CN114121306A - Feasibility Verification Device for Waste Heat Utilization of Tokamak Lower Divertor Heat Pipe Thermoelectric Power Generation - Google Patents
Feasibility Verification Device for Waste Heat Utilization of Tokamak Lower Divertor Heat Pipe Thermoelectric Power Generation Download PDFInfo
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- CN114121306A CN114121306A CN202111416993.7A CN202111416993A CN114121306A CN 114121306 A CN114121306 A CN 114121306A CN 202111416993 A CN202111416993 A CN 202111416993A CN 114121306 A CN114121306 A CN 114121306A
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- thermoelectric
- water
- heat pipe
- silent
- tokamak
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- 239000002918 waste heat Substances 0.000 title claims abstract description 24
- 238000012795 verification Methods 0.000 title claims abstract description 16
- 238000010248 power generation Methods 0.000 title claims description 16
- 238000010438 heat treatment Methods 0.000 claims abstract description 41
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 33
- PTVDYARBVCBHSL-UHFFFAOYSA-N copper;hydrate Chemical compound O.[Cu] PTVDYARBVCBHSL-UHFFFAOYSA-N 0.000 claims abstract description 25
- 239000000758 substrate Substances 0.000 claims abstract description 20
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 claims abstract description 8
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 claims description 28
- 229910052786 argon Inorganic materials 0.000 claims description 14
- 230000005494 condensation Effects 0.000 claims description 11
- 238000009833 condensation Methods 0.000 claims description 11
- 239000000463 material Substances 0.000 claims description 9
- 239000000498 cooling water Substances 0.000 claims description 8
- 238000001704 evaporation Methods 0.000 claims description 8
- 230000008020 evaporation Effects 0.000 claims description 8
- 238000001816 cooling Methods 0.000 claims description 7
- 239000011159 matrix material Substances 0.000 claims description 7
- 230000000087 stabilizing effect Effects 0.000 claims description 6
- 239000007788 liquid Substances 0.000 claims description 3
- 230000002745 absorbent Effects 0.000 claims 1
- 239000002250 absorbent Substances 0.000 claims 1
- 230000000694 effects Effects 0.000 claims 1
- 238000000034 method Methods 0.000 abstract description 2
- 230000003068 static effect Effects 0.000 description 23
- 230000004927 fusion Effects 0.000 description 6
- 238000004088 simulation Methods 0.000 description 3
- 238000010521 absorption reaction Methods 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 230000017525 heat dissipation Effects 0.000 description 2
- 238000011160 research Methods 0.000 description 2
- 230000005678 Seebeck effect Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000002452 interceptive effect Effects 0.000 description 1
- 239000002994 raw material Substances 0.000 description 1
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/25—Maintenance, e.g. repair or remote inspection
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/11—Details
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/11—Details
- G21B1/13—First wall; Blanket; Divertor
-
- 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
- Y02E30/10—Nuclear fusion 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)
- Photovoltaic Devices (AREA)
Abstract
The invention discloses a verification device for the feasibility of utilizing waste heat of thermoelectric generation of a thermotube of a lower divertor of Tokamak, which comprises an electric cabinet control box, a power supply, a frame, a bottom plate, a railing, quartz glass, a top plate, a copper-water thermotube, a heating rod, a silent substrate, a thermoelectric generation silent sheet, a substrate, an electronic load, a support rod, a water pump and a water tank. The method is compact in structure, high in inherent safety, simple and feasible, and capable of being used for verifying feasibility of a scheme for utilizing waste heat of the thermoelectric generation of the heat pipe of the divertor under the Tokamak device.
Description
Technical Field
The invention relates to the technical field of nuclear power supplies, in particular to a verification device for feasibility of thermoelectric generation waste heat utilization of a thermotube of a lower divertor of a Tokamak.
Background
Compared with a fission reactor, the fusion reactor has the advantages of high energy, safety, environmental protection, high efficiency and inexhaustible raw materials, and is expected to solve the problem of energy resources once and for all. Therefore, the EAST fusion reactor researched by plasma of Chinese academy of sciences has extremely important research value, and the EAST serving as the first full-superconducting non-circular-section tokamak nuclear fusion experimental device designed and researched by China has the characteristics of ultrahigh temperature, ultralow temperature, ultrahigh current, superstrong magnetic field and ultrahigh vacuum. In the current research, the heat sink material stored in the divertor can not be used during the running of the EAST fusion reactor, so that the part of energy is wasted, the energy utilization rate is reduced, the part of energy can be used by adopting a heat pipe-temperature difference power generation technology, and a device is needed to complete the simulation of the working state of the lower divertor and verify whether the scheme is feasible or not.
