CN102270511A - Tubular positioning grid for pressurized water reactor double-sided cooling fuel rod - Google Patents
Tubular positioning grid for pressurized water reactor double-sided cooling fuel rod Download PDFInfo
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- CN102270511A CN102270511A CN2011102000816A CN201110200081A CN102270511A CN 102270511 A CN102270511 A CN 102270511A CN 2011102000816 A CN2011102000816 A CN 2011102000816A CN 201110200081 A CN201110200081 A CN 201110200081A CN 102270511 A CN102270511 A CN 102270511A
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- fuel rod
- grid
- water reactor
- sided cooling
- grid cell
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- 239000000446 fuel Substances 0.000 title claims abstract description 89
- 238000001816 cooling Methods 0.000 title claims abstract description 17
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 17
- 125000006850 spacer group Chemical group 0.000 claims abstract description 35
- 238000004080 punching Methods 0.000 claims abstract description 8
- 238000003466 welding Methods 0.000 claims abstract description 6
- 230000015572 biosynthetic process Effects 0.000 claims description 5
- 238000004519 manufacturing process Methods 0.000 abstract description 6
- 238000005516 engineering process Methods 0.000 description 5
- 238000000034 method Methods 0.000 description 4
- 239000003758 nuclear fuel Substances 0.000 description 3
- 229910001093 Zr alloy Inorganic materials 0.000 description 2
- 229910045601 alloy Inorganic materials 0.000 description 2
- 239000000956 alloy Substances 0.000 description 2
- 238000010276 construction Methods 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 239000004449 solid propellant Substances 0.000 description 2
- 241000216843 Ursus arctos horribilis Species 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 239000013078 crystal Substances 0.000 description 1
- 230000007812 deficiency Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 239000011159 matrix material Substances 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 238000007493 shaping process Methods 0.000 description 1
- 230000003319 supportive effect Effects 0.000 description 1
- 230000001052 transient effect Effects 0.000 description 1
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Classifications
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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
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- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a tubular spacer grid of a pressurized water reactor double-sided cooling fuel rod, which is formed by welding quasi-square grid units, wherein four corners of each grid unit are bulged towards the center, convex surfaces bulged towards the center are contacted with the excircle of the fuel rod to support and position the fuel rod, and the grid units are formed by punching or drawing round tubes. The tubular positioning grid of the pressurized water reactor double-sided cooling fuel rod is simple in structure, low in manufacturing process technical difficulty, better in economy and safety and convenient to install.
Description
Technical field
The present invention relates to the nuclear reactor field of engineering technology, the tubular grid spacer of the two-sided cooling fuel rod of particularly a kind of presurized water reactor.
Background technology
In the nuclear power plant reactor operational process, the performance of nuclear fuel is one of key factor that influences nuclear reactor safety and economy.Aspect consideration power density, margin of safety, unloading burnup and cost of electricity-generating, fuel temperature all is a very important references index.In order to reduce the fuel element failure rate and to improve assembly life-span, people constantly improve the quality of fuel and cladding materials, as using new zirconium alloy, big crystal grain pellet etc.Yet the benefit people of raising power density are familiar with less, and it can improve the economic benefit of nuclear power plant greatly.Usually, nuclear fuel all is designed to columned, the about 9mm of diameter, and the volume ratio of water and fuel is about 1.7, and cooling medium flows through outside involucrum.The 4th generation the presurized water reactor annular fuel inside and outside two involucrums are arranged, cooling medium is taken away the heat that fuel sends from inside and outside both sides simultaneously.Compare with traditional filled circles column fuel, the benefit of annular fuel is under very high linear power density, and the operational centre temperature of fuel is still very low, and the energy of storing in the fuel is less, fission gas discharges less.It is better to be expected under normal operation and the transient condition fuel performance, can reach higher burnup.Fig. 1 is the structural representation of solid fuel rod, and Fig. 2 is the structural representation of annular fuel rod.
