CN103187107B - A kind of grid of nuclear fuel element with enhancement mode hybrid blade - Google Patents
A kind of grid of nuclear fuel element with enhancement mode hybrid blade Download PDFInfo
- Publication number
- CN103187107B CN103187107B CN201310011973.0A CN201310011973A CN103187107B CN 103187107 B CN103187107 B CN 103187107B CN 201310011973 A CN201310011973 A CN 201310011973A CN 103187107 B CN103187107 B CN 103187107B
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- grid
- enhancement mode
- hybrid blade
- mode hybrid
- grid strip
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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
Abstract
The invention provides a kind of grid of nuclear fuel element with enhancement mode hybrid blade, the sidewall of each grid strip is equipped with upper and lower two firm convex, and two firm convex between a spring, to clamp fuel rod; Its below in each grid strip or above have groove, adjacent cells band is connected by groove top-bottom cross; Two corresponding enhancement mode hybrid blades are provided with, to mix the fluid flow through above grid strip point of crossing; Described enhancement mode hybrid blade is enclosed construction; Axis below grid strip point of crossing within the scope of 1 ~ 20mm is provided with chamber, realizes between grid strip fixing by carrying out welding at chamber place.Enhancement mode hybrid blade of the present invention and band infall form closed region, and what significantly improve hybrid blade convection cell mixes disturbance.By arranging welding chamber below hybrid blade, guarantee the overall mechanical strength of mixing grillwork.
Description
Technical field
The present invention relates to fuel assembly technology, particularly relate to a kind of grid of nuclear fuel element with enhancement mode hybrid blade.
Background technology
Fuel assembly is the critical component of pressurized-water reactor reactor core, and it produces heat energy and this heat energy is passed to cooling medium.Fuel assembly heat energy is produced by fuel rod, and fuel rod is slender rod shaped structure, forms primarily of the some cylindrical pellet of outer tubular shell encapsulates.Fuel rod runs through fuel assembly vertically, carries out axis and located lateral by grid spacer.Each fuel assembly axially spaced-apart is furnished with several grid spacers, and each grid spacer intersects composition by multiple sheeting strip, the sidewall of each grid is furnished with spring or just convexly supports fuel rod.By the welding of band square crossing place, reinforcing strengthening is carried out to the structure of grid.
Grid spacer can be divided into end screen work and mixing grillwork two kinds.End screen work mainly carries out clamping action to fuel rod, guarantees the firm supporting of fuel rod.Mixing grillwork is divided into again intermediate grid and middle mixing grillwork two kinds, and intermediate grid is clamped fuel rod by spring-firm convex formula, and middle mixing grillwork is supported fuel rod by just convex-firm convex formula.Bending mixing fin is all furnished with, by mixing the overall heat transfer property improving fuel element to the fluid flowing through fuel rod above mixing grillwork band.
At present, advanced pressurized water reactor fuel assembly mixing grillwork is all furnished with hybrid blade in order to improve the overall heat transfer property of fuel assembly in the world.To the west of room and Fa Matong fuel assembly screen work stir and make muddy the wing and be designed to example, except guide pipe and gauge pipe grid positions, each band infall is all furnished with hybrid blade for mixing fluid (as shown in Figure 1, 2), but because the mutual infall of band must carry out the overall mechanical strength welding to improve screen work, therefore hybrid blade has the welding that wicket facilitates screen work band infall, and current PWR fuel assembly mixing fin in the world all adopts similar designs substantially.Due to the existence of welding window, a part of fluid is by welding window by-pass flow, and what reduce hybrid blade to a certain extent mixes performance.
Summary of the invention
The object of the present invention is to provide a kind of grid of nuclear fuel element with enhancement mode hybrid blade, it can improve the Gating Area of hybrid blade thus enhance fluid mixes performance.
