GB2092817A - Fuel rod support grid - Google Patents

Fuel rod support grid Download PDF

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Publication number
GB2092817A
GB2092817A GB8127231A GB8127231A GB2092817A GB 2092817 A GB2092817 A GB 2092817A GB 8127231 A GB8127231 A GB 8127231A GB 8127231 A GB8127231 A GB 8127231A GB 2092817 A GB2092817 A GB 2092817A
Authority
GB
United Kingdom
Prior art keywords
grid
strap
support grid
straps
fuel rods
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.)
Withdrawn
Application number
GB8127231A
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
CBS Corp
Original Assignee
Westinghouse Electric Corp
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Westinghouse Electric Corp filed Critical Westinghouse Electric Corp
Publication of GB2092817A publication Critical patent/GB2092817A/en
Withdrawn legal-status Critical Current

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Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/34Spacer grids
    • G21C3/348Spacer grids formed of assembled non-intersecting strips
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Fuel Cell (AREA)
  • Butt Welding And Welding Of Specific Article (AREA)

Abstract

A grid for the support of nuclear fuel rods (1) arranged in a triangular array is formed by concentric rings (4) of straps (3) joined by radially arranged web sections (22). <IMAGE>

Description

SPECIFICATION Fuel rod support grid This invention relates to a new design for a support grid for triangular arrays of nuclear fuel rods, especially for hexagonal fuel assemblies for sodium-cooled fast reactors.
The core of a nuclear reactor usually consists of a grouping of fuel assemblies. Each fuel assembly is a grouping of cylindrical fuel rods which are arranged and supported by grids which are spaced axially along the fuel assembly. The support grids define the geometric pattern of cells for the fuel rods and maintain the correct spacing between rods.
Some nuclear reactor designs specify hexagonal fuel assemblies, with fuel rods arranged in a triangular array. A triangular array of rods is defined herein as a geometric pattern of rods in which three imaginary lines joining the centers of any three mutually adjacent rods in the assembly form an equilateral triangle. The triangular array is repetitious such that the family of all imaginary triangles formed by the centers of all possible groups of three mutually adjacent rods in the assembly consists of congruent triangles. The prior art provides grids for triangular arrays, but these, as shown below, have fabrication and technical disadvantages.
Hexagonal grids for a triangular array of rods consists of stacks of many deeply corrugated straps which stack is wrapped with a strap which then forms the enclosing member of the grid.
The stacking of corrugated straps results in the creation of double walls at periodic iocations in the grid. These double walls constitute flow restrictions in the final fuel assembly.
The depth of the corrugations in a strap may vary during manufacturing due, for example, to stamping die wear. Experience has shown these variations in depth to be trending rather than statistical, such that all straps in a manufactured batch may have a depth slightly deeper (or shallower) than designed. In the stacking operation presently used to construct grids, the deviations are cumulative, such that the height of the fina grid becomes distorted. This distortion problem originates at the strap stamping stage, but is only manifested later in the stacking stage of fabrication at which time the only capability to adjust to dimensional variations is the flexibility of the dimples. The practical result is that the sum of the cumulative deviations occasionally exceeds the dimple flexibility such that some rods cannot be inserted and the entire grid must be discarded.
A variety of manufacturing problems introduces variation in the exact placement of the dimples.
Such variation causes the rod to be more or less firmly secured than desired since even a slight shift in dimple position changes the distance between dimple contact points within a cell.
The fabrication of an annular grid (a grid with an empty center) is presently accomplished by the fabrication of a complete grid by stacking, cutting to a hexagonal outside shape and banding the outside surface, followed by the cutting out and removal of the center section, and banding of the inside hexagonal surface. The need to fabricate a complete grid is occasioned by the nature of the stacking method wherein the positioning, alignment, and support of a strap during welding is achieved by reference to the previously welded strap. The center section of the grid cannot be merely omitted since it has a fabrication process role. All the labor and material associated with this center region is presently wasted. Moreover, the resulting annular grid must have a least two rows of fuel rod holes such that a mechanically sound structure is maintained during the cutting operation.
It is therefore the principal object of the present invention to provide a grid supporting fuel rods in a triangular array, which grid can be manufactured without the stacking of straps and without the extra manufacturing operations to form annular or polygonal grids.
With this object in view, the present invention resides in a support grid for supporting nuclear fuel rods in a triangular array, consisting of interconnected metal straps, characterized in that said straps are arranged in the form of a plurality of rings disposed concentrically with a plurality of webs extending radially between adjacent rings and attached to adjacent rings thereby defining cells for receiving nuclear fuel rods such that the arrangement of cells is a triangular array.
This web and strap construction is applicable to fuel assemblies of polygonal cross-section, such as a hexagonal assembly. The preferred embodiments discussed below relate to hexagonal fuel assemblies.