Disclosure of Invention
In order to verify the feasibility of the utilization of the waste heat of the heat pipe thermoelectric generation of the lower divertor of the EAST fusion reactor and realize the utilization of the waste heat in the heat sink material of the lower divertor, the invention provides the verification device of the feasibility of the utilization of the waste heat of the heat pipe thermoelectric generation of the lower divertor of the tokamak, which can meet the requirements of utilizing the waste heat, not interfering the work of the internal components of the tokamak device and accurately simulating the working condition of the lower divertor.
In order to achieve the purpose, the invention adopts the following design scheme:
the verification device for the feasibility of utilizing the waste heat of the thermoelectric power generation of the heat pipe of the lower divertor of the Tokamak comprises a power supply control box 1, a power supply 2, a frame 3, a bottom plate 4, a railing 5, quartz glass 6, a top plate 7, a combined cover nut-coarse teeth 8, an exhaust hole 9, a thermoelectric power generation static tacit sheet 10, a static substrate 11, a substrate 12, a heating rod 13, a support rod 14, a water pump 15, a water tank 16, a copper-water heating pipe 17 and an electronic load 18; the power supply 2 is arranged at the bottom of the frame 3 and is connected with the power supply control cabinet 1, the bottom plate 4, the railing 5, the quartz glass 6 and the top plate 7 form a display platform, the combined cover type nut-coarse teeth 8 are used for fixing, a heating rod 13 is inserted into a base body 12, a wire of the heating rod 13 penetrates out of a wire outlet of the heating rod and is connected to a power supply 2, an evaporation section of a copper-water heating pipe 17 is inserted into the base body 12, a condensation section completely penetrates through a silent base body 11, a thermoelectric generation static mercy piece 10 is arranged on the silent base body 11, a cold end of the thermoelectric generation static mercy piece 10 is provided with a water jacket, the water jacket, a water pump 15 and a water tank 16 form a water cooling loop, a connecting line of the thermoelectric generation static mercy piece 10 is connected to an electronic load 18 through a silent wire outlet, and the thermoelectric generation static mercy piece 10, the silent base body 11, the base body 12, the heating rod 13, a support rod 14 and the copper-water heating pipe 17 form an experimental section which is fixed on the support rod 14 and is arranged in a display platform; the substrate 12 is used to simulate heat sink material in a tokamak lower divertor.
The power supply control box 1, the power supply 2 and the heating rod 13 form a heating system, the power supply 2 uses a program-controlled power supply to regulate and control the voltage of the heating rod 13 so as to ensure that the surface temperature of the matrix 12 is 300 ℃, and the simulation device is used for simulating the temperature of a heat sink material in a divertor under Tokamak after being cooled by cooling water.
The copper-water heat pipe 17 is a capillary driven heat pipe, the liquid absorption core is a sintered liquid absorption core, the length is 300mm, the diameter is 20mm, the length of the evaporation section is 160mm, the length of the condensation section is 120mm, and the working temperature is 300 ℃.
The thermoelectric generation static sheet 10, the silent base 11 and the electronic load 18 form a thermoelectric generation system, 42 thermoelectric generation static sheets 10 are uniformly arranged on the silent base 11, the connecting line of the 42 thermoelectric generation static sheets 10 passes through the silent outlet and is connected to the voltage stabilizing module, and the other end of the voltage stabilizing module is connected to the electronic load 18.
When the device works, the vacuum is required to be pumped to 10-3And Pa, removing air from the device by using argon, wherein the argon enters the device from an argon inlet, and the air is discharged from the device through an exhaust hole 9.
The copper-water heat pipes 17 may be uniformly arranged in the horizontal direction of the substrate 12 using flat plate heat pipes.
Compared with the prior art, the invention has the following advantages:
the working principle of the copper-water heat pipe is used as working medium natural circulation, and compared with a passive component, the copper-water heat pipe has high safety; the heating rod and the cooling water pipe are simultaneously used for acting on the matrix, so that the temperature of the matrix is stabilized at 300 ℃, the heating process of the heat sink material in the divertor under the EAST is accurately simulated, and the result has more reference significance; the vacuum device is adopted, and the air in the device is exhausted by using argon, so that the heat dissipation of the condensation section of the copper-water heating pipe is reduced, and the heat utilization rate of the thermoelectric generation static sheet is higher.
The invention provides a device for verifying feasibility aiming at a scheme for utilizing waste heat of the divertor heat pipe temperature difference power generation in an EAST fusion reactor tokamak device.
