CN111946415A - Nuclear drive brayton device - Google Patents
Nuclear drive brayton device Download PDFInfo
- Publication number
- CN111946415A CN111946415A CN202010871692.2A CN202010871692A CN111946415A CN 111946415 A CN111946415 A CN 111946415A CN 202010871692 A CN202010871692 A CN 202010871692A CN 111946415 A CN111946415 A CN 111946415A
- Authority
- CN
- China
- Prior art keywords
- nuclear
- brayton
- heat
- nuclear fuel
- brayton cycle
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
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Links
- 239000003758 nuclear fuel Substances 0.000 claims abstract description 32
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 claims abstract description 24
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 claims abstract description 24
- 229910002092 carbon dioxide Inorganic materials 0.000 claims abstract description 12
- 239000001569 carbon dioxide Substances 0.000 claims abstract description 12
- 229910052757 nitrogen Inorganic materials 0.000 claims abstract description 12
- 239000007789 gas Substances 0.000 claims abstract description 11
- 230000009257 reactivity Effects 0.000 claims abstract description 9
- 230000006835 compression Effects 0.000 claims description 8
- 238000007906 compression Methods 0.000 claims description 8
- 238000010521 absorption reaction Methods 0.000 claims description 5
- 238000005516 engineering process Methods 0.000 abstract description 10
- 230000004992 fission Effects 0.000 abstract description 5
- 238000010248 power generation Methods 0.000 abstract description 5
- 238000006243 chemical reaction Methods 0.000 abstract description 3
- 238000005065 mining Methods 0.000 abstract description 3
- 239000000463 material Substances 0.000 description 4
- 229910052770 Uranium Inorganic materials 0.000 description 3
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 3
- 238000010586 diagram Methods 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 230000008569 process Effects 0.000 description 2
- ZSLUVFAKFWKJRC-IGMARMGPSA-N 232Th Chemical compound [232Th] ZSLUVFAKFWKJRC-IGMARMGPSA-N 0.000 description 1
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- 229910052778 Plutonium Inorganic materials 0.000 description 1
- 229910052776 Thorium Inorganic materials 0.000 description 1
- 230000004888 barrier function Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 229910002804 graphite Inorganic materials 0.000 description 1
- 239000010439 graphite Substances 0.000 description 1
- 230000017525 heat dissipation Effects 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000005025 nuclear technology Methods 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 230000035939 shock Effects 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Images
Classifications
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K27/00—Plants for converting heat or fluid energy into mechanical energy, not otherwise provided for
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K25/00—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for
- F01K25/08—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for using special vapours
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K25/00—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for
- F01K25/08—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for using special vapours
- F01K25/10—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for using special vapours the vapours being cold, e.g. ammonia, carbon dioxide, ether
- F01K25/103—Carbon dioxide
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K7/00—Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating
- F01K7/32—Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating the engines using steam of critical or overcritical pressure
Landscapes
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Combustion & Propulsion (AREA)
- Mechanical Engineering (AREA)
- General Engineering & Computer Science (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Engine Equipment That Uses Special Cycles (AREA)
Abstract
The invention aims to disclose a nuclear-driven Brayton device, which comprises a container, wherein a nuclear fuel block is arranged in the middle of the container, a plurality of heat conduction pipes penetrate through the nuclear fuel block, the nuclear fuel block is connected with a Brayton cycle device, one end of the Brayton cycle device is connected with a generator, the other end of the Brayton cycle device is connected with a compressor, the outer side of the nuclear fuel block is provided with a reactivity and radioactivity control ring, and the outer side of the nuclear fuel block is also provided with a heat exhauster; the novel nuclear power generation technology is adopted, namely the nuclear fission technology and the gas turbine technology are coupled, the Brayton cycle is carried out by using supercritical carbon dioxide or nitrogen, the high-efficiency conversion from the nuclear energy to the electric energy is realized, the system configuration is obviously simplified, the volume is small, the structure is simple, the reliability is high, the highway/ship/airplane/aerospace transportation requirements are met, the nuclear power generation system can be used for various scenes of sea, land, air and space, and nuclear power guarantee is provided for data centers, remote mining areas, emergency rescue and the like.