Though the fuel rod of two-sided cooling can improve cooling performance and fuel stability and obtain high burnup and output power, yet, for the fuel rod that makes two-sided cooling and existing pressurized water reactor core adapt, what the physical dimension of annular fuel assembly must be with existing presurized water reactor is consistent; So the rod footpath of the annular fuel rod of two-sided cooling increases to some extent, and brings interrod spacing to increase, the excellent gap between adjacent like this two fuel rods becomes narrow, and the gap between fuel rod and the screen work band reduces.
Pressurized-water reactor nuclear power plant with million kilowatt, traditional cylindric fuel rod is to arrange (as shown in Figure 3) in the mode of 17 * 17-25, represent fuel rod with circle grey background color, that diameter is less among Fig. 3, fuel rod diameter D is 9.5mm, interrod spacing P is 12.63mm, the rod gap is 3.11mm, and P/D is 1.3264.Do not represent the control rod guide pipe with circle background color, that diameter is bigger.The grid spacer of assembly is formed by the band right-angled intersection of thin slice, form 289 square grid, wherein 264 fuel rod grid and 24 guide pipe grid, the former supports fuel rod, insert guide pipe in the latter and also and between the guide pipe be welded to connect, one of the center is neutron fluence rate supervision pipe grid.Generally along assembly vertically, be furnished with 8 grid spacers with certain interval, by their realize fuel rod axially and radial location.Each fuel rod grid has 6 strong points to each fuel rod, wherein two is longitudinal spring, they lay respectively on two sides of fuel rod grid, formation is to 2 elastic supports of fuel rod, there are 4 to be pit, they be positioned in couples two springs about, and respectively on two other side, constitute rigid support to fuel rod.If use the fuel rod of two-sided cooling, suppose to arrange (as shown in Figure 4) by 13 * 13-9, the annulus of band black matrix look is represented two-sided cooling fuel rod among the figure, do not represent the control rod guide pipe with the circle of background color, the outer envelope diameter D of ring-type fuel rod is 15.367mm, P is 16.51mm, and excellent gap is 1.143mm, and P/D is 1.0734.If the grid spacer of assembly is still formed by the band right-angled intersection, comprise fuel rod grid and guide pipe grid, so, because the excellent gap of ring-type fuel rod only is 1.143mm, the beam thickness of supposing grid spacer is 0.3mm, and rod will be reduced to 0.42mm from 1.45mm with the gap of screen work band so.
Tradition PWR fuel assembly grid spacer histogram as shown in Figure 5, each fuel rod is inserted in the square grid of being made up of screen work band intersection, wherein a projection is arranged towards the three curved springs fuel rod cylindrical, longitudinally, strip on two sides, constitute 2 elastic supports fuel rod.Then respectively there is the recess of two projectioies towards the fuel rod cylindrical two other side, constitutes 4 rigid supports to fuel rod.Each fuel rod is subjected to the support and the location of two springs and four recesses.If the screen work band is to be made by nickel-base alloy, spring and recess just are stamped to form by band itself, and two recesses are positioned at the upper and lower side of three curved springs of strip, and towards opposite with spring, be that they play a supportive role to the fuel rod of band both sides respectively, Here it is usually said monometallic screen work.If the screen work band is to be made by zircaloy, spring is fitted on the screen work band promptly usually said bimetal grid after just being formed by other nickel-base alloy arrowband punching press with spot welding method.Obviously,,, do not have enough spatial placement longitudinal springs, can not use existing fuel rod supporting construction because narrow gaps between the fuel rod dative grizzly bar band is less than 0.5mm for the fuel rod of two-sided cooling.
In U.S. Patent Publication instructions US2010/0027734A1, a kind of grid spacer of fuel rod is disclosed, this grid spacer also is to adopt the band right-angled intersection to form, the support component of screen work moves to the diagonal line place of grid, though solved the support of presurized water reactor annular fuel rod and the problem of location like this, but this grid spacer structure is complicated, the manufacturing process difficulty is big, wherein the elastic support of the band of Cai Yonging adopts press-working spring, elastic support is subjected to causing easily under the influence of long-term souring lax in the reactor operation process, reduce the resiliency supported ability, cause the instability of fuel rod.And this ribbon construction complex process, Production Time is longer, installs complicated.
