CN111785397A - Nuclear power device based on heat pipe type reactor and using method - Google Patents
Nuclear power device based on heat pipe type reactor and using method Download PDFInfo
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- CN111785397A CN111785397A CN202010695572.1A CN202010695572A CN111785397A CN 111785397 A CN111785397 A CN 111785397A CN 202010695572 A CN202010695572 A CN 202010695572A CN 111785397 A CN111785397 A CN 111785397A
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- 238000000034 method Methods 0.000 title abstract description 9
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Chemical compound O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 99
- 239000000498 cooling water Substances 0.000 claims description 10
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 claims description 5
- 229910052708 sodium Inorganic materials 0.000 claims description 5
- 239000011734 sodium Substances 0.000 claims description 5
- WHXSMMKQMYFTQS-UHFFFAOYSA-N Lithium Chemical compound [Li] WHXSMMKQMYFTQS-UHFFFAOYSA-N 0.000 claims description 3
- 229910001182 Mo alloy Inorganic materials 0.000 claims description 3
- ZLMJMSJWJFRBEC-UHFFFAOYSA-N Potassium Chemical compound [K] ZLMJMSJWJFRBEC-UHFFFAOYSA-N 0.000 claims description 3
- 229910052770 Uranium Inorganic materials 0.000 claims description 3
- MVXWAZXVYXTENN-UHFFFAOYSA-N azanylidyneuranium Chemical compound [U]#N MVXWAZXVYXTENN-UHFFFAOYSA-N 0.000 claims description 3
- 239000000446 fuel Substances 0.000 claims description 3
- 238000010438 heat treatment Methods 0.000 claims description 3
- 229910052744 lithium Inorganic materials 0.000 claims description 3
- KTEXACXVPZFITO-UHFFFAOYSA-N molybdenum uranium Chemical compound [Mo].[U] KTEXACXVPZFITO-UHFFFAOYSA-N 0.000 claims description 3
- OOAWCECZEHPMBX-UHFFFAOYSA-N oxygen(2-);uranium(4+) Chemical compound [O-2].[O-2].[U+4] OOAWCECZEHPMBX-UHFFFAOYSA-N 0.000 claims description 3
- 229910052700 potassium Inorganic materials 0.000 claims description 3
- 239000011591 potassium Substances 0.000 claims description 3
- FCTBKIHDJGHPPO-UHFFFAOYSA-N uranium dioxide Inorganic materials O=[U]=O FCTBKIHDJGHPPO-UHFFFAOYSA-N 0.000 claims description 3
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims description 3
- 238000001816 cooling Methods 0.000 claims description 2
- 238000012423 maintenance Methods 0.000 abstract description 8
- 238000006243 chemical reaction Methods 0.000 abstract description 5
- 239000007789 gas Substances 0.000 description 8
- 239000007788 liquid Substances 0.000 description 3
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 229910052783 alkali metal Inorganic materials 0.000 description 1
- 150000001340 alkali metals Chemical class 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 229910002092 carbon dioxide Inorganic materials 0.000 description 1
- 239000001569 carbon dioxide Substances 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000007599 discharging Methods 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000002360 explosive Substances 0.000 description 1
- JEGUKCSWCFPDGT-UHFFFAOYSA-N h2o hydrate Chemical compound O.O JEGUKCSWCFPDGT-UHFFFAOYSA-N 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 125000004435 hydrogen atom Chemical class [H]* 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/006—Details of nuclear power plant primary side of steam generators
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
-
- 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
-
- 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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Engine Equipment That Uses Special Cycles (AREA)
Abstract
The invention discloses a nuclear power device based on a heat pipe type reactor and a using method thereof, wherein the device comprises: the reactor core of the heat pipe type reactor, heat pipes, a heat pipe exchanger and a water vapor circulation system, wherein one end of each heat pipe is connected with the reactor core of the heat pipe type reactor, the other end of each heat pipe is connected with the heat pipe exchanger, and the heat pipe exchanger is connected with the water vapor circulation system; the use method of the device comprises the following steps: the heat pipe passively loads heat energy generated by the core of the heat pipe type reactor into the heat pipe heat exchanger, water vapor in the heat pipe heat exchanger absorbs heat and is heated, and the heated water vapor enters the water vapor circulation system to perform energy circulation exchange. The nuclear power device based on the heat pipe type reactor has the advantages of simple structure, safety, reliability, simpler operation and maintenance, small volume, mobility and the like, realizes the conversion from heat energy to electric energy, can be used as a mobile nuclear power source or a nuclear power device applied to most occasions, and has wide application prospect.
