CN109817354A - A kind of underwater nuclear reactor power supply of multikilowatt - Google Patents
A kind of underwater nuclear reactor power supply of multikilowatt Download PDFInfo
- Publication number
- CN109817354A CN109817354A CN201811653486.3A CN201811653486A CN109817354A CN 109817354 A CN109817354 A CN 109817354A CN 201811653486 A CN201811653486 A CN 201811653486A CN 109817354 A CN109817354 A CN 109817354A
- Authority
- CN
- China
- Prior art keywords
- power supply
- heat pipe
- fuel
- multikilowatt
- nuclear reactor
- 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.)
- Pending
Links
- 239000000446 fuel Substances 0.000 claims abstract description 40
- 229910008894 U—Mo Inorganic materials 0.000 claims abstract description 9
- 229910052770 Uranium Inorganic materials 0.000 claims description 7
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims description 7
- ZLMJMSJWJFRBEC-UHFFFAOYSA-N Potassium Chemical compound [K] ZLMJMSJWJFRBEC-UHFFFAOYSA-N 0.000 claims description 5
- 229910052700 potassium Inorganic materials 0.000 claims description 5
- 239000011591 potassium Substances 0.000 claims description 5
- 238000009833 condensation Methods 0.000 claims description 3
- 230000005494 condensation Effects 0.000 claims description 3
- 238000010276 construction Methods 0.000 claims description 3
- 238000002485 combustion reaction Methods 0.000 claims description 2
- 238000000034 method Methods 0.000 claims description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 7
- 230000035755 proliferation Effects 0.000 abstract description 4
- 230000009286 beneficial effect Effects 0.000 abstract description 2
- 239000000463 material Substances 0.000 description 8
- 230000007246 mechanism Effects 0.000 description 5
- 238000010586 diagram Methods 0.000 description 4
- 238000012546 transfer Methods 0.000 description 4
- 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 description 3
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 description 3
- 239000006096 absorbing agent Substances 0.000 description 3
- 238000006243 chemical reaction Methods 0.000 description 3
- 238000013461 design Methods 0.000 description 3
- 229910052739 hydrogen Inorganic materials 0.000 description 3
- 239000001257 hydrogen Substances 0.000 description 3
- 125000004435 hydrogen atom Chemical class [H]* 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 239000013535 sea water Substances 0.000 description 3
- 229910052708 sodium Inorganic materials 0.000 description 3
- 239000011734 sodium Substances 0.000 description 3
- 239000002918 waste heat Substances 0.000 description 3
- 229910052726 zirconium Inorganic materials 0.000 description 3
- 229910052580 B4C Inorganic materials 0.000 description 2
- 239000000956 alloy Substances 0.000 description 2
- 229910052790 beryllium Inorganic materials 0.000 description 2
- ATBAMAFKBVZNFJ-UHFFFAOYSA-N beryllium atom Chemical compound [Be] ATBAMAFKBVZNFJ-UHFFFAOYSA-N 0.000 description 2
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical group B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 description 2
- 230000005611 electricity Effects 0.000 description 2
- 230000003647 oxidation Effects 0.000 description 2
- 238000007254 oxidation reaction Methods 0.000 description 2
- 230000003068 static effect Effects 0.000 description 2
- FRWYFWZENXDZMU-UHFFFAOYSA-N 2-iodoquinoline Chemical compound C1=CC=CC2=NC(I)=CC=C21 FRWYFWZENXDZMU-UHFFFAOYSA-N 0.000 description 1
- 230000009471 action Effects 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- LTPBRCUWZOMYOC-UHFFFAOYSA-N beryllium oxide Inorganic materials O=[Be] LTPBRCUWZOMYOC-UHFFFAOYSA-N 0.000 description 1
- 150000001875 compounds Chemical class 0.000 description 1
- 230000001276 controlling effect Effects 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007812 deficiency Effects 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000005530 etching Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000000977 initiatory effect Effects 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- KTEXACXVPZFITO-UHFFFAOYSA-N molybdenum uranium Chemical compound [Mo].[U] KTEXACXVPZFITO-UHFFFAOYSA-N 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
Classifications
-
- 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The present invention relates to a kind of underwater nuclear reactor power supplys of multikilowatt, including fuel, control drum, radial reflector, safety rod channel, heat pipe and axial reflecting layer;The fuel is columnar U-Mo Alloy fuel, is provided with safety rod channel and heat pipe channel;The heat pipe surrounds the safety rod channel, is inserted into the heat pipe channel;The radial reflector is set on the outside of the fuel, and the axial direction reflecting layer is set to the fuel both ends;The control drum is uniformly arranged in the radial reflector.Beneficial effects of the present invention are as follows: using U-Mo Alloy fuel, the risk of nuclear proliferation can be avoided by using the fuel of low enrichment;This programme exports reactor core heat using heat pipe, eliminates the pressurization water loop of two larger sizes of TRIOS, and heat pipe has the advantages that passive, non-single point failure.