The invention will become more readily apparent from the following description of preferred embodiments thereof shown in the accompanying drawings, in which: Figure 1 is a straight-strap embodiment of the invention; Figure 2 is a corrugated-strap embodiment of the invention; Figures 3 and 4 are views from Figure 1 as indicated, showing details of a double dimple; Figures 5 and 6 are views from Figure 2 as indicated, showing details of a single dimple; and Figures 7 and 8 show details of strap-to-web joints.
The present grid is shown in one embodiment in Figure 1 which shows a grid which supports thirty-seven cylindrical fuel rods 1 in a triangular array 2, forming a hexagonal assembly. The fiat straps 3 are formed into hexagonal rings 4 and welded at the corners 5. Radial webs 22 extend only between adjacent rings 4 and are welded to the flat straps 3 at each end of the web 22 forming cells 9 receiving the fuel rods 1. Double dimples 20 are integral with the web 22. The central cell 8 as shown in Figure 2 has dimples on the ring strap 4.
Figures 3 and 4 are views from Figure 1 which show the details of a double dimple 20. Figures 5 and 6 are views from Figure 2, which show the details of a single dimple 21 used to support the center rod in Figure 1. These dimples 20, 21 are structures integral to the strap or web material.
The present grid is not fabricated by the stacking method, and does not have a cumulative deviation problem. The grid can be assembled in a welding fixture which receives and temporarily supports the flat straps in the appropriate shape and location. Any variation in cell size is due to the characteristics of the welding fixture which can be detected and corrected before grid fabrication. The grid cell is completed by selection and installation of webs 22 such that a tight fit is accomplished. If butt weld joints as shown in Fig. 7 are used, the tight fit is achieved by the use of webs of slightly varying length, selected as needed. If a tongue and-groove weld joint as shown in Fig. 8 is used, the slip of the joint may be used to achieve the - tight fit such that only standard webs of a single size are needed.The final deviation in cell size is not cumulative over the grid. Obviously, any deviation existing will, in this new design, be within the adjustable range of the dimples in all but most unusual circumstances.
The flat-leaf, single and double dimples 20, 21 in this invention have line-contact areas 1 6 (Figures 1, 2) such that small deviations of fuel rod positions will not result in looseness.
The final grid has no double wells such that less flow restriction is anticipated.
The grid represented in Figure 1 is useful for certain applications, but cannot accommodate a fuel rod array in which the rods are closer together such that no iine-of-sight gap exists between rods adequate to admit the hexagonal rings 4 of flat strap 3.
Figure 2 is an embodiment of the invention in which corrugated straps 10 are used to fabricate the hexagonal rings 4. This grid has closely spaced fuel rods and has no line-of-sight clearance between adjacent rod rings.
In this design, the dimples occur in both web positions and strap positions. Figures 3, 4, 5, and 6 shaw details of the double dimples 20 (Figure 4) and single dimples 21 (Figures 5, 6). The center rod 8 may be supported by additional dimples over the three shown in Figure 2.
The construction technique for this second embodiment also involves the use of tongue-and groove joints or variable-length webs 22 each extending between adjacent rings 4 only. The same advantages as enumerated for the first embodiment apply. Deviations in the depth of the corrugations in the corrugated strap 10 will affect only cells adjacent to the particular strap, are not cumulative across the grid, and therefore within the adjustment range of the support dimples. The corrugated strap 10 may still be supported in a welding fixture since the use of tongue-in-groove joints or webs of varying length will provide the flexibility needed to adjust to the depth deviations.
Figure 2 shows single dimples 21 at location 23 which are unused. These are shown in the drawing since the use of standardized corrugated strap 10 for all hexagonal rings 4 results in the existence of these unneeded dimples. These may alternatively be omitted.
Both embodiments employ a web and strap construction which involves the joinder of web and strap members while these are supported and formed into the desired grid shape in a welding fixture comprising grooved plates and a welding machine. The strap sections are cut to the appropriate lengths to form the needed rings from previously prepared standard strap which has the dimples already constructed at appropriate intervals. The standard strap may be prepared in standard lengths or even in large rolls. The strap sections are inserted into the grooves in the welding fixture plates which shapes the strap into hexagonal rings of predetermined size. Web sections are inserted into welding fixture plate grooves which bring these webs into suitable proximity for welding to the rings.It is at this step when webs of slightly varying length are chosen to ensure affirmative contact with the rings and accommodate slight variations in ring-to-ring distance.
The welding may be by electron beam, resistance, laser or other methods.
Figure 7 shows a butt joint between the web and strap in which the strap 3 is resistancewelded at points 26 and welded by electron beam or other method at contact lines 27.
Figure 8 shows a tongue and groove joint between the web and strap, with welds at double contact lines 28. The tongue and groove method allows some flexibility of fit of a standard web length to accomodate smalrvariations in ring-toring spacing due to the slide of the tongue 30 in the groove 31 while still providing welding double contact lines 28. This feature may reduce or eiiminate the need for variable length web.
The grids in Figures 1 and 2 are shown for convenience to be for relatively small assemblies.
In practice, the grid can be adapted to support many more rods in larger assemblies.