Description
Technical Field
The invention relates to a Brayton device, in particular to a nuclear driving Brayton device for driving Brayton cycle power generation through nuclear fission heat.
Background
Small nuclear power plants are the focus of international nuclear technology competition for the next 20 years. The traditional large nuclear power station adopts a pressurized water reactor technology and drives steam Brayton cycle power generation through nuclear fission. The small nuclear power device is required to be small in size, highly modularized, and movable and highly reliable, so that the nuclear power device is required to be innovative in design, extremely optimized and simplified, and new challenges are brought.
With the implementation of significant national science and technology specialities, particularly the implementation of nuclear power specialities and gas turbine specialities, the high-temperature gas cooled reactor technology and the gas turbine technology become mature day by day.
Therefore, there is a particular need for a nuclear driven brayton apparatus that addresses the above-mentioned problems of the prior art.
Disclosure of Invention
The invention aims to provide a nuclear-driven Brayton device, which aims at overcoming the defects of the prior art, provides safe, clean, reliable and economic electric power for more users and meets the electric power requirements in the environments of land, sea, air and sky.
The technical problem solved by the invention can be realized by adopting the following technical scheme:
the utility model provides a nuclear drive brayton device, its characterized in that, it includes the container the middle part of container is provided with nuclear fuel piece run through in the nuclear fuel piece and be provided with a plurality of heat pipes, nuclear fuel is connected with brayton cycle device soon, brayton cycle device's one end is connected with the generator, brayton cycle device's the other end is connected with the compressor, the outside of nuclear fuel piece is provided with reactivity and radioactivity control ring the outside of nuclear fuel piece still is provided with the heat exhauster.
In one embodiment of the invention, the heat conductive pipes each have an inlet and an outlet and penetrate the nuclear fuel block, and gas flows in from the inlets of the heat conductive pipes, is heated through the nuclear fuel block, and flows out from the outlets of the heat conductive pipes.
In one embodiment of the present invention, the number of the heat conductive pipes is more than 4.
In one embodiment of the invention, the brayton cycle apparatus includes a rotating shaft, the rotating shaft passes through the nuclear fuel block, a working blade is installed on the rotating shaft at a position close to the outlet of the heat pipe, a compression blade is installed on the rotating shaft at a position close to the inlet of the heat pipe, one end of the rotating shaft close to the working blade passes through the container and is connected with the generator, and one end of the rotating shaft close to the compression blade passes through the container and is connected with the compressor.
In one embodiment of the invention, the reactivity and radioactivity control ring is disposed coaxially with the axis of rotation of the brayton cycle device.
In one embodiment of the invention, the heat rejector comprises a heat absorption section and a heat release section, the heat absorption section of the heat rejector being located inside the container and the heat release section of the heat rejector being located outside the container.
In one embodiment of the invention, the inside of the container is provided with an aerodynamic flow channel, and the inside of the container is filled with supercritical carbon dioxide or nitrogen.
Compared with the prior art, the nuclear-driven Brayton device adopts a new nuclear power generation technology, namely a nuclear fission technology and a gas turbine technology are coupled, and the Brayton cycle is carried out by using supercritical carbon dioxide or nitrogen, so that the high-efficiency conversion from nuclear power to electric energy is realized, the system configuration is obviously simplified, the volume is small, the structure is simple, the reliability is high, the highway/ship/airplane/aerospace transportation requirements are met, the nuclear-driven Brayton device can be used in various scenes of sea, land, air and sky, and nuclear power guarantee is provided for data centers, remote mining areas, emergency rescue and the like, and the aim of the nuclear-driven Brayton device is fulfilled.
The features of the present invention will be apparent from the accompanying drawings and from the detailed description of the preferred embodiments which follows.
Drawings
FIG. 1 is a schematic structural diagram of a planar cross-section of a nuclear-driven Brayton apparatus of the present invention;
FIG. 2 is a schematic side sectional view of a nuclear-driven Brayton apparatus according to the present invention.