Description
Technical Field
The invention belongs to the field of nuclear power, and particularly relates to a nuclear power device based on a heat pipe type reactor and a using method thereof.
Background
The energy is a cornerstone for social development, and nuclear energy plays an increasingly important role in the energy structure of China due to the characteristics of high energy density, sustainability, stability, cleanness and the like. At present, the nuclear power technology of large pressurized water reactors is mature and has a great proportion in energy structures in China and even the world, but the development of movable nuclear power sources and nuclear power devices applied to sea, land and air, such as ship-borne, vehicle-borne and airborne innovative small nuclear reactors, is yet to be researched to meet the requirements of social and economic development.
The movable nuclear power supply and the nuclear power device applied to sea, land and air have the characteristics of safety, light weight, compactness, simplicity, reliability, swing resistance and the like. The nuclear power plant of the traditional nuclear power plant adopts a pressurized water reactor and steam Rankine cycle system, and the device has the problems of complex equipment structure, low cycle efficiency, high vibration noise and difficult operation and maintenance, and in addition, has the potential risks of accidents such as loss of water and flow of a primary loop coolant and the like, and needs to specially arrange nuclear safety auxiliary facilities, so that the nuclear power plant has the disadvantages of complex structure, low safety and reliability and difficult operation and maintenance; the novel underwater nuclear power device adopts a lead-based reactor and supercritical carbon dioxide circulation system, the device has the problems of difficult equipment maintenance caused by virulent Po-210, corrosive lead-based reactor materials and the like, the melting point of lead in the lead-based reactor is high, corresponding functional modules are required to be added into the device in order to maintain the unfreezing and liquid states of the reactor, the complexity of the device is increased, and the maintenance work is complicated; in addition, a nuclear power device adopts a system of 'sodium-cooled fast reactor + steam Rankine cycle', metal needs to be unfrozen when a reactor is started, the risk that sodium on the secondary side reacts with water is high, the sodium reacts with the water violently to generate explosive gas hydrogen, and the reactor does not have inherent safety characteristics; in addition, the volume and the mass of the conventional nuclear power device are large, so that the nuclear power device is inconvenient to move. The above problems limit the application of marine, land and air nuclear power sources and nuclear power plants.
The heat pipe type reactor is a novel reactor device which transfers heat from a reactor core to an energy conversion system by utilizing the two-phase natural circulation characteristic of alkali metal in a high-temperature heat pipe. The novel heat pipe reactor coupled water vapor Rankine cycle nuclear power system is an ideal choice for the application scene of sea, land and air mobile nuclear power sources and nuclear power devices.
Therefore, there is a need for a mobile nuclear power plant which has a simple structure in a limited space, good safety and reliability, and easy operation and maintenance, and can be used in sea, land and air.
Disclosure of Invention
In view of the above, the invention provides a nuclear power plant based on a heat pipe reactor, which has a simple structure, is safe and reliable, is simple to operate and maintain, has a small volume, and is movable, and a using method thereof.
In order to achieve the purpose, the invention adopts the following technical scheme: a nuclear power plant based on a heat pipe type reactor is characterized in that: the apparatus comprises:
a heat pipe type reactor core;
one end of the heat pipe is connected with the core of the heat pipe type reactor;
the heat pipe heat exchanger is connected with the other end of the heat pipe;
and the water vapor circulating system is connected with the heat pipe heat exchanger.
