (en) * | 2023-02-14 | 2024-04-26 | 上海交通大学 | Power supply system suitable for miniature ocean reactor |
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Application publication date: 20200904 |