Fig. 3 is a side schematic view of a nuclear-driven brayton apparatus of the present invention.
Fig. 4 is a schematic diagram of a nuclear-driven brayton apparatus of the present invention for powering a ground base station.
Detailed Description
In order to make the technical means, the creation characteristics, the achievement purposes and the effects of the invention easy to understand, the invention is further explained below by combining the specific drawings.
Examples
As shown in fig. 1 to 4, the nuclear powered brayton apparatus of the present invention comprises a nuclear fuel block 1, a heat pipe 2, a brayton cycle apparatus 3, a reactivity and radioactivity control ring 4, a heat remover 5 and a container 6.
The energy source of the nuclear-driven Brayton device is from a nuclear fuel block 1, the nuclear fuel block 1 is cylindrical, the main components of the nuclear fuel block 1 comprise uranium, plutonium, thorium, graphite and the like according to a certain proportion, the enrichment degree of the uranium is between 6% and 19%, a plurality of through holes are distributed in the nuclear fuel block 1, and the through holes are used for inserting heat conduction pipes 2 penetrating through the nuclear fuel block 1.
The heat conductive pipes 2 penetrate the nuclear fuel block 1, the number of the heat conductive pipes 2 is more than 4, each heat conductive pipe 2 is provided with an inlet 21 and an outlet 22, and gas can flow in from the inlets 21 of the heat conductive pipes 2, be heated through the nuclear fuel block 1, and flow out from the outlets 2-2 of the heat conductive pipes 2.
The brayton cycle apparatus 3 includes a rotating shaft 31, the rotating shaft 31 passes through the nuclear fuel block 1, a working vane 32 is installed on the rotating shaft 31 at a position adjacent to the outlet 22 of the heat conductive pipe 2, a compression vane 33 is installed on the rotating shaft 31 at a position adjacent to the inlet 21 of the heat conductive pipe 2, one end of the rotating shaft 31 near the working vane 32 passes through the container 6 and is connected to a generator 34, and one end of the rotating shaft 31 near the compression vane 33 passes through the container 6 and is connected to a compressor 35.
A reactivity and radioactivity control ring 4 for controlling the reactivity and radioactivity of the reactor, containing neutron reflecting material and neutron moderating material, which can be configured in various ways; the reactivity and radioactivity control ring 4 is of the toroidal type, coaxial with the axis of rotation 31.
The heat absorbing section 51 of the heat rejector 5 is located inside the container 6 and the heat rejecting section 52 of the heat rejector 5 is located outside the container 6.
The main material of the container 6 is stainless steel, and an aerodynamic flow passage is designed inside the container 6 to reduce the flow resistance. The container 6 provides mechanical support for other components, acting as a secondary radioactive barrier, as a means of heat dissipation. The inside of the container 6 is filled with supercritical carbon dioxide or nitrogen, and when the container 6 is in a sealed state during working, the container 6 can be opened during maintenance or material changing.
The Brayton cycle of the nuclear driving Brayton device comprises four processes, namely gas absorbs heat, expands and does work, releases heat and compresses outwards.
When the device is started, the compressor 35 is started to drive the rotating shaft 31, the acting blades 32 and the compression blades 33 to rotate, and the device helps carbon dioxide or nitrogen in the container 6 to establish an initial Brayton cycle. The nuclear fuel block 1 generates heat through a nuclear fission reaction of uranium. Carbon dioxide or nitrogen flows through the nuclear fuel block 1 from the inlet 21 of the heat conduction pipe 2 to be heated, energy is obtained, the carbon dioxide or nitrogen flows out from the outlet 22, the acting blade 32 is pushed, the acting blade 32 rotates to drive the rotating shaft 31 to rotate, further the generator 34 is driven to generate electricity, the compression blade 33 is driven to rotate, carbon dioxide gas or nitrogen is sucked into the inlet 21 of the heat conduction pipe 2, self-sustaining system circulation of supercritical carbon dioxide or nitrogen in the container 6 is established, and the compressor 35 is withdrawn from working.