Claims (4)

1. A support grid for supporting nuclear fuel rods in a triangular array, consisting of interconnected metal straps,'characterized in that said straps (4, 10) are arranged in the form of a plurality of rings disposed concentrically with a plurality of webs (22) extending radially between adjacent rings (4, 10) and attached to adjacent rings (4, 10) thereby defining cells for receiving nuclear fuel rods (1), such that the arrangement of cells (9, 18) is a triangular array.
2. A support grid as claimed in claim 1, characterized in that said concentric rings (4) are of corrugated straps (10) to provide for a closely spaced triangular array of fuel rods (1).
3. A support grid as claimed in claim 1 or 2, characterized in that said webs (22) are of varying length.
4. A support grid as claimed in claim 1, 2 or 3 characterized by spring dimples providing for a line-contact area (16) for said fuel rods (1).
GB8127231A 1981-02-10 1981-09-09 Fuel rod support grid Withdrawn GB2092817A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US23322681A 1981-02-10 1981-02-10

Publications (1)

Publication Number Publication Date
GB2092817A true GB2092817A (en) 1982-08-18

Family

ID=22876411

Family Applications (1)

Application Number Title Priority Date Filing Date
GB8127231A Withdrawn GB2092817A (en) 1981-02-10 1981-09-09 Fuel rod support grid

Country Status (4)

Country Link
JP (1) JPS57139692A (en)
DE (1) DE3139903A1 (en)
FR (1) FR2499750B1 (en)
GB (1) GB2092817A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0230613A2 (en) * 1985-12-25 1987-08-05 Hitachi, Ltd. Nuclear fuel assembly
WO1995026554A1 (en) * 1994-03-25 1995-10-05 Siemens Aktiengesellschaft Spacer with hexagonal interstices
US7163666B2 (en) * 2000-11-13 2007-01-16 Kawasaki Jukogyo Kabushiki Kaisha Thermally tolerant support structure for a catalytic combustion catalyst

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4869865A (en) * 1988-12-02 1989-09-26 General Electric Company Method of manufacturing nuclear fuel bundle spacers

Family Cites Families (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1082679B (en) * 1959-04-22 1960-06-02 Siemens Ag Spacer in the form of a bar for elements with a large number of elements
US3137638A (en) * 1959-05-23 1964-06-16 Siemens Ag Neutronic reactor fuel elements
US3142627A (en) * 1959-10-21 1964-07-28 Atomic Energy Authority Uk Fuel element assemblies
GB1094851A (en) * 1964-01-16 1967-12-13 Atomic Energy Authority Uk Improvements in or relating to grids for nuclear fuel elements
GB1081281A (en) * 1964-08-11 1967-08-31 Atomic Energy Authority Uk Nuclear reactor fuel element assemblies
DE2111349A1 (en) * 1971-03-10 1972-09-28 Siemens Ag Nuclear reactor fuel element
FR2208104A2 (en) * 1972-11-30 1974-06-21 Trepaud Georges Nuclear reactor heat exchanger - with central shaft giving access for tube installation and repair
GB2010567B (en) * 1977-12-19 1982-04-15 Atomic Energy Authority Uk Nuclear fuel subassemblies

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0230613A2 (en) * 1985-12-25 1987-08-05 Hitachi, Ltd. Nuclear fuel assembly
EP0230613A3 (en) * 1985-12-25 1988-01-13 Hitachi, Ltd. Nuclear fuel assembly
WO1995026554A1 (en) * 1994-03-25 1995-10-05 Siemens Aktiengesellschaft Spacer with hexagonal interstices
US7163666B2 (en) * 2000-11-13 2007-01-16 Kawasaki Jukogyo Kabushiki Kaisha Thermally tolerant support structure for a catalytic combustion catalyst

Also Published As

Publication number Publication date
FR2499750B1 (en) 1988-07-15
JPS57139692A (en) 1982-08-28
DE3139903A1 (en) 1982-09-02
FR2499750A1 (en) 1982-08-13
JPS648799B2 (en) 1989-02-15

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WAP Application withdrawn, taken to be withdrawn or refused ** after publication under section 16(1)