Description
Technical field
The present invention relates to nuclear power engineering fields, and in particular to a kind of underwater nuclear reactor power supply of multikilowatt.
Background technique
According to disclosed data, up to the present, there are no underwater kilowatt of order reactions for having obtained practical application in the world
Heap power supply.In terms of relevant reactor power supply design scheme, reacted under water with the TRIOS for having the U.S. that this programme is closer to
Heap power source design and the Kilopower space based reactor power source design in the U.S..
The D.T.Allen in the U.S. etc. proposes a kind of entitled in document " Undersea Thermionic Reactors "
The fixed reactor power supply in the seabed of TRIOS.The reactor uses two kinds of fuel rods, is 9 thermionic fuel elements respectively
With 106 uranium hydrogen zirconium fuel elements, wherein thermionic fuel element is for generating electricity, and gross electric capacity is about 5 kilowatts, uranium hydrogen zirconium fuel
Element then as driving fuel, provides enough reactivity for reactor core, while the intrinsic negative temperature coefficient of the fuel can be in thing
Therefore it is provided safeguard in situation for the safety of reactor.There are two water loop of pressurizeing, primary Ioops to use axis for reactor system setting
To double-layer shell structure, height is higher, takes the heat of reactor out of by the Natural Circulation of water, and pass heat through heat exchanger
It is handed to the pressure (hydraulic) water of secondary circuit, secondary circuit is incited somebody to action equally by the way of Natural Circulation eventually by an external heat exchanger
Heat transfer is to seawater.
Program technical maturity with higher and realizability are provided simultaneously with good inherent safety features, but same
When the program there is also some shortcomingss: firstly, the generating efficiency of system is very low, only 9 thermionic fuel elements
Heat is utilized, and the heat needs of remaining 106 uranium hydrogen zirconium fuel element are all discharged as waste heat, system power generation
Efficiency only about 0.83%;In addition, the reactor power-supply system is relatively complicated, and system bulk is more huge, and power supply is most
Major diameter reaches 5.7 meters, and total height reaches 9.16 meters.
The multikilowatt nuclear reactor for space power supply that the U.S. currently develops the entitled Kilopower of a type (can refer to document
“Development of NASA’s Small Fission Power System for Science and Human
Exploration "), which, as fuel, exports reactor core by 8 sodium heat pipes using the high degree of enrichment U-Mo Alloy of made of one piece
Heat, and produced electricl energy by 8 opposed two-by-two free-piston type stirling generators, waste heat is emitted into outside too by radiator
Sky, about 1 kilowatt of the power supply gross electric capacity.