There is pertinent literature to disclose the grid spacer of reactor in the prior art at present, in the patent documentations such as Chinese patent instructions CN86102224A, CN87100909A, CN1140885A, CN1820326A grid spacer is disclosed for example, all to be tabular materials of adopting band or similar band assemble in the mode of right-angled intersection this class grid spacer, grid spacer is made cumbersome, and uses at existing s Nuclear Plant design.And the support of nuclear reactor fuel rod and location are the cores of reactor safety operation, must seek fuel rod support and orientation problem that new solution improves the annular fuel assembly for this reason, but not have reference to spell out the direction of dealing with problems so far as yet.Therefore the grid spacer of researching and developing a kind of high security is the active demand of China's presurized water reactor annular fuel assembly.
Summary of the invention
The present invention has overcome the deficiency that existing grid spacer is used in the annular fuel assembly, a kind of simple in structure, the manufacture craft technical difficulty is low, economy is better, the two-sided cooling fuel rod of presurized water reactor installed better is convenient in security tubular grid spacer is provided.
In order to solve the problems of the technologies described above, the present invention is achieved by the following technical solutions:
The tubular grid spacer of the two-sided cooling fuel rod of a kind of presurized water reactor, key is, grid spacer is formed by the grid cell welding of a plurality of dead squares, the place, four angles of each grid cell is to central protuberance, convex surface to central protuberance contacts with the periphery of fuel rod, formation is to the support and the location of fuel rod, and described grid cell is formed by pipe punching press or drawing.
The present invention is all right:
The place, four angles of described each grid cell is to central protuberance, convex surface to central protuberance contacts with the periphery of fuel rod to locating to central protuberance at four angles of each grid cell, form the convex surface of four quadrant shapes or circular arc or flat shape, wherein circle or circular arc or plane contact with the periphery of fuel rod.Described grid cell is that a punching press of pipe or the drawing of 0.2mm～0.3mm forms by wall thickness.
Compared with prior art, the invention has the beneficial effects as follows:
The present invention has cancelled the structural design of traditional lattice of straps, has broken those skilled in the art's traditional design thought, and structure of the present invention is simpler, and security is higher.Because grid cell is formed by pipe punching press or drawing, the manufacturing process technology difficulty reduces, and economy is better; The grid cell welding forms, and the assembling of screen work is more prone to.The present invention moves on to the diagonal line place of grid with the support component of screen work, makes the support of screen work and location structure more firm simultaneously.
Description of drawings
The schematic cross-section of Fig. 1 solid fuel rod
The schematic cross-section of Fig. 2 annular fuel rod
The fuel assembly sectional view that the fuel rod that Fig. 3 is traditional is arranged
The sectional view of Fig. 4 annular fuel arrangements of components
The PWR fuel assembly grid spacer histogram that Fig. 5 is traditional
The shaft side figure of Fig. 6 circular convex grid cell
The vertical view of Fig. 7 circular convex grid cell
The shaft side figure of Fig. 8 arc convex surface grid cell
The vertical view of Fig. 9 arc convex surface grid cell
The shaft side figure of Figure 10 plane convex surface grid cell
The vertical view of Figure 11 plane convex surface grid cell
The structural representation of the grid spacer that Figure 12 circular convex grid cell is formed
The vertical view of the grid spacer that Figure 13 circular convex grid cell is formed
The structural representation of the grid spacer that Figure 14 arc convex surface grid cell is formed
The vertical view of the grid spacer that Figure 15 arc convex surface grid cell is formed
The structural representation of the grid spacer that Figure 16 plane convex surface grid cell is formed
The vertical view of the grid spacer that Figure 17 plane convex surface grid cell is formed
Embodiment
Below in conjunction with accompanying drawing and embodiment the present invention is described in further detail:
The present invention is formed by the grid cell welding of a lot of dead squares, and the place, four angles of each grid cell forms convex surface to central protuberance, and convex surface contacts with the periphery of fuel rod, forms support and location to fuel rod.Square grid in this enforcement adopts the manufacturing of shaping round tube technology, designed the grid cell of three kinds of forms altogether, quadrant shape convex surface grid cell as shown in Figure 6 and Figure 7, arc convex surface grid cell such as Fig. 8 and shown in Figure 9, plane convex surface grid cell as shown in Figure 10 and Figure 11.Wherein each accurate square grid is formed by a punching press of pipe or the drawing of wall thickness 0.2mm～0.3mm.