Preferably, the water vapor circulation system includes:
the turbine air inlet is connected with the heat pipe heat exchanger;
the generator rotating shaft is connected with the turbine rotating shaft, and the turbine rotating shaft drives the rotating shaft of the generator to synchronously rotate;
a water circulating pump;
the air inlet of the condenser is connected with the air outlet of the turbine, and the water inlet of the condenser is connected with the circulating water pump;
and a water inlet of the water feeding pump is connected with a first water outlet of the condenser, and a water outlet of the water feeding pump is connected with the heat pipe exchanger.
Preferably, the core of the heat pipe type reactor is an all-solid-state reactor.
Preferably, the fuel of the core of the heat pipe reactor is one of uranium molybdenum alloy, uranium dioxide, uranium nitride and uranium carbide.
Preferably, the heat pipe is a pipe bundle consisting of 10-20000 pipes.
Preferably, the outer diameter of the heat pipe is 10mm-100 mm.
Preferably, the arrangement mode of the heat pipe bundle is in a fork row or a straight row.
Preferably, the working medium of the heat pipe is one or more of lithium, sodium and potassium.
Preferably, the circulation medium in the water vapor circulation system is subcritical water or supercritical water.
A method of using a nuclear power plant based on a heat pipe type reactor, characterized in that it comprises the following steps:
a. the core of the heat pipe type reactor works to generate heat energy;
b. the heat pipe loads heat energy generated by the heat pipe type reactor core into the heat pipe heat exchanger in a passive mode;
c. heating the supercritical or critical steam of the flowing working medium in a heat pipe exchanger;
c. the steam after temperature rise enters a turbine to do work, and a rotating shaft of the turbine rotates;
d. the turbine rotating shaft drives the generator to start working;
e. the exhaust gas which does work in the turbine enters a condenser through a connecting pipeline and a condenser air inlet, and simultaneously a circulating water pump pumps cooling water into the condenser through a water inlet of the condenser to cool the exhaust gas entering the condenser; the cooled exhaust gas is discharged from a first water outlet of the condenser, and the circulating cooling water is discharged from a second water outlet of the condenser;
f. cooling exhaust gas enters a water feeding pump through a connecting pipeline;
g. the water pumped by the water pump enters the heat pipe exchanger along the connecting pipeline to be heated, and a new circulation is started.
The invention has the beneficial effects that: the invention provides a concept of a nuclear power device based on a heat pipe type reactor, and the device disclosed by the invention has the advantages of simple structure, safety, reliability, simpler operation and maintenance, small volume, mobility and the like, and is embodied in the following aspects:
1. the device utilizes the passive heat transfer of the heat pipe as a reactor core heat guiding means, a loop system and a rotating part in the existing device are not provided, the structure of the device is greatly simplified, the heat pipe type reactor core is an all-solid reactor core, the reactor core can be free of maintenance, the traditional pressurized water reactor rod-losing and rod-bouncing accident is avoided, and the reliability and the safety of the device are improved; 2. in the aspect of a power conversion device, the steam state in the steam circulation system can be supercritical water, and compared with subcritical water steam of a pressurized water reactor, the supercritical water can reach higher temperature, so that the conversion efficiency of the circulation capacity of the device is higher; 3. the device simple structure, the volume is less, is applicable to the limited occasion in space, also can remove at will, adapts to different use occasions.
Drawings
FIG. 1 is a schematic diagram of a nuclear power plant based on a heat pipe type reactor according to the present invention;
in the figure: 1. the reactor core 2 of the heat pipe type reactor, the heat pipe 3, the heat pipe exchanger 4, the water vapor circulating system 5, the turbine 6, the generator 7, the circulating water pump 8, the condenser 9, the water feeding pump 10 are connected with pipelines.
