Abstract: A fuel rod capturing support grid having a spring and arch design which provides performance improvements over current or previous designs by decreasing fuel rod fretting wear. The disclosed spring and arch designs follow the contour of the fuel rod, thus providing an increased, substantially arc-shaped area of contact between the fuel rod and the spring tabs and arches.

Abstract: A fuel assembly grid (10) in which the height dimension of the grid strips (A,B,C,D) varies along the strip length, so that channels or cells (24',28) immediately surrounding the guide tube (30) define a relatively longer flow path, than channels that are relatively remote from the guide tube. In particular, the grids have a first plurality of four-walled first cells (24) for receiving and supporting respective fuel rods (26) and a second plurality of four-walled second cells (28) that are larger in cross-sectional area than, and interspersed among, the first cells, for receiving respective guide tubes (30). The improvement according to the present invention, provides that the height dimension (H2) of each strip (C) that defines walls of particular first and second cells is greater at the walls of the particular second cells, than at the walls of at least some of the particular first cells.

Abstract: A fuel assembly (1) for a nuclear reactor of pressurized-water type with a number of fuel rods (2) retained into a bundle by means of spacers (3) between a top nozzle (4) and a bottom nozzle (5) which includes a plurality of openings for a coolant flow to the fuel rods (2). A partial fuel box (7) is providing at at least the lower part of the fuel assembly and extending from the bottom nozzle (5) and at least up past the lowermost ordinary spacer (3) of the bundle.

Abstract: A zirconium based alloy plate of low irradiation growth, containing not more than 5 wt % Sn and/or not more 5 wt % Nb, and the balance Zr of not less than 90 wt %. The alloy plate has a texture that <0001> orientation (Fr value) with respect to direction perpendicular to the surface of the plate ranges from 0.20 to 0.50. This alloy plate is effective in being used to form a fuel channel box. Also a fuel assembly using this channel box is provided in which the crystal orientation of the zirconium alloy is made random by a heat treatment. Specifically, by the heat treatment, the Fr, Ft, and Fl values thereof are set to 0.25 to 0.50, 0.25 to 0.36, and 0.25 to 0.36, respectively.

Abstract: There is provided a method of manufacturing a grid for a nuclear fuel assembly, the grid having at least two crossed sets of mutually parallel plates which define cells, some of which receive guide tubes and others receive fuel rods, the plates being provided with boss means for limiting the amount of movement available to the rods relative to the nodes of a regular array. The plates are formed with bosses projecting radially inwardly into each cell for receiving a fuel rod by such an amount that they define a passage having a size at least equal to a minimum diameter of the fuel rods. Then the bosses are deformed radially outwardly for imparting to each passage a predetermined radial size, slightly higher than that of one fuel rod and determined by a gauge.

Abstract: A nuclear reactor core assembly includes a support plate having a plurality of inlets for channeling water to a core lattice fixedly joined thereto. The lattice includes a plurality of flow channels, each including a respective separately removable fuel bundle. In a preferred embodiment, the core lattice includes a plurality of flow dividers joined together for allowing unrestrained expansion and contraction thereof, and which prevent crossflow of water therebetween.

Abstract: A tool guide plate for use in a rod consolidation system for the consolidation of spent fuel rods within a storage container. The system utilizes a robot in conjunction with long reach tools to remove spent fuel rods from an array of rods in a rod assembly and to transfer them to a rod consolidation holder. The tool guide plate has a plurality of apertures shaped to receive the end of a tool and less than the number of rods in the array and has means located on the guide plate for indexing the apertures over the rod position to provide tool access to all of the rods in the array, the apertures providing access to a plurality of rod positions in each index position.

Abstract: Grid strips for a nuclear fuel assembly grid have elongated weld tabs. The weld tabs are bent against the strips along the intersection with an adjacent orthogonal strip. The tabs are dimensioned and positioned to initially extend substantially the entire length of the intersection of two grid strips. The tabs are then melted during the welding process.

Abstract: To provide quality assurance inspection of the dimensional characteristics of cells to be incorporated in spacers utilized in nuclear fuel bundles to establish critical spacings between fuel rods, a cell is placed in a fixture dimensioned to gauge the outer dimensions of the cell. A fuel rod-simulating pin is then inserted through the cell to rest on fuel rod-positioning stops formed on the cell. "Go, no go" feeler gauges then check the dimensions of the gaps between the fixture and pin.

Abstract: The additional mixing grid has no belt and comprises at least two sets of crossed plates that are fixed to each other at their cross-points, the plates being fitted with fins for stirring the coolant, and delimiting cells, some for receiving guide tubes and the others for receiving fuel rods. Each plate is provided, on each of the faces of those internal cells that receive the rods, with bosses that project sufficiently little to leave radial clearance for the rods passing through the cells and the projection of the bosses is proportioned relative to the projection of the fins so that in the event of bending vibration the rods come into contact with the bosses without reaching the fins, the lengths of the plates being such that the footprint of the additional grid is less than the footprint of the polygon constituting the virtual envelope of the rods.

Abstract: A mixing grid for use in a pressurized reactor comprises at least two sets of crossed fixed together at their cross-points, delimiting cells, some for receiving fuel rods and the others for receiving guide tubes, the plates being provided with coolant stirring fins extending the plates downstream and disposed to deflect the coolant transversely to its general flow direction, each plate being provided with abutment means projecting inwardly from each of the faces of the cells for receiving fuel rods, thereby delimiting a passage that is larger than the size of the rods but small enough to prevent a rod contained in the cell coming into contact with the fins. In each wall the abutment means comprise two portions of plate that are cut out and deformed into a scoop-shape, and that are offset relative to each other in the coolant flow direction, with the scoops projecting in opposite directions and tending to cause coolant to pass from one cell to another.