Type reactor power-supply system is small in size, light-weight, conversion efficiency of thermoelectric is high for this, system structure is very simple, has
Higher reliability, if but be used for underwater environment, still have several drawbacks place: firstly, reactor core uses highly concentrated uranium fuel, this
Risk with nuclear proliferation;In addition, the system operating temperature is high, fuel maximum temperature reaches about 1200K, the operation temperature of sodium heat pipe
Degree reaches 1050K, and at such high temperatures, if running in non-vacuum environment under water, many components have oxidation, corrosion etc. and ask
Topic, is unfavorable for the service life of power supply.
In view of this, the present invention is specifically proposed.
Summary of the invention
In view of the deficiencies in the prior art, the object of the present invention is to provide a kind of underwater nuclear reactor electricity of multikilowatt
Source, the risk problem of nuclear proliferation when being at least able to solve applied to underwater environment.
Technical scheme is as follows:
A kind of underwater nuclear reactor power supply of multikilowatt, including fuel, control drum, radial reflector, safety rod channel, heat pipe
With axial reflecting layer;The fuel is columnar U-Mo Alloy fuel, is provided with safety rod channel and heat pipe channel;It is described
Heat pipe surrounds the safety rod channel, is inserted into the heat pipe channel;The radial reflector is set on the outside of the fuel, institute
It states axial reflecting layer and is set to the fuel both ends;The control drum is uniformly arranged in the radial reflector.
Further, the underwater nuclear reactor power supply of above-mentioned multikilowatt, -235 degree of enrichment of uranium of the U-Mo Alloy fuel
It is 19.75%.
Further, the underwater nuclear reactor power supply of above-mentioned multikilowatt, the working medium of the heat pipe are potassium.
Further, the underwater nuclear reactor power supply of above-mentioned multikilowatt, the condensation segment and heat exchange of heat pipe of the heat pipe connect
It connects, the heat exchange of heat pipe is connect with thermo-electric generation element.
Further, the underwater nuclear reactor power supply of above-mentioned multikilowatt, the power supply are set in power supply pressure vessel, institute
It states thermo-electric generation element and is affixed on the power supply internal pressure vessel walls.
Further, the underwater nuclear reactor power supply of above-mentioned multikilowatt, the power supply pressure vessel outside and the temperature difference
The corresponding part of generating element is provided with radiating fin.
Further, the underwater nuclear reactor power supply of above-mentioned multikilowatt, power supply pressure vessel lower part are provided with support
Structure.
Further, the underwater nuclear reactor power supply of above-mentioned multikilowatt, between the power supply and the power supply pressure vessel
It is provided with shielded layer.
Beneficial effects of the present invention are as follows:
1, using U-Mo Alloy fuel, the risk of nuclear proliferation can be avoided by using the fuel of low enrichment;
2, this programme exports reactor core heat using heat pipe, eliminates the pressurization water loop of two larger sizes of TRIOS, and
Heat pipe has the advantages that passive, non-single point failure;
3, this programme uses potassium heat pipe, and running temperature is in 800K or so, and the sodium heat pipe compared with Kilopower is much lower, material
Material oxidation and etching problem also opposite more easily processing;In addition, this programme is using static thermo-electric generation mode, efficiency compared with
The Stirling transfer efficiency of Kilopower is low, but vibration, the noise etc. that static thermo-electric generation is existing there is no Stirling conversion
Problem, and have higher reliability.
Detailed description of the invention
Fig. 1 is the core structure schematic diagram of the underwater nuclear reactor power supply of multikilowatt of the invention.
Fig. 2 is the reactor core longitudinal profile structure schematic of the underwater nuclear reactor power supply of multikilowatt of the invention.
Fig. 3 is the schematic diagram that heat pipe is connect with thermo-electric generation element in the present invention.
Fig. 4 is the magnified partial view in Fig. 3.
Fig. 5 is the structural schematic diagram that the underwater nuclear reactor power supply of multikilowatt of the invention is installed on the power supply pressure vessel
(omitting shielded layer).
Fig. 6 is the structural schematic diagram that the underwater nuclear reactor power supply of multikilowatt of the invention is installed on the power supply pressure vessel
(including shield).
Fig. 7 is the installation detailed schematic of temperature difference generating element and power supply pressure vessel in Fig. 5.
In above-mentioned attached drawing, 1, radial reflector;2, control drum;3, drum absorber is controlled;4, fuel;5, safety rod channel;
6, heat pipe;7, safe rod drive mechanism;8, drum driving mechanism is controlled;9, safety rod;10, axial reflecting layer;11, heat pipe heat exchanging
Device;12, thermo-electric generation element;13, radiating fin;14, power supply pressure vessel;15, support construction;16, shielded layer.
Specific embodiment
The present invention is described in detail below with reference to embodiment.
As depicted in figs. 1 and 2, the present invention provides a kind of underwater nuclear reactor power supplys of multikilowatt, including fuel 4, control
Drum 2, radial reflector 1, safety rod channel 5, heat pipe 6 and axial reflecting layer 10;The fuel 4 is the combustion of columnar U-Mo Alloy
Material, is provided with safety rod channel 5 and heat pipe channel;The heat pipe 6 surrounds the safety rod channel 5, is inserted into the heat pipe
In channel;The radial reflector 1 is set to 4 outside of fuel, and the axial direction reflecting layer 10 is set to 4 liang of the fuel
End, using beryllium oxide material;The control drum 2 is uniformly arranged in the radial reflector 1.In the present embodiment, the uranium molybdenum
- 235 degree of enrichment of uranium of alloy fuel is 19.75%.Heap in-core arranges 12 heat pipes 6, and 6 working medium of heat pipe is potassium;Radial reflector 1
Material is beryllium, wherein being disposed with 4 control drums 2, control 2 material of main part of drum is beryllium, controls and sets on direction of the drum 2 far from fuel 4
It is equipped with control drum absorber 3, control drum 3 material of absorber is boron carbide, and each control drum 2 is by 1 control drum driving
Mechanism 8 is regulated and controled;Reactor center is safety rod channel 5, and wherein 9 material of safety rod is boron carbide, by safety rod driving machine
Structure 7 is controlled.
As shown in Figure 3 and Figure 4, the condensation segment of the heat pipe 6 is connect with heat exchange of heat pipe 11, the heat exchange of heat pipe 11 with
The hot end of thermo-electric generation element 12 is directly connected to.As shown in figure 5, the power supply is set in power supply pressure vessel 14, temperature difference hair
The cold end of electric device 12 is then directly connected with the inner wall of power supply pressure vessel 14.14 outside of power supply pressure vessel and the temperature
The corresponding part of poor generating element 12 is provided with radiating fin 13 (referring to Fig. 7), for increasing the heat exchange property between seawater.
14 lower part of power supply pressure vessel is provided with support construction 15 for increasing the integrally-built stability of power supply.The power supply with
Shielded layer 16 is provided between the power supply pressure vessel 14 (setting of shielded layer is referring to Fig. 6).Thermo-electric generation element 12 uses
The running temperature of skutterudite compound material, the type generating element can match with the running temperature of potassium heat pipe 6.
When power initiation, safety rod 9 is extracted out reactor core by safe rod drive mechanism 7, and adjusted by controlling drum driving mechanism 8
Drum 2 is controlled to position appropriate, so that reactor is reached critical and generates stable power.The heat that fuel 4 generates is through heat transfer
Mode is transferred to heat pipe 6, and heat pipe 6 takes heat out of, and transfers heat to thermo-electric generation element 12 through heat exchange of heat pipe 11 and use
In producing electricl energy, waste heat is transferred directly to the inner wall of power supply pressure vessel 14 by the cold end of thermo-electric generation element 12, and the heat is most
It by the outer wall of power supply pressure vessel 14 and is arranged in the radiating fin 13 of outer wall eventually and is transferred to seawater in a manner of free convection.
The reactor power supply can be disposed at seabed, and long-term, stable electric energy is provided for other instruments equipment.