Grid spacer is according to the demand of reactor inner structure, and through being welded to form square grid frame, grid cell can have different physical dimensions by a plurality of independently grid cells, and the incircle of its formation should be equal to the outside diameter of fuel rod.The negative camber of grid cell or plane contact with the fuel rod periphery, thereby play the effect of supporting and locating fuel rod.
Embodiment 1
Grid spacer is made up of a lot of circular convex grids, and the place, four angles of square grid is the quadrant of circular direction projection outside fuel rod, and they form the support of fuel rod.The screen work form as shown in Figure 12 and Figure 13.
Grid spacer is made up of a lot of arc convex surface grid cells, and the place, four angles of grid is the circular-arc of towards fuel rod outside circular direction projection, the support of their formation fuel rods.Screen work form such as Figure 14, shown in Figure 15.
Embodiment 3
Grid spacer is made up of a lot of plane convex surface grid cells, and the place, four angles of grid cell is towards fuel rod cylindrical direction plane shape, and they form the support of fuel rod.Screen work form such as Figure 16, shown in Figure 17.
Claims (3)
1. the tubular grid spacer of the two-sided cooling fuel rod of presurized water reactor, it is characterized in that, grid spacer is formed by the grid cell welding of dead square, the place, four angles of each grid cell is to central protuberance, convex surface to central protuberance contacts with the periphery of fuel rod, formation is to the support and the location of fuel rod, and described grid cell is formed by pipe punching press or drawing.
2. the tubular grid spacer of the two-sided cooling fuel rod of a kind of presurized water reactor according to claim 1, it is characterized in that, the place, four angles of described each grid cell is to central protuberance, convex surface to central protuberance contacts with the periphery of fuel rod to locating to central protuberance at four angles of each grid cell, form the convex surface of four quadrant shapes or circular arc or flat shape, wherein circle or circular arc or plane contact with the periphery of fuel rod.
3. the tubular grid spacer of the two-sided cooling fuel rod of a kind of presurized water reactor according to claim 1 is characterized in that, described grid cell is that a punching press of pipe or the drawing of 0.2mm～0.3mm forms by wall thickness.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2011102000816A CN102270511A (en) | 2011-07-18 | 2011-07-18 | Tubular positioning grid for pressurized water reactor double-sided cooling fuel rod |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2011102000816A CN102270511A (en) | 2011-07-18 | 2011-07-18 | Tubular positioning grid for pressurized water reactor double-sided cooling fuel rod |
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| Publication Number | Publication Date |
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| CN102270511A true CN102270511A (en) | 2011-12-07 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2011102000816A Pending CN102270511A (en) | 2011-07-18 | 2011-07-18 | Tubular positioning grid for pressurized water reactor double-sided cooling fuel rod |
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Cited By (20)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106601311A (en) * | 2016-12-29 | 2017-04-26 | 华北电力大学 | Nuclear fuel element |
| CN108511093A (en) * | 2018-04-16 | 2018-09-07 | 西安交通大学 | A kind of PWR Fuel cluster high-temperature heating clamping experimental provision |
| CN109074878A (en) * | 2016-12-29 | 2018-12-21 | Tvel股份公司 | Reactor fuel assemblies |
| CN109585038A (en) * | 2017-09-28 | 2019-04-05 | 华龙国际核电技术有限公司 | A kind of burnable poison assembly and reactor core |
| CN109935361A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of cooling annular fuel assembly of square double-sided |
| CN109935367A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of spacer grid of fuel assembly and fuel assembly of band buckle |
| CN109935349A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of cooling annular fuel assembly of the fixed square double-sided in fuel rod lower end |
| CN109935362A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of bottom device of fuel assembly and its bottom nozzle and fuel assembly |