Realize the technical scheme of the object of the invention: a kind of grid of nuclear fuel element with enhancement mode hybrid blade, this fuel assembly grid forms network by some grid strip cross connections, the sidewall of each grid strip is equipped with upper and lower two firm convex, and two firm convex between a spring, to clamp fuel rod; Its below in each grid strip or above have groove, adjacent cells band is connected by groove top-bottom cross; Two corresponding enhancement mode hybrid blades are provided with, to mix the fluid flow through above grid strip point of crossing; Described enhancement mode hybrid blade is enclosed construction; Axis below grid strip point of crossing within the scope of 1 ~ 20mm is provided with chamber, and chamber can be circle, square or special-shaped, realizes between grid strip fixing by carrying out welding at chamber place.
Have a grid of nuclear fuel element for enhancement mode hybrid blade as above, the enhancement mode hybrid blade described in it is enclosed construction and is not with window, and enhancement mode hybrid blade and grid strip together form closed region and mix by fluid.
Have a grid of nuclear fuel element for enhancement mode hybrid blade as above, the width of the groove described in it is between 0.2mm ~ 0.8mm, and length is between 5 ~ 40mm.
Effect of the present invention is: the grid of nuclear fuel element with enhancement mode hybrid blade of the present invention, and its enhancement mode hybrid blade and band infall form closed region, and what significantly improve hybrid blade convection cell mixes disturbance.Simultaneously by carrying out shape optimum to hybrid blade, adding the Gating Area of hybrid blade, further increasing the heat transfer property of screen work.By arranging welding chamber below hybrid blade, guarantee the overall mechanical strength of mixing grillwork.
Accompanying drawing explanation
Fig. 1 is western room fuel assembly mixing fin schematic diagram;
Fig. 2 is Fa Matong fuel assembly mixing fin schematic diagram;
Fig. 3 is enhancement mode hybrid blade vertical view;
Fig. 4 is enhancement mode hybrid blade stereographic map;
Fig. 5 is the grid of nuclear fuel element band schematic diagram with enhancement mode hybrid blade.
In figure: 1---spring; 2---just convex; 3---groove; 4---chamber; 5---enhancement mode hybrid blade.
Embodiment
Below in conjunction with the drawings and specific embodiments, a kind of grid of nuclear fuel element with enhancement mode hybrid blade of the present invention is further described.
As shown in Figures 3 to 5, a kind of grid of nuclear fuel element with enhancement mode hybrid blade of the present invention, it forms fenestral fabric by some grid strip cross connections.
It is equipped with upper and lower two firm convex 2 on the sidewall of each grid strip, and a spring 1 between two firm convex 2, to clamp fuel rod.
Below each grid strip or above have groove 3, adjacent cells band is connected to form grid by groove 3 top-bottom cross.The width of described groove 3 is between 0.2mm ~ 0.8mm, and length is between 5 ~ 40mm.
Above grid strip point of crossing, be fixedly connected with two corresponding enhancement mode hybrid blades 5, the coolant fluid flow through is mixed, form eddy current, thus strengthen the heat transfer property by rear fluid.Described enhancement mode hybrid blade 5 is enclosed construction, is not with window, and enhancement mode hybrid blade 5 and grid strip together form closed region and mix by fluid.
Within the scope of the below 1 ~ 20mm of grid strip point of crossing, axis is provided with chamber 9, by welding at chamber 9 place, realizes between grid strip fixing, the physical strength of grid entirety is reinforced.Chamber 9 can be circle, square or special-shaped.
Claims (2)
1. one kind has the grid of nuclear fuel element of enhancement mode hybrid blade, this fuel assembly grid forms network by some grid strip cross connections, the sidewall of each grid strip is equipped with upper and lower two firm convex (2), and the spring (1) be positioned between two firm convex (2), to clamp fuel rod; It is characterized in that:
The below of each grid strip or above have groove (3), adjacent cells band by groove (3) top-bottom cross connect;
Two corresponding enhancement mode hybrid blades (5) are provided with, to mix the fluid flow through above grid strip point of crossing; Described enhancement mode hybrid blade (5) is enclosed construction;
Axis below grid strip point of crossing within the scope of 1 ~ 20mm is provided with chamber (9), chamber (9) can be circle, square or special-shaped, realizes between grid strip fixing by carrying out welding at chamber (9) place;
Described enhancement mode hybrid blade (5) is for enclosed construction and be not with window, and enhancement mode hybrid blade (5) and grid strip together form closed region and mix by fluid.
2. a kind of grid of nuclear fuel element with enhancement mode hybrid blade according to claim 1, is characterized in that: the width of described groove (3) is between 0.2mm ~ 0.8mm, and length is between 5 ~ 40mm.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201310011973.0A CN103187107B (en) | 2013-01-14 | 2013-01-14 | A kind of grid of nuclear fuel element with enhancement mode hybrid blade |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201310011973.0A CN103187107B (en) | 2013-01-14 | 2013-01-14 | A kind of grid of nuclear fuel element with enhancement mode hybrid blade |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN103187107A CN103187107A (en) | 2013-07-03 |
| CN103187107B true CN103187107B (en) | 2016-01-27 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN201310011973.0A Active CN103187107B (en) | 2013-01-14 | 2013-01-14 | A kind of grid of nuclear fuel element with enhancement mode hybrid blade |
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| CN (1) | CN103187107B (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| UA123207C2 (en) * | 2016-12-29 | 2021-03-03 | Акционєрноє Общєство "Твел" | Nuclear reactor fuel assembly |
| KR102117496B1 (en) * | 2019-10-14 | 2020-06-01 | 한전원자력연료 주식회사 | Spacer grid of a nuclear fuel assembly having simple shape structure |
| CN113059063B (en) * | 2021-04-22 | 2023-03-24 | 宁波康迪普瑞模具技术有限公司 | Mold design method and processing method of grid straps |
Citations (4)
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| CN101377964A (en) * | 2007-08-27 | 2009-03-04 | 韩电原子力燃料株式会社 | Support grillwork with rowboat-shaped spring for preventing frottage of fuel rod |
| CN101770821A (en) * | 2008-12-26 | 2010-07-07 | 韩电原子力燃料株式会社 | Support grid having a layout of mixing blades for realizing hydraulic balance |
| CN102568632A (en) * | 2012-03-02 | 2012-07-11 | 中科华核电技术研究院有限公司 | Screenwork for nuclear fuel component and mixing stick for screenwork |
| CN203070780U (en) * | 2013-01-14 | 2013-07-17 | 上海核工程研究设计院 | Nuclear fuel component grid with reinforced mixing blades |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH05126986A (en) * | 1991-10-23 | 1993-05-25 | Mitsubishi Nuclear Fuel Co Ltd | Key for inserting and removing fuel rod and inserting and removing method for fuel rod in and from support grid by use of the key |
| FR2736190B1 (en) * | 1995-06-29 | 1997-10-10 | Framatome Sa | GRID SPACER OF A FUEL ASSEMBLY FOR A NUCLEAR REACTOR AND FUEL ASSEMBLY |
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2013
- 2013-01-14 CN CN201310011973.0A patent/CN103187107B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101377964A (en) * | 2007-08-27 | 2009-03-04 | 韩电原子力燃料株式会社 | Support grillwork with rowboat-shaped spring for preventing frottage of fuel rod |
| US20100098208A1 (en) * | 2007-08-27 | 2010-04-22 | Korea Nuclear Fuel Co., Ltd. | Anti-fretting Wear Spacer Grid With Canoe-Shaped Spring |
| CN101770821A (en) * | 2008-12-26 | 2010-07-07 | 韩电原子力燃料株式会社 | Support grid having a layout of mixing blades for realizing hydraulic balance |
| CN102568632A (en) * | 2012-03-02 | 2012-07-11 | 中科华核电技术研究院有限公司 | Screenwork for nuclear fuel component and mixing stick for screenwork |
| CN203070780U (en) * | 2013-01-14 | 2013-07-17 | 上海核工程研究设计院 | Nuclear fuel component grid with reinforced mixing blades |
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| CN103187107A (en) | 2013-07-03 |
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Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. Address before: 200233 No. 29, Hong Cao Road, Xuhui District, Shanghai. Patentee before: Shanghai Nuclear Engineering Research & Design Institute |
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| CP01 | Change in the name or title of a patent holder |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
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| CP01 | Change in the name or title of a patent holder |