Detailed Description
It will be appreciated by those of ordinary skill in the art that the embodiments described herein are intended to assist the reader in understanding the principles of the invention and are to be construed as being without limitation to such specifically recited embodiments and examples. Those skilled in the art can make various other specific changes and combinations based on the teachings of the present invention without departing from the spirit of the invention, and these changes and combinations are within the scope of the invention.
The invention is described in detail below with reference to the figures and specific embodiments.
As shown in fig. 1, a nuclear power plant based on a reactor of the heat pipe type, comprises: the reactor comprises a heat pipe type reactor core 1, heat pipes 2, a heat pipe heat exchanger 3 and a water vapor circulating system 4; one end of the heat pipe 2 is connected with the heat pipe type reactor core 1, and the other end of the heat pipe is connected with the heat pipe heat exchanger 3; the water vapor circulation system 4 is connected with the heat pipe heat exchanger 3 through a connecting pipeline 10.
The heat pipe 2 passively loads heat energy generated by the heat pipe type reactor core 1 into the heat pipe heat exchanger 3, the heat pipe heat exchanger 3 absorbs heat and heats supercritical or critical water vapor, and the heated water vapor enters the water vapor circulation system 4 and then carries out conversion from heat energy to electric energy.
Preferably, the water vapor circulation system 4 comprises: a turbine 5, a generator 6, a circulating water pump 7, a condenser 8 and a water feeding pump 9; a rotating shaft of the turbine 5 is directly connected with a rotating shaft of the generator 6, and the rotating shaft of the turbine 5 can drive the rotating shaft of the generator 6 to synchronously rotate; along the flowing direction of the steam, an air inlet of a turbine 5 is connected with the heat pipe heat exchanger 3, an air outlet of the turbine 5 is connected with an air inlet of a condenser 8, a first water outlet of the condenser 8 is connected with a water feed pump 9, and a water outlet of the water feed pump 9 is connected with the heat pipe heat exchanger 3; the water outlet of the circulating water pump 7 is connected with the water inlet of the condenser 8, and cooling water is directly discharged through the second water outlet of the condenser 8.
The inlet of the condenser 8 is defined as being connected to the outlet of the turbine 5, through which steam enters the condenser 8; a water inlet of the condenser 8 is defined as a water inlet connected with the circulating water pump 7, and cooling water enters the condenser 8 through the water inlet; the first water outlet of the condenser 8 is defined as the water outlet connected with the water feeding pump 9, and after water vapor is cooled in the condenser 8, the state is changed from gas to liquid, and the liquid is discharged through the first water outlet of the condenser 8 and enters the water feeding pump 9; and a second water outlet of the condenser 8 is communicated with the water inlet and is used for discharging cooling water.
The rotating shaft of the turbine 5 can drive the rotating shaft of the generator 6 to synchronously rotate, the turbine converts the heat energy output by the heat pipe exchanger 3 into mechanical energy, and the generator 6 converts the mechanical energy into electric energy to provide nuclear power.
Preferably, the core 1 of the heat pipe type reactor is an all-solid-state core.
Preferably, the fuel material of the core 1 is one of uranium-molybdenum alloy, uranium dioxide, uranium nitride and uranium carbide.
Preferably, the heat pipe 2 is a pipe bundle consisting of 10 to 20000 pipes, and the number of the pipe bundles can be adjusted according to the power required in practical application.
Preferably, the outer diameter of the heat pipe 2 is 10mm-100 mm.
Preferably, the arrangement mode of the heat pipe 2 bundle is in a fork row or a row.
Preferably, the working medium of the heat pipe 2 is one or more of lithium, sodium and potassium.