| CN109935359A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of fuel assembly skeleton connection structure and fuel assembly skeleton |
| CN109935365A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of band tubular type lattice cell spacer grid of fuel assembly |
| CN109935368A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of spacer grid of fuel assembly and fuel assembly with angle plug-in unit |
| CN109935364A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of guiding pipe connected pipe, upper tube socket and fuel assembly skeleton |
| CN109935360A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of fuel assembly guide pipe and upper tube socket connection structure and fuel assembly skeleton |
| CN109935369A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of lattice cell, spacer grid of fuel assembly and fuel assembly |
| CN109935358A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of annular fuel rod limiting pellet axial float using spring |
| CN109935370A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of spacer grid of fuel assembly and fuel assembly with plug-in unit |
| CN110926562A (en) * | 2019-12-16 | 2020-03-27 | 西安交通大学 | Top end positioning piece suitable for flow measurement of rod bundle sub-channel outlet |
| CN111415762A (en) * | 2020-04-02 | 2020-07-14 | 哈尔滨工程大学 | Full visual body structure of annular fuel element flow |
| CN111613351A (en) * | 2020-06-04 | 2020-09-01 | 中国核动力研究设计院 | Stress fatigue resistant single-metal positioning grid for pressurized water reactor fuel assembly |
| CN115171923A (en) * | 2022-06-24 | 2022-10-11 | 上海核工程研究设计院有限公司 | Grid structure of fuel assembly and positioning grillwork |
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Cited By (29)
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| CN106601311A (en) * | 2016-12-29 | 2017-04-26 | 华北电力大学 | Nuclear fuel element |
| CN106601311B (en) * | 2016-12-29 | 2018-07-24 | 华北电力大学 | A kind of nuclear fuel element |
| CN109074878B (en) * | 2016-12-29 | 2023-04-14 | Tvel股份公司 | Reactor fuel assembly |
| CN109074878A (en) * | 2016-12-29 | 2018-12-21 | Tvel股份公司 | Reactor fuel assemblies |
| CN109585038A (en) * | 2017-09-28 | 2019-04-05 | 华龙国际核电技术有限公司 | A kind of burnable poison assembly and reactor core |
| CN109935369A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of lattice cell, spacer grid of fuel assembly and fuel assembly |
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| CN109935365A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of band tubular type lattice cell spacer grid of fuel assembly |
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| CN109935361A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of cooling annular fuel assembly of square double-sided |
| CN109935358A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of annular fuel rod limiting pellet axial float using spring |
| CN109935367A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of spacer grid of fuel assembly and fuel assembly of band buckle |
| CN109935370B (en) * | 2017-12-19 | 2024-07-19 | 中国原子能科学研究院 | Fuel assembly positioning grid with plug-in component and fuel assembly |
| CN109935369B (en) * | 2017-12-19 | 2024-07-02 | 中国原子能科学研究院 | Cell, fuel assembly positioning grid and fuel assembly |
| CN109935361B (en) * | 2017-12-19 | 2024-05-31 | 中国原子能科学研究院 | Square double-sided cooling annular fuel assembly |
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| CN108511093A (en) * | 2018-04-16 | 2018-09-07 | 西安交通大学 | A kind of PWR Fuel cluster high-temperature heating clamping experimental provision |
| CN110926562A (en) * | 2019-12-16 | 2020-03-27 | 西安交通大学 | Top end positioning piece suitable for flow measurement of rod bundle sub-channel outlet |
| CN111415762A (en) * | 2020-04-02 | 2020-07-14 | 哈尔滨工程大学 | Full visual body structure of annular fuel element flow |
| CN111613351B (en) * | 2020-06-04 | 2022-05-20 | 中国核动力研究设计院 | Stress fatigue resistant single-metal positioning grid for pressurized water reactor fuel assembly |
| CN111613351A (en) * | 2020-06-04 | 2020-09-01 | 中国核动力研究设计院 | Stress fatigue resistant single-metal positioning grid for pressurized water reactor fuel assembly |
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| CN115171923B (en) * | 2022-06-24 | 2024-06-07 | 上海核工程研究设计院股份有限公司 | Fuel assembly grid structure and positioning grid |
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