Drawings
FIG. 1 is a front view of a verification device for feasibility of waste heat utilization of thermoelectric power generation of a Tokamak lower divertor heat pipe.
FIG. 2 is a left side view of a verification device for feasibility of thermoelectric generation waste heat utilization of a Tokamak lower divertor heat pipe.
FIG. 3 is a top view of a verification device for the feasibility of utilizing waste heat of the thermoelectric generation of the heat pipe of the lower divertor of the tokamak.
Detailed Description
The invention will now be further described with reference to the following examples, and the accompanying drawings:
as shown in fig. 1, fig. 2 and fig. 3, the verification device for feasibility of waste heat utilization of thermoelectric generation of the tokamak lower divertor heat pipe comprises a power control box 1, a power supply 2, a frame 3, a bottom plate 4, a rail 5, quartz glass 6, a top plate 7, a combined cap nut-coarse teeth 8, an exhaust hole 9, a thermoelectric generation static sheet 10, a static substrate 11, a substrate 12, a heating rod 13, a support rod 14, a water pump 15, a water tank 16, a copper-water heating pipe 17 and an electronic load 18; the power supply 2 is arranged at the bottom of the frame 3 and is connected with the power supply control cabinet 1, the bottom plate 4, the railing 5, the quartz glass 6 and the top plate 7 form a display platform, the combined cover type nut-coarse teeth 8 are used for fixing, a heating rod 13 is inserted into a base body 12, a wire of the heating rod 13 penetrates out of a wire outlet of the heating rod and is connected to a power supply 2, an evaporation section of a copper-water heating pipe 17 is inserted into the base body 12, a condensation section completely penetrates through a silent base body 11, a thermoelectric generation static mercy piece 10 is arranged on the silent base body 11, a cold end of the thermoelectric generation static mercy piece 10 is provided with a water jacket, the water jacket, a water pump 15 and a water tank 16 form a water cooling loop, a connecting line of the thermoelectric generation static mercy piece 10 is connected to an electronic load 18 through a silent wire outlet, and the thermoelectric generation static mercy piece 10, the silent base body 11, the base body 12, the heating rod 13, a support rod 14 and the copper-water heating pipe 17 form an experimental section which is fixed on the support rod 14 and is arranged in a display platform; the substrate 12 is used to simulate heat sink material in a tokamak lower divertor.
As a preferred embodiment of the invention, the power supply control box 1, the power supply 2 and the heating rod 13 form a heating system, the power supply 2 uses a program-controlled power supply to regulate and control the voltage of the heating rod 13 so as to ensure that the surface temperature of the substrate 12 is 300 ℃ and is used for simulating the temperature of a heat sink material in a divertor under EAST after being cooled by cooling water, so that the surface temperature of the substrate 12 can be accurately controlled to be kept stable, and the temperature simulation is more accurate. As a preferred embodiment of the present invention, the copper-water heat pipe 17 is a capillary driven heat pipe, the wick is a sintered wick, the length is 300mm, the diameter is 20mm, the length of the evaporation section is 160mm, the length of the condensation section is 120mm, and the working temperature is 300 ℃, so that the heat pipe design can meet the experimental temperature requirement and the heat dissipation is low.
As the preferred embodiment of the invention, the thermoelectric generation static sheet 10, the silent base 11 and the electronic load 18 form a thermoelectric generation system, 42 thermoelectric generation static sheets 10 are uniformly arranged on the silent base 11, the connecting line of the 42 thermoelectric generation static sheets 10 passes through the silent outlet and is connected to the voltage stabilizing module, and the other end of the voltage stabilizing module is connected to the electronic load 18, so that the heat utilization and thermoelectric conversion process can be visually demonstrated.
As a preferred embodiment of the invention, when the device works, the device needs to be vacuumized to 10 < -3 > Pa, argon is used for exhausting air from the device, the argon enters the device from an argon inlet, and the air is exhausted from the device through the exhaust hole 9, so that the air can be completely exhausted when the device works, the substrate 12 is prevented from contacting with the air when being heated, and rusting is avoided.
As a preferred embodiment of the present invention, the copper-water heat pipes 17 may be flat heat pipes, and are uniformly arranged along the horizontal direction of the substrate 12, so as to ensure that the heat in the substrate 12 is fully utilized and reduce the heat loss.