Abstract: A grid for use on a PWR fuel element comprises a belt of hexagonal shape and three sets of plates secured to the belt. The plates in each set are mutually parallel and are at an angle of 120.degree. with the plates of the two other sets. All plates have the same length and have a 120.degree. bend in their middle. Each plate is parallel to two successive faces of the belt.

Abstract: There is disclosed a grid in a nuclear fuel assembly for supporting fuel rods and thimbles, which includes a plurality of elongated straps intersecting perpendicularly with each other to define a plurality of first grid cells for supporting the fuel rods and a plurality of second grid cells for supporting the thimbles. Each grid cell has a prescribed intervening distance defined between the opposed straps. A cylindrical sleeve is arranged on at least one of the opposite ends of the strap portions defining the second grid cell and has an inner diameter generally identical to the intervening distance. There is provided an engaging unit for securing each sleeve to the strap portions. The engaging unit includes at least one first engaging portion provided on the strap portions and at least one second engaging portion provided on the sleeve. The first and second engaging portions are held in resilient engagement with each other.

Abstract: A strip (16) for an eggcrate-type nuclear fuel assembly grid (10), in which the fuel rod support springs (30,36) are formed by beams (75,77) and a connecting arch (78). More particularly, the strip has a substantially flat body (56), upper and lower edges (84,86) defining the strip vertical height, and opposed side edges (80) defining the length of the body. The fuel rod support structure (30) projects transversely from the body and comprises a plurality of spring members spaced apart in the longitudinal direction along the body, each spring member having a pedestal portion (75,77) resiliently supported by the body and a contact portion (78) integrally formed on and projecting from the pedestal portion. The pedestal portion preferably includes a beam integrally constrained at both ends by the body. By integrally fixing the ends, the spring member can be considerably smaller and produce the same force for a given deflection as a conventional grid.

Abstract: There is disclosed a grid in a nuclear fuel assembly for supporting fuel rods and thimbles, which includes a plurality of elongated straps intersecting perpendicularly with each other to define a plurality of grid cells. A plurality of engaging units are provided on the grid cells for supporting thimbles, respectively. Each engaging unit includes at least one engaging member provided on at least one of the opposite ends of the straps of the grid cell and defining an engaging portion. A plurality of cylindrical sleeves are arranged in the grid cells for supporting thimbles, respectively. Each sleeve has at least one engaging projection associated with the engaging portion of the engaging member. The engaging projection of the sleeve and the engaging portion of the engaging member are formed such that when the sleeve is turned circumferentially, the engaging projection is held in engagement with the engaging portion.

Abstract: A diagrid for a nuclear reactor core, of the type with two disc-like plates, for a series of parallel chandelles, and a cylindrical shell fitted with heat-exchanging fluid input and output ducts. A forced fit between the edges of said plates (10,11) and said shell (12) consists of a thick welded joint. The upper ends of each of the chandelles (30) protrudes above the upper surface of the upper plate. The two ends of each of the chandelles are welded to the plates.

Abstract: A spacer for a fuel bundle is disclosed in which a grid type construction provides an approximation to a traditional ferrule spacer. First and second sets of diagonally extending strips of Zircaloy are utilized extending along opposite diagonals across a square sectioned spacer. One set of strips is disposed in a first parallel array along a first diagonal, with each strip of the set being spaced from other strips of the set at rod width spaced intervals along the second and remaining diagonal. The other set of strips is disposed in a second parallel array along an second diagonal, with each strip of the set being spaced from the other strips of the set at rod width spaced intervals along the first diagonal.

Abstract: A grid key and method for keying exterior grid cells in a nuclear fuel assembly. The grid key has a main body portion having first and second ends and is bent at approximately a 45 degree angle near the first end. Two tabs extend outward from the first end at a right angle to the main body portion to define a T-shape. The T-shaped end is inserted into the window of the exterior grid strip such that the top of the T-shape is parallel to the longitudinal axis of the grid assembly. The main body portion is then rotated 90 degrees to position the top of the T-shaped end to be perpendicular to the longitudinal axis of the grid assembly and behind the exterior grid strip. The main body portion is then pulled away from the exterior grid strip in a vertical rotating motion, causing the top of the T-shaped end to pull the exterior grid strip away from the center of the cell defined by the grid assembly.

Abstract: A method and apparatus for assembling an egg-crate type grid (10) by orthogonally interengaging slots (30,32) cut transversely into one longitudinal edge of each of a plurality of metal strips (12,14). A first plurality of strips (14) is supported on their lower unslotted edges in north-south orientation so that the strips are uniformly spaced apart in parallel in the east-west direction with all the slots (32) oriented upwardly on the upper edge. The slotted upper edges (26) of adjacent north-south strips are then spread farther apart in the east west direction while maintaining the lower edges (28) at said uniform spacing. The lower, slotted edges (24) of a second plurality of east-west oriented strips are interengaged with the north-south strips while the selected portions of the upper edges of the north-south strips are spread. The upper edges of the first plurality of strips are then returned to the unspread orientation.

Abstract: A bracing grid suitable for use in a light water reactor has a plurality of mutually intersecting sets of plates defining cells which receive fuel rods. The plates carry springs for retaining the rods by friction. Each spring is formed has a U legs located each on one side of a plate, the branch being for contact on the elements in two mutually adjacