CN104766636B - A kind of nuclear fuel rod cools down the nested integral structure of heat pipe with center - Google Patents
A kind of nuclear fuel rod cools down the nested integral structure of heat pipe with center Download PDFInfo
- Publication number
- CN104766636B CN104766636B CN201510188176.9A CN201510188176A CN104766636B CN 104766636 B CN104766636 B CN 104766636B CN 201510188176 A CN201510188176 A CN 201510188176A CN 104766636 B CN104766636 B CN 104766636B
- Authority
- CN
- China
- Prior art keywords
- fuel rod
- nuclear fuel
- heat pipe
- center
- evaporator section
- 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.)
- Expired - Fee Related
Links
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 44
- 238000001816 cooling Methods 0.000 claims abstract description 35
- 239000000446 fuel Substances 0.000 claims abstract description 24
- 239000008188 pellet Substances 0.000 claims abstract description 12
- 238000009833 condensation Methods 0.000 claims abstract description 5
- 230000005494 condensation Effects 0.000 claims abstract description 5
- 239000007788 liquid Substances 0.000 claims abstract description 5
- 239000000463 material Substances 0.000 description 7
- 238000006243 chemical reaction Methods 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 3
- PEDCQBHIVMGVHV-UHFFFAOYSA-N Glycerine Chemical compound OCC(O)CO PEDCQBHIVMGVHV-UHFFFAOYSA-N 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000004744 fabric Substances 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000002485 combustion reaction Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 229910001338 liquidmetal Inorganic materials 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000010025 steaming Methods 0.000 description 1
- 230000001960 triggered effect Effects 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/334—Assembling, maintenance or repair of the bundles
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
- G21C3/12—Means forming part of the element for locating it within the 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses the nested integral structure that a kind of nuclear fuel rod cools down heat pipe with center, including center cooling heat pipe, the nuclear fuel rod of positive six face column structure, the evaporator section of central cooling tube is placed in the core bore in the middle part of the nuclear fuel rod.Central cooling tube is followed successively by the porous wick structure, liquid ring cavity, tube wall that central steam area, porosity are 0.69 from inside to outside.Central steam area includes evaporator section, adiabatic section, condensation segment successively from bottom to top in the axial direction, and the length of evaporator section is consistent with the length of nuclear fuel rod.The inside of nuclear fuel rod is that fuel pellet, outside are involucrum, and the tube wall of the evaporator section of center cooling heat pipe is designed with the involucrum on the inside of nuclear fuel rod core bore to be integrated.0.1mm gap is left between fuel pellet and involucrum.Compact in design, safe, good reliability, are particularly suitable for use in nuclear reactor for space and the small-sized nuclear reactor of other specific uses.
Description
Technical field
The present invention relates to a kind of nuclear power energy technology, more particularly to a kind of nuclear fuel rod nested the one of heat pipe is cooled down with center
Body structure.
Background technology
It is following to carry out space in the moon and other celestial body surfaces with the development and implementation of countries in the world survey of deep space plan
Construction of base is by with great science, military and political value.Space base is set up in the moon and other celestial body surfaces, it is first
First need solution is energy problem.And the mode such as solar cell and isotope battery is difficult to space base and meets powerful
Actual demand, therefore nuclear reactor for space is with the obvious advantage in terms of the energy supply of future space base.
The states such as the U.S., Russia, Japan generate keen interest to nuclear reactor for space, study and propose tens of
Nuclear reactor for space system schema is planted, the type of cooling includes heat pipe cooling, liquid metal cooling, gas cooling etc..Due to space
The complexity of Site environment, nuclear reactor for space reactor core should take passive cooling technology, and heat pipe cooling has optimal hot wink
State feedback performance, optimal reliability, minimum maintenance demand, therefore nuclear reactor for space design at present mostly uses heat pipe cold
But, the heat produced by fuel rod takes reactor core out of by cooling heat pipe, then provides energy supply by energy conversion system.
As shown in Figure 3 a, in the design of existing nuclear reactor for space, fuel rod is made into external diameter phase with cooling heat pipe
With it is cylindric, mode is adjacently positioned with cooling heat pipe using fuel rod.But, this arrangement is due to several by heat pipe
The constraint of what shape, certainly exists gap, causes filling fuels rate relatively low between fuel rod and heat pipe, and fuel rod and cooling heat
After gap between pipe is filled by structural material, cause the increase of nuclear reactor critical mass and reactor core gross mass.
The content of the invention
It is an object of the invention to provide the cooling of a kind of compact in design, safe, good reliability nuclear fuel rod and center
The nested integral structure of heat pipe.
The purpose of the present invention is achieved through the following technical solutions：
The nuclear fuel rod of the present invention cools down the nested integral structure of heat pipe, including center cooling heat pipe, core combustion with center
Charge bar, the evaporator section of the central cooling tube is placed in the core bore in the middle part of the nuclear fuel rod.
As seen from the above technical solution provided by the invention, nuclear fuel rod provided in an embodiment of the present invention and center are cold
But the nested integral structure of heat pipe, is placed in the core bore in the middle part of the nuclear fuel rod, cloth due to the evaporator section of central cooling tube
Compact, the safe, good reliability of office, is particularly suitable for use in nuclear reactor for space and the small-sized nuclear reaction of other specific uses
Heap.
Brief description of the drawings
Fig. 1 is that the radial direction for the nested integral structure that nuclear fuel rod provided in an embodiment of the present invention cools down heat pipe with center is cut
Face structural representation；
Fig. 2 is that the axial direction for the nested integral structure that nuclear fuel rod provided in an embodiment of the present invention cools down heat pipe with center is cut
Face structural representation；
Nuclear fuel rod and cooling heat pipe arrangement schematic diagram that Fig. 3 a are used for reactor core in the prior art；
Fig. 3 b are that nuclear fuel rod provided in an embodiment of the present invention is applied to the nested integral structure that center cools down heat pipe
The arrangement schematic diagram of Core Design.
In figure：
1st, fuel pellet, 2, involucrum, 3, liquid ring cavity, 4, porous wick structure, 5, central steam area, 6, evaporator section, 7, absolutely
Hot arc, 8, condensation segment, 9, nuclear fuel rod, 10, center cooling heat pipe (or cooling heat pipe).
Embodiment
The embodiment of the present invention will be described in further detail below.
The nested integral structure of nuclear fuel rod and center the cooling heat pipe of the present invention, its preferably embodiment
It is：
Including center cooling heat pipe, nuclear fuel rod, the evaporator section of the central cooling tube is placed in the middle part of the nuclear fuel rod
Core bore in.
The central cooling tube is followed successively by central steam area, porous wick structure, liquid ring cavity, tube wall from inside to outside.
The central steam area includes evaporator section, adiabatic section, condensation segment, the steaming successively from bottom to top in the axial direction
The length for sending out section is consistent with the length of nuclear fuel rod.
The porosity of the porous wick structure is 0.69.
The inside of the nuclear fuel rod is that fuel pellet, outside are involucrum, the pipe of the evaporator section of the center cooling heat pipe
Wall is integrated with the involucrum design on the inside of the nuclear fuel rod core bore.
0.1mm gap is left between the fuel pellet and the involucrum.
The nuclear fuel rod is positive six face column structure.
The nuclear fuel rod of the present invention cools down the nested integral structure of heat pipe with center, overcomes of the prior art lack
Point, compact in design, safe, good reliability are particularly suitable for use in nuclear reactor for space and the small cores of other specific uses
Reactor.The nested integral structure that this nuclear fuel rod cools down heat pipe with center can have in reactor core close arrangement
Effect ground improves the filling fuels degree of reactor core, reduces the critical mass of reactor core, makes so as to reduce structural material, shielding material
With the gross mass of reduction reactor core；Meanwhile, heat pipe arrangement relative density increase, it is possible to prevente effectively from single heat pipe failure is triggered
The problem of, reliability is high.The present invention realizes the nested integrated structure design that nuclear fuel rod cools down heat pipe with center, use
Passive compact design, can effectively improve the safety and reliability of reactor.
Center cooling heat pipe evaporator section absorbs the heat that fuel pellet is produced, and cools down heat pipe adiabatic section and cold by center
Solidifying section takes heat out of reactor core.0.1mm gap is left between fuel pellet and involucrum can store fission gas.
Compared with prior art, the beneficial effects of the invention are as follows：
(1) nuclear fuel rod be positive six face cylinder can compact Layout, so as to improve filling fuels degree, reduction nuclear reactor is critical
Quality, reduces heap core volume.
(2) use of structural material, shielding material is reduced, reactor core quality is reduced.
(3) increase of heat pipe arrangement relative density, can be prevented effectively from the problem of single heat pipe failure triggers, reliability
It is high.
Specific embodiment：
Exemplified by applied to nuclear reactor for space Core Design, nuclear fuel rod and center cool down projected life of heat pipe with
Core life is reference, without changing in core life.
As shown in accompanying drawing 1,2, center cooling heat pipe 10 is placed in the center of nuclear fuel rod 9, center cooling heat pipe evaporator section 6 and core
Fuel rod length is consistent, and center cooling heat pipe evaporator section 6 absorbs the heat that fuel pellet 1 is produced, and cools down heat pipe by center
Adiabatic section 7 and condensation segment 8 take heat out of reactor core.It is fuel pellet 1 in nuclear fuel rod 9, outer nuclear fuel rod 9 is fuel rod clad
2.0.1mm gap is left between fuel pellet and involucrum to store fission gas.Center cools down heat pipe shell and nuclear fuel rod
Interior involucrum design is integrated, and is the porous wick structure 4 that porosity is 0.69 in pipe, is liquid ring cavity 3 between liquid-sucking core and tube wall,
Steam dome 5 centered on heat pipe centre.
The present invention is applied to the effect of nuclear reactor for space Core Design as shown in Figure 3 b, the cloth of fuel rod and cooling heat pipe
Office is compacter relative to Core Design of the prior art as shown in Figure 3 a, improves filling fuels rate, reduces nuclear reaction
Heap critical mass, reduces heap core volume, while decreasing the use of structural material, shielding material, reduces reactor core quality.And
And, heat pipe arrangement relative density increase can be prevented effectively from the problem of single heat pipe failure triggers, reliability is high.
What the present invention was not elaborated partly belongs to techniques known.
The foregoing is only a preferred embodiment of the present invention, but protection scope of the present invention be not limited thereto,
Any one skilled in the art is in the technical scope of present disclosure, the change or replacement that can be readily occurred in,
It should all be included within the scope of the present invention.Therefore, protection scope of the present invention should be with the protection model of claims
Enclose and be defined.
Claims (3)
1. a kind of nuclear fuel rod and center cool down the nested integral structure of heat pipe, it is characterised in that including center cooling heat pipe,
Nuclear fuel rod, the evaporator section of the central cooling tube is placed in the core bore in the middle part of the nuclear fuel rod；
The central cooling tube is followed successively by central steam area, porous wick structure, liquid ring cavity, tube wall from inside to outside；
The central steam area includes evaporator section, adiabatic section, condensation segment, the evaporator section successively from bottom to top in the axial direction
Length it is consistent with the length of nuclear fuel rod；
The inside of the nuclear fuel rod is that fuel pellet, outside are involucrum, the tube wall of the evaporator section of the center cooling heat pipe with
Involucrum design on the inside of the nuclear fuel rod core bore is integrated；
The nuclear fuel rod is positive six face column structure.
2. nuclear fuel rod according to claim 1 cools down the nested integral structure of heat pipe with center, it is characterised in that institute
The porosity for stating porous wick structure is 0.69.
3. nuclear fuel rod according to claim 1 or 2 cools down the nested integral structure of heat pipe with center, its feature exists
In leaving 0.1mm gap between the fuel pellet and the involucrum.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510188176.9A CN104766636B (en) | 2015-04-20 | 2015-04-20 | A kind of nuclear fuel rod cools down the nested integral structure of heat pipe with center |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510188176.9A CN104766636B (en) | 2015-04-20 | 2015-04-20 | A kind of nuclear fuel rod cools down the nested integral structure of heat pipe with center |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN104766636A CN104766636A (en) | 2015-07-08 |
| CN104766636B true CN104766636B (en) | 2017-07-25 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201510188176.9A Expired - Fee Related CN104766636B (en) | 2015-04-20 | 2015-04-20 | A kind of nuclear fuel rod cools down the nested integral structure of heat pipe with center |
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| CN106653107B (en) * | 2016-09-26 | 2018-09-07 | 南华大学 | A kind of liquid metal cooling passive accident afterheat discharge system of pool reactor |
| US10559389B2 (en) * | 2017-02-06 | 2020-02-11 | Battell Energy Alliance, LLC | Modular nuclear reactors including fuel elements and heat pipes extending through grid plates, and methods of forming the modular nuclear reactors |
| US10910116B2 (en) | 2017-03-16 | 2021-02-02 | Battelle Energy Alliance, Llc | Nuclear reactors including heat exchangers and heat pipes extending from a core of the nuclear reactor into the heat exchanger and related methods |
| CN107919175A (en) * | 2017-11-07 | 2018-04-17 | 肇庆鼎湖檀树电子科技有限公司 | Fuel rod cooling system |
| CN108511092A (en) * | 2018-06-14 | 2018-09-07 | 华南理工大学 | A kind of integral structure that nuclear fuel element is nested with circuit parallel type cooling heat pipe |
| RU2687288C1 (en) * | 2018-08-16 | 2019-05-13 | Акционерное общество "Государственный научный центр Российской Федерации - Физико-энергетический институт имени А.И. Лейпунского" | Nuclear reactor active zone |
| CN109887618B (en) * | 2019-04-11 | 2023-04-11 | 哈尔滨工程大学 | Nuclear reactor with radially arranged heat pipes |
| CN110211709B (en) * | 2019-06-14 | 2020-08-11 | 北京卫星环境工程研究所 | Heat pipe type alkali metal conversion integrated reactor |
| CN111081398A (en) * | 2019-12-31 | 2020-04-28 | 中国核动力研究设计院 | Integrated fast spectrum reactor core structure for gapless solid heat transfer |
| CN111081391B (en) * | 2019-12-31 | 2022-06-28 | 中国核动力研究设计院 | Reactor core structure of heat pipe reactor fuel element adopting hexagonal prism cladding |
| CN111951986B (en) * | 2020-08-20 | 2021-04-30 | 大连理工大学 | Nested structure of nuclear fuel rod and hot-pressing conversion heat transfer device |
| CN113130097B (en) * | 2021-03-05 | 2022-04-12 | 安徽中科超核科技有限公司 | High-efficiency heat-conducting heat pipe reactor fuel element |
| CN115354271A (en) * | 2022-08-22 | 2022-11-18 | 中国科学技术大学 | System and method for retarding corrosion of bundle cladding of lead-cooled fast reactor fuel assembly |
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| CN2879089Y (en) * | 2006-02-28 | 2007-03-14 | 上海科宏变电设备有限公司 | Inner heating type hot tube |
| CN102354539A (en) * | 2011-09-15 | 2012-02-15 | 西安交通大学 | Annular fuel element and annular fuel supercritical water reactor |
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| CN103994682A (en) * | 2014-05-07 | 2014-08-20 | 江苏科技大学 | Heat pipe and manufacturing method thereof |
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2015
- 2015-04-20 CN CN201510188176.9A patent/CN104766636B/en not_active Expired - Fee Related
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5408510A (en) * | 1994-04-11 | 1995-04-18 | The Babcock & Wilcox Company | Thermionic nuclear reactor with flux shielded components |
| CN2879089Y (en) * | 2006-02-28 | 2007-03-14 | 上海科宏变电设备有限公司 | Inner heating type hot tube |
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| Publication number | Publication date |
|---|---|
| CN104766636A (en) | 2015-07-08 |
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Granted publication date: 20170725 |