In the process of circulating the supercritical carbon dioxide or nitrogen in the container 6, the supercritical carbon dioxide or nitrogen flows through the heat exhauster 5, the heat is absorbed by the heat absorption section 51 in the heat exhauster 5, and the heat in the gas is led out to the heat release section 52, the heat release section 52 can generate power by using the released heat according to the needs of system configuration, and various configuration modes can be provided.
The nuclear-driven Brayton device has the advantages of simple system, small volume, compact structure, higher safety and reliability, capability of realizing autonomous operation, stronger shock resistance and impact resistance, capability of meeting the transportation requirements of ground/underwater/aviation/aerospace, and capability of providing nuclear power guarantee for data centers, remote mining areas, emergency rescue and the like, and the power output range of the nuclear-driven Brayton device is 1MWe to 10 MWe.
The foregoing shows and describes the general principles and broad features of the present invention and advantages thereof. It will be understood by those skilled in the art that the present invention is not limited to the embodiments described above, which are merely illustrative of the principles of the present invention, but that various changes and modifications may be made without departing from the spirit and scope of the invention, which is defined by the appended claims and their equivalents.
Claims (7)
1. The utility model provides a nuclear drive brayton device, its characterized in that, it includes the container the middle part of container is provided with nuclear fuel piece run through in the nuclear fuel piece and be provided with a plurality of heat pipes, nuclear fuel is connected with brayton cycle device soon, brayton cycle device's one end is connected with the generator, brayton cycle device's the other end is connected with the compressor, the outside of nuclear fuel piece is provided with reactivity and radioactivity control ring the outside of nuclear fuel piece still is provided with the heat exhauster.
2. A nuclear powered brayton apparatus as claimed in claim 1, wherein heat pipes extend through the nuclear fuel block, the heat pipes each having an inlet and an outlet, gas flowing from the inlet of the heat pipe, being heated through the nuclear fuel block and flowing from the outlet of the heat pipe.
3. The nuclear powered brayton apparatus of claim 1, wherein the number of heat pipes is greater than 4.
4. The nuclear powered brayton apparatus of claim 1, wherein the brayton cycle apparatus includes a shaft extending through the nuclear fuel block, wherein the shaft has power vanes mounted thereon adjacent to the outlet of the heat pipe, wherein the shaft has compression vanes mounted thereon adjacent to the inlet of the heat pipe, wherein one end of the shaft adjacent to the power vanes extends through the vessel and is connected to the generator, and wherein one end of the shaft adjacent to the compression vanes extends through the vessel and is connected to the compressor.
5. The nuclear powered brayton apparatus of claim 1, wherein the reactivity and radioactivity control ring is disposed coaxially with the rotational axis of the brayton cycle apparatus.
6. The nuclear powered brayton apparatus of claim 1, wherein the heat rejector comprises a heat absorption section and a heat release section, the heat absorption section of the heat rejector being located inside the vessel and the heat release section of the heat rejector being located outside the vessel.
7. A nuclear powered brayton apparatus as claimed in claim 1, wherein the interior of the vessel is provided with an aerodynamic flow path and is filled with supercritical carbon dioxide or nitrogen.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010871692.2A CN111946415A (en) | 2020-08-26 | 2020-08-26 | Nuclear drive brayton device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010871692.2A CN111946415A (en) | 2020-08-26 | 2020-08-26 | Nuclear drive brayton device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN111946415A true CN111946415A (en) | 2020-11-17 |
Family
ID=73367870
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202010871692.2A Withdrawn CN111946415A (en) | 2020-08-26 | 2020-08-26 | Nuclear drive brayton device |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN111946415A (en) |
-
2020
- 2020-08-26 CN CN202010871692.2A patent/CN111946415A/en not_active Withdrawn
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| CB02 | Change of applicant information |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
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| CB02 | Change of applicant information | ||
| WW01 | Invention patent application withdrawn after publication |
Application publication date: 20201117 |
|
| WW01 | Invention patent application withdrawn after publication |