Fig. 1 shows a method for using a nuclear power plant based on a heat pipe type reactor, wherein the small triangular arrows in fig. 1 indicate the flow directions of water vapor and water in a connecting pipe 10, and the method comprises the following steps:
firstly, the heat pipe type reactor core 1 works to generate heat energy; the heat pipe 2 passively loads heat energy generated by the heat pipe type reactor core 1 into the heat pipe heat exchanger 3; in the heat pipe heat exchanger 3, supercritical water vapor absorbs heat to heat; the heated supercritical water vapor enters a turbine 5 to do work, and a rotating shaft of the turbine 5 rotates; the rotating shaft of the turbine 5 drives the generator 6 to start rotating and generate electricity; supercritical water vapor exhaust gas which does work in the turbine 5 enters a condenser 8 through a connecting pipeline 10, and simultaneously a circulation water pump pumps cooling water into the condenser to cool the water vapor exhaust gas entering the condenser 8 to the lowest circulation temperature of the system; the cooled water vapor is discharged from a first water outlet of the condenser 8, and the circulating cooling water is discharged from a second water outlet of the condenser 8; the cooling water then enters the feed pump 9, and the water pumped by the feed pump 9 enters the heat pipe exchanger 3 along the connecting pipe 10, is heated, and a new cycle is started.
Claims (10)
1. A nuclear power plant based on a heat pipe type reactor is characterized in that: the apparatus comprises:
a heat pipe type reactor core (1);
one end of the heat pipe (2) is connected with the heat pipe type reactor core (1);
the heat pipe heat exchanger (3), the said heat pipe heat exchanger (3) is connected with another end of the heat pipe (2);
and the water vapor circulating system (4), and the water vapor circulating system (4) is connected with the heat pipe heat exchanger (3).
2. The heat pipe type reactor based nuclear power plant as defined in claim 1, wherein: the water vapor circulation system (4) comprises:
the air inlet of the turbine (5) is connected with the heat pipe heat exchanger (3);
the rotating shaft of the generator (6) is connected with the rotating shaft of the turbine (5), and the rotating shaft of the turbine (5) drives the rotating shaft of the generator (6) to synchronously rotate;
a circulating water pump (7);
the air inlet of the condenser (8) is connected with the air outlet of the turbine (5), and the water inlet of the condenser (8) is connected with the circulating water pump (7);
a water inlet of the water feeding pump (9) is connected with a first water outlet of the condenser (8), and a water outlet of the water feeding pump (9) is connected with the heat pipe heat exchanger (3).
3. The heat pipe type reactor based nuclear power plant as defined in claim 1, wherein: the reactor core (1) of the heat pipe type reactor is an all-solid-state reactor.
4. The heat pipe type reactor based nuclear power plant as defined in claim 3, wherein: the fuel of the heat pipe type reactor core (1) is one of uranium molybdenum alloy, uranium dioxide, uranium nitride and uranium carbide.
5. The heat pipe type reactor based nuclear power plant as defined in claim 1, wherein: the heat pipe (2) is a pipe bundle consisting of 10-20000 pipes.
6. The heat pipe type reactor based nuclear power plant as defined in claim 5, wherein: the outer diameter of the heat pipe (2) is 10mm-100 mm.
7. The heat pipe type reactor based nuclear power plant as defined in claim 6, wherein: the arrangement mode of the heat pipe (2) bundles is in a fork row or a straight row.
8. The heat pipe type reactor based nuclear power plant as defined in claim 7, wherein: the working medium of the heat pipe (2) is one or more of lithium, sodium and potassium.
9. The heat pipe type reactor based nuclear power plant as defined in claim 1, wherein: and the circulating medium in the water vapor circulating system (4) is subcritical water or supercritical water.
