CN109841287B - Liquid fuel nuclear reactor capable of working through inertia force - Google Patents
Liquid fuel nuclear reactor capable of working through inertia force Download PDFInfo
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- CN109841287B CN109841287B CN201910290028.6A CN201910290028A CN109841287B CN 109841287 B CN109841287 B CN 109841287B CN 201910290028 A CN201910290028 A CN 201910290028A CN 109841287 B CN109841287 B CN 109841287B
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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
Abstract
The invention provides a liquid fuel nuclear reactor which can work through inertia force, belongs to the technical field of nuclear engineering and nuclear, and particularly relates to a liquid fuel nuclear reactor which can work through inertia force. The problem of current nuclear reactor can't realize natural circulation under the condition of no gravity, liquid fuel is difficult to maintain stable form in the reactor core is solved. The reactor comprises a reactor core, a fixed base, a heat dissipation device, a central channel and liquid fuel. It is mainly used in liquid fuel nuclear reactors under gravity-free conditions or under severe external influences.
Description
Technical Field
The invention belongs to the technical field of nuclear engineering and nuclear, and particularly relates to a liquid fuel nuclear reactor which can work through inertia force.
Background
The existing liquid fuel nuclear reactor uses a liquid fissile material as fuel to generate heat energy, the heat energy is directly converted into internal energy of the liquid fuel material, and the internal energy of the fuel material is forced to circulate under the driving of a pump or naturally circulates under the action of gravity, so that the internal energy of the fuel material is transferred to a cooling material and then is converted into usable kinetic energy or electric energy. However, liquid fuel heat pipe nuclear reactors have significant problems in that natural circulation cannot be achieved without gravity, either face failure or rely only on forced circulation driven by a pump. Once a circulation pump fails, the nuclear reactor is at risk of failing by insufficient heat dissipation. Or under the severe external influence, such as violent swing and shaking, the liquid fuel is difficult to maintain a stable form in the reactor core, and the stable power cannot be provided.
Disclosure of Invention
The invention provides a liquid fuel nuclear reactor which can work through inertia force in order to solve the problems in the prior art.
In order to achieve the purpose, the invention adopts the following technical scheme: a liquid fuel nuclear reactor capable of achieving work through inertia force comprises a reactor core, a fixed base, heat dissipation devices, a central channel and liquid fuel, wherein the reactor core is annularly arranged around a central shaft of the fixed base, the center of the reactor core is the central channel, a cooling flowing working medium is introduced into the central channel, the fuel medium adopted by the reactor core is the liquid fuel, the number of the heat dissipation devices is a plurality, the heat dissipation devices are radially distributed along the reactor core to form heat dissipation layers, the heat dissipation layers are axially arranged along the reactor core, the heat dissipation devices are inserted into the liquid fuel to be divided into heating sections, the heat dissipation devices are located inside the central channel to be divided into cooling sections, and the nuclear reactor rotates around the central shaft during work.
Further, the rotation of the nuclear reactor is driven by an external rotation mechanism.
Furthermore, the rotation of the nuclear reactor is driven by a cooling flowing working medium, and the plurality of heat dissipation layers are spirally arranged along the axial direction of the reactor core of the reactor.
Further, the nuclear reactor is placed horizontally or vertically.
Further, the liquid fuel is a liquid molten salt material or a liquid metal material.
Further, the reactor core rotates about the central axis within the stationary base or the reactor core and the stationary base together rotate about the central axis when the nuclear reactor is in operation.
Furthermore, the cooling flowing working medium is compressed gas.
Furthermore, the inlet end and the outlet end of the cooling flowing working medium are connected with the central channel by adopting rotary joints.
Furthermore, the heat pipes are connected through a grid plate.
Furthermore, the heat dissipation device is a heat pipe or a fin heat dissipation plate.
Compared with the prior art, the invention has the beneficial effects that: when the invention works, the nuclear reactor rotates around the central shaft under the drive of an external rotating mechanism or a cooling flowing working medium, so as to provide inertia force for the circulation of the liquid fuel, realize that fluid flows without depending on gravity, overcome the influence of the external environment, maintain the stable state of the liquid fuel under the condition of ocean or different gravity, provide stable power distribution, and realize the homogenization of temperature under the stirring action of structures in the liquid fuel, such as the heat pipe, the fin cooling fin, the grid plate and the like.