The working principle of the invention is as follows: argon is filled through an argon inlet above the device, air is discharged through an exhaust hole 9, a power supply 2 supplies power to a heating rod 13, the heating rod 13 releases heat, the heating rod is absorbed by a base body 12, the temperature of the base body 12 rises, an evaporation section of a copper-water heating pipe 17 absorbs the heat in the base body 12 and transfers the heat to a condensation section of the copper-water heating pipe 17, the condensation section of the copper-water heating pipe 17 heats the hot end of a thermoelectric generation static mercy piece 10, the heated thermoelectric generation static mercy piece 10 generates electric energy due to the Seebeck effect, the heated thermoelectric generation static mercy piece 10 is cooled by cooling water in a water cooling loop from a water tank 16, the cooling water in the water cooling loop is driven by a water pump 15 to flow back to the water tank 16, the electric energy with unstable pressure generated by the heated thermoelectric generation static mercy piece 10 is transferred to an electronic load 18 after passing through a voltage stabilizing module, the electronic load 18 consumes the electric energy, and the verification of the feasibility of utilizing the thermoelectric generation waste heat of the heat pipe of the partial filter under the Tokamak is realized.
Claims (7)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111416993.7A CN114121306B (en) | 2021-11-25 | 2021-11-25 | Device for verifying thermal power generation waste heat utilization feasibility of heat pipe temperature difference generation of tokamak lower partial filter |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111416993.7A CN114121306B (en) | 2021-11-25 | 2021-11-25 | Device for verifying thermal power generation waste heat utilization feasibility of heat pipe temperature difference generation of tokamak lower partial filter |
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| Publication Number | Publication Date |
|---|---|
| CN114121306A true CN114121306A (en) | 2022-03-01 |
| CN114121306B CN114121306B (en) | 2024-10-25 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202111416993.7A Active CN114121306B (en) | 2021-11-25 | 2021-11-25 | Device for verifying thermal power generation waste heat utilization feasibility of heat pipe temperature difference generation of tokamak lower partial filter |
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| CN (1) | CN114121306B (en) |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0438724A2 (en) * | 1990-01-22 | 1991-07-31 | Werner K. Dipl.-Ing. Steudtner | Fusion reactor |
| CN101013610A (en) * | 2007-01-29 | 2007-08-08 | 中国科学院等离子体物理研究所 | Cool-off heat sink of steady-state tokamak divertor |
| CN104332184A (en) * | 2014-08-30 | 2015-02-04 | 中国科学院等离子体物理研究所 | Target-plate probe system applicable to full-tungsten divertor of EAST tokamak device |
| CN105976873A (en) * | 2016-03-02 | 2016-09-28 | 中国科学院等离子体物理研究所 | Internal part cooling power generation system for future tokamak fusion reactor |
| RU173227U1 (en) * | 2016-11-28 | 2017-08-17 | Федеральное государственное бюджетное образовательное учреждение высшего образования Балтийский государственный технический университет "ВОЕНМЕХ" им. Д.Ф. Устинова (БГТУ "ВОЕНМЕХ") | The device of the diverter of the tokamak reactor |
| CN109585031A (en) * | 2018-10-16 | 2019-04-05 | 中国科学院合肥物质科学研究院 | A kind of water quality managing and control system based on Superconducting tokamak device |
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2021
- 2021-11-25 CN CN202111416993.7A patent/CN114121306B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0438724A2 (en) * | 1990-01-22 | 1991-07-31 | Werner K. Dipl.-Ing. Steudtner | Fusion reactor |
| CN101013610A (en) * | 2007-01-29 | 2007-08-08 | 中国科学院等离子体物理研究所 | Cool-off heat sink of steady-state tokamak divertor |
| CN104332184A (en) * | 2014-08-30 | 2015-02-04 | 中国科学院等离子体物理研究所 | Target-plate probe system applicable to full-tungsten divertor of EAST tokamak device |
| CN105976873A (en) * | 2016-03-02 | 2016-09-28 | 中国科学院等离子体物理研究所 | Internal part cooling power generation system for future tokamak fusion reactor |
| RU173227U1 (en) * | 2016-11-28 | 2017-08-17 | Федеральное государственное бюджетное образовательное учреждение высшего образования Балтийский государственный технический университет "ВОЕНМЕХ" им. Д.Ф. Устинова (БГТУ "ВОЕНМЕХ") | The device of the diverter of the tokamak reactor |
| CN109585031A (en) * | 2018-10-16 | 2019-04-05 | 中国科学院合肥物质科学研究院 | A kind of water quality managing and control system based on Superconducting tokamak device |
Non-Patent Citations (1)
| Title |
|---|
| 谢韩;宋云涛;姚达毛;: "EAST超导托卡马克偏滤器水冷结构设计", 核聚变与等离子体物理, no. 04, 15 December 2009 (2009-12-15) * |
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