Obviously, various changes and modifications can be made to the invention without departing from essence of the invention by those skilled in the art
Mind and range.If in this way, belonging to the model of the claims in the present invention and its equivalent technology to these modifications and changes of the present invention
Within enclosing, then the present invention is also intended to include these modifications and variations.
Claims (8)
1. a kind of underwater nuclear reactor power supply of multikilowatt, it is characterised in that: including fuel (4), control drum (2), radial reflector
(1), safety rod channel (5), heat pipe (6) and axial reflecting layer (10);The fuel (4) is columnar U-Mo Alloy fuel,
In be provided with safety rod channel (5) and heat pipe channel;The heat pipe (6) surrounds the safety rod channel (5), is inserted into the heat pipe
In channel;The radial reflector (1) is set on the outside of the fuel (4), and the axial direction reflecting layer (10) is set to the combustion
Expect (4) both ends;The control drum (2) is uniformly arranged in the radial reflector (1).
2. the underwater nuclear reactor power supply of multikilowatt as described in claim 1, it is characterised in that: the U-Mo Alloy fuel
- 235 degree of enrichment of uranium is 19.75%.
3. the underwater nuclear reactor power supply of multikilowatt as described in claim 1, it is characterised in that: the working medium of the heat pipe (6) is
Potassium.
4. the underwater nuclear reactor power supply of multikilowatt a method according to any one of claims 1-3, it is characterised in that: the heat pipe (6)
Condensation segment is connect with heat exchange of heat pipe (11), and the heat exchange of heat pipe (11) connect with thermo-electric generation element (12).
5. the underwater nuclear reactor power supply of multikilowatt as claimed in claim 4, it is characterised in that: the power supply is set to power supply pressure
In force container (14), the thermo-electric generation element (12) is affixed on power supply pressure vessel (14) inner wall.
6. the underwater nuclear reactor power supply of multikilowatt as claimed in claim 5, it is characterised in that: the power supply pressure vessel (14)
External part corresponding with thermo-electric generation element (12) is provided with radiating fin (13).
7. the underwater nuclear reactor power supply of multikilowatt as claimed in claim 6, it is characterised in that: the power supply pressure vessel (14)
Lower part is provided with support construction (15).
8. the underwater nuclear reactor power supply of multikilowatt as claimed in claim 5, it is characterised in that: the power supply and the power supply pressure
Shielded layer (16) are provided between force container (14).
Priority Applications (1)
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CN201811653486.3A CN109817354A (en) | 2018-12-29 | 2018-12-29 | A kind of underwater nuclear reactor power supply of multikilowatt |
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CN201811653486.3A CN109817354A (en) | 2018-12-29 | 2018-12-29 | A kind of underwater nuclear reactor power supply of multikilowatt |
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Family
ID=66603115
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CN201811653486.3A Pending CN109817354A (en) | 2018-12-29 | 2018-12-29 | A kind of underwater nuclear reactor power supply of multikilowatt |
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Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN110310751A (en) * | 2019-06-29 | 2019-10-08 | 西安交通大学 | A kind of nuclear reactor power supply of the two-way insertion reactor core of heat pipe |
CN110729067A (en) * | 2019-10-31 | 2020-01-24 | 哈尔滨工程大学 | Nuclear power supply system for underwater unmanned submersible vehicle |
CN112117016A (en) * | 2020-08-24 | 2020-12-22 | 中国原子能科学研究院 | Heat transfer scheme for core of heat pipe reactor |
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Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN110310751A (en) * | 2019-06-29 | 2019-10-08 | 西安交通大学 | A kind of nuclear reactor power supply of the two-way insertion reactor core of heat pipe |
CN110729067A (en) * | 2019-10-31 | 2020-01-24 | 哈尔滨工程大学 | Nuclear power supply system for underwater unmanned submersible vehicle |
CN112117016A (en) * | 2020-08-24 | 2020-12-22 | 中国原子能科学研究院 | Heat transfer scheme for core of heat pipe reactor |
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