Drawings
FIG. 1 is a schematic diagram of a liquid fuel nuclear reactor with spirally arranged heat pipes according to the present invention
FIG. 2 is a schematic diagram of the cycle trajectory of a liquid fuel nuclear reactor with spirally arranged heat pipes according to the present invention
FIG. 3 is a schematic diagram of a nuclear reactor with a heat pipe as a heat sink according to the present invention
FIG. 4 is a schematic diagram of a nuclear reactor with a fin-type heat sink according to the present invention
1-fixed base, 2-reactor core periphery, 3-heat pipe, 4-central channel, 5-liquid fuel, 6-fin radiating fin
Detailed Description
The technical solution in the embodiments of the present invention will be clearly and completely explained below with reference to the drawings in the embodiments of the present invention.
Referring to fig. 1 to 4, the present embodiment is a liquid fuel nuclear reactor that operates by inertial force, characterized in that: the reactor core comprises a reactor core, a fixed base 1, heat dissipation devices 3, a central channel 4 and liquid fuel 5, wherein the reactor core is annularly arranged around the central shaft of the fixed base 1, the center of the reactor core is the central channel 4, cooling flowing working media are introduced into the central channel 4, the fuel medium adopted by the reactor core is the liquid fuel 5, the number of the heat dissipation devices 3 is a plurality, the heat dissipation devices 3 are radially distributed along the reactor core to form heat dissipation layers, the heat dissipation layers are axially arranged along the reactor core, the heat dissipation devices 3 are inserted into the liquid fuel 5 and divided into heating sections, the heat dissipation devices 3 are located inside the central channel 4 and divided into cooling sections, and the nuclear reactor rotates around the central shaft during working.
In the embodiment, the inertial force is a centrifugal force generated in the rotation process of the nuclear reactor, the nuclear reactor can be placed horizontally or vertically, the liquid fuel is a liquid molten salt material or a liquid metal material, when the reactor core rotates around a central shaft in the fixed base 1 or the reactor core and the fixed base 1 rotate around the central shaft together, the liquid fuel 5 is gathered towards the outer side under the action of the centrifugal force generated by rotation of the reactor core, and gas is gathered towards the inner periphery of the reactor core, so that the phenomenon that gas bubbles are reserved in the liquid fuel 5 when the nuclear reactor is static and gas is gathered at one side of the reactor or in a gravity-free environment is avoided. An unfilled region is formed near the inner periphery to serve as a buffer region for the liquid fuel 5 when it expands or fission gases are generated. The liquid metal in the heat sink 3 is more likely to return to the reactor core, and the metal vapor in the heat sink 3 is more likely to accumulate toward the cooling zone, which enhances the heat transfer capability of the heat sink 3.
The rotation of the nuclear reactor is driven by an external rotating mechanism or by a cooling flowing working medium, when the nuclear reactor is driven by the external rotating mechanism, the nuclear reactor is connected with the external rotating mechanism, and the nuclear reactor is driven to rotate by the rotation of the external rotating mechanism; when the reactor is driven by cooling flowing working medium, the plurality of heat dissipation layers are spirally arranged along the axial direction of the reactor core, and each heat dissipation layer vertical to the core shaft and the next heat dissipation layer are staggered by a certain angle to complete a period after a certain distance. With such an arrangement, the heat sinks 3 within the central channel 4 may form a helical channel. Compressed gas or other cooling flowing working media are introduced into the central channel 4, the cooling flowing working media advance in the central channel 4 and can push the heat pipes which are spirally arranged to drive the reactor core to rotate, the cooling flowing working media consume kinetic energy in the process, meanwhile, the cooling flowing working media are heated by the cooling section of the heat dissipation device 3 in the central channel 4, the volume is expanded, the temperature is increased, higher kinetic energy and internal energy can be achieved, and the cooling flowing working media can participate in energy conversion circulation after being led out.
The inlet end and the outlet end of the cooling flowing working medium are connected with the central channel 4 by adopting rotary joints, one end of each rotary joint is connected with the central channel 4, the other end of each rotary joint is connected with a fixed pipeline, and the cooling medium pipelines are divided into a plurality of bundles and respectively participate in a plurality of energy conversion cycles. The distribution density of the heat dissipation devices 3 is determined according to the situation, and the heat dissipation devices 3 are connected through the grid plates, so that the structural strength is improved, the liquid fuel 5 is stirred, the heat exchange inside the liquid fuel 5 is improved, and the temperature homogenization is promoted. The heat dissipation device 3 is a heat pipe or a fin heat dissipation plate 6 or other active and passive heat exchange modes as a reactor core heat dissipation mode.