10. Use of a nuclear power plant based on a heat pipe type reactor according to claim 1, characterized in that it comprises the following steps:
a. the heat pipe type reactor core (1) works to generate heat energy;
b. the heat pipe (2) loads the heat energy generated by the heat pipe type reactor core (1) into the heat pipe heat exchanger (3) in a passive mode;
c. in the heat pipe heat exchanger (3), heating the supercritical or critical steam of the flowing working medium;
c. the heated steam enters a turbine (5) to do work, and a rotating shaft of the turbine (5) rotates;
d. a rotating shaft of the turbine (5) drives the generator (6) to start working;
e. exhaust gas which does work in the turbine (5) enters a condenser (8) through a connecting pipeline (10) and an air inlet of the condenser (8), and meanwhile a circulating water pump (7) pumps cooling water into the condenser (8) through a water inlet of the condenser (8) to cool the exhaust gas entering the condenser (8); the cooled exhaust gas is discharged from a first water outlet of the condenser (8), and the circulating cooling water is discharged from a second water outlet of the condenser (8);
f. cooling exhaust gas enters a water feeding pump (9) through a connecting pipeline (10);
g. the water pumped by the water feeding pump (9) enters the heat pipe heat exchanger (3) along the connecting pipeline (10) for heating, and a new circulation is started.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010695572.1A CN111785397A (en) | 2020-07-17 | 2020-07-17 | Nuclear power device based on heat pipe type reactor and using method |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010695572.1A CN111785397A (en) | 2020-07-17 | 2020-07-17 | Nuclear power device based on heat pipe type reactor and using method |
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| CN111785397A true CN111785397A (en) | 2020-10-16 |
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| CN202010695572.1A Pending CN111785397A (en) | 2020-07-17 | 2020-07-17 | Nuclear power device based on heat pipe type reactor and using method |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN115171924A (en) * | 2022-07-08 | 2022-10-11 | 上海交通大学 | Lead bismuth cooling solid reactor core system |
| CN116072318A (en) * | 2023-01-18 | 2023-05-05 | 哈尔滨工程大学 | Multi-loop brayton cycle energy conversion system for heat pipe stacks and method of operation |
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| CN111105883A (en) * | 2019-12-31 | 2020-05-05 | 中国核动力研究设计院 | Heat pipe reactor system with supercritical carbon dioxide as thermoelectric conversion working medium |
| CN111128410A (en) * | 2019-12-31 | 2020-05-08 | 中国核动力研究设计院 | Heat pipe reactor system and energy conversion mode thereof |
| CN111128415A (en) * | 2019-12-31 | 2020-05-08 | 中国核动力研究设计院 | Heat pipe reactor adopting closed gas Brayton cycle and operation method thereof |
| CN111120100A (en) * | 2019-12-31 | 2020-05-08 | 中国核动力研究设计院 | Heat pipe reactor adopting open type gas Brayton cycle and operation method thereof |
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2020
- 2020-07-17 CN CN202010695572.1A patent/CN111785397A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN203931515U (en) * | 2014-03-20 | 2014-11-05 | 中国核动力研究设计院 | Based on actively adding of 177 reactor cores non-active nuclear steam supply system and nuclear power station thereof |
| CN111105883A (en) * | 2019-12-31 | 2020-05-05 | 中国核动力研究设计院 | Heat pipe reactor system with supercritical carbon dioxide as thermoelectric conversion working medium |
| CN111128410A (en) * | 2019-12-31 | 2020-05-08 | 中国核动力研究设计院 | Heat pipe reactor system and energy conversion mode thereof |
| CN111128415A (en) * | 2019-12-31 | 2020-05-08 | 中国核动力研究设计院 | Heat pipe reactor adopting closed gas Brayton cycle and operation method thereof |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115171924A (en) * | 2022-07-08 | 2022-10-11 | 上海交通大学 | Lead bismuth cooling solid reactor core system |
| CN116072318A (en) * | 2023-01-18 | 2023-05-05 | 哈尔滨工程大学 | Multi-loop brayton cycle energy conversion system for heat pipe stacks and method of operation |
| CN116072318B (en) * | 2023-01-18 | 2024-01-23 | 哈尔滨工程大学 | Multi-loop brayton cycle energy conversion system for heat pipe stacks and method of operation |
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