The liquid fuel nuclear reactor provided by the present invention, which operates by inertia force, is described in detail above, and the principle and the embodiment of the present invention are explained herein by using specific examples, and the description of the above examples is only used to help understanding the method and the core idea of the present invention; meanwhile, for a person skilled in the art, according to the idea of the present invention, there may be variations in the specific embodiments and the application scope, and in summary, the content of the present specification should not be construed as a limitation to the present invention.
Claims (10)
1. A liquid fuel nuclear reactor operating by inertial forces, characterized by: the reactor core comprises a reactor core, a fixed base (1), a heat dissipation device (3), a central channel (4) and liquid fuel (5), wherein the reactor core is annularly arranged around a central shaft of the fixed base (1), the center of the reactor core is the central channel (4), a cooling flowing working medium is introduced into the central channel (4), a fuel medium adopted by the reactor core is the liquid fuel (5), the number of the heat dissipation devices (3) is a plurality of, the heat dissipation devices (3) are radially distributed along the reactor core to form heat dissipation layers, the heat dissipation layers are axially arranged along the reactor core, the heat dissipation devices (3) are inserted into the liquid fuel (5) and are divided into heating sections, the heat dissipation devices (3) are positioned inside the central channel (4) and are divided into cooling sections, and the nuclear reactor rotates around the central shaft during working.
2. A liquid fuel nuclear reactor operating by inertial forces according to claim 1, wherein: the rotation of the nuclear reactor is driven by an external rotation mechanism.
3. A liquid fuel nuclear reactor operating by inertial forces according to claim 1, wherein: the rotation of the nuclear reactor is driven by a cooling flowing working medium, and the plurality of heat dissipation layers are spirally arranged along the axial direction of the reactor core.
4. A liquid fuel nuclear reactor operating by inertial force according to any one of claims 1 to 3, characterized in that: the nuclear reactor is placed horizontally or vertically.
5. A liquid fuel nuclear reactor operating by inertial forces according to any one of claims 1 to 3, characterized in that: the liquid fuel is a liquid molten salt material or a liquid metal material.
6. A liquid fuel nuclear reactor operating by inertial forces according to any one of claims 1 to 3, characterized in that: when the nuclear reactor works, the reactor core rotates around the central shaft in the fixed base (1) or the reactor core and the fixed base (1) rotate around the central shaft together.
7. A liquid fuel nuclear reactor operating by inertial forces according to any one of claims 1 to 3, characterized in that: the cooling flowing working medium is compressed gas.
8. A liquid fuel nuclear reactor operating by inertial forces according to any one of claims 1 to 3, characterized in that: and the inlet end and the outlet end of the cooling flowing working medium are connected with the central channel (4) by adopting rotary joints.
9. A liquid fuel nuclear reactor operating by inertial forces according to any one of claims 1 to 3, characterized in that: the heat dissipation devices (3) are connected through grid plates.
10. A liquid fuel nuclear reactor operating by inertial force according to any one of claims 1 to 3, characterized in that: the heat dissipation device (3) is a heat pipe or a fin heat dissipation sheet (6).
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Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
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US3136700A (en) * | 1961-05-17 | 1964-06-09 | Heinz F Poppendiek | Fuel channel elements for circulating fuel neutronic reactors |
CN103348413A (en) * | 2011-05-13 | 2013-10-09 | 尼尔·曼恩 | Nuclear reactor control method and apparatus |
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GB772404A (en) * | 1954-10-27 | 1957-04-10 | Varian Associates | Nuclear reactor |
US4645640A (en) * | 1984-02-09 | 1987-02-24 | Westinghouse Electric Corp. | Refueling system with small diameter rotatable plugs |
JPH0713661B2 (en) * | 1989-12-27 | 1995-02-15 | 日本原子力研究所 | Reactor |
JP2000180572A (en) * | 1998-12-15 | 2000-06-30 | Toshiba Corp | Liquid metal cooled reactor |
CN103985419B (en) * | 2014-06-05 | 2016-08-24 | 中国科学院合肥物质科学研究院 | A kind of fuel assembly locking device of liquid heavy metal reactor |
CN109074873B (en) * | 2016-04-26 | 2023-07-25 | 科利尔株式会社 | Load following miniaturized nuclear reactor system using liquid metal primary coolant |
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Patent Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3136700A (en) * | 1961-05-17 | 1964-06-09 | Heinz F Poppendiek | Fuel channel elements for circulating fuel neutronic reactors |
CN103348413A (en) * | 2011-05-13 | 2013-10-09 | 尼尔·曼恩 | Nuclear reactor control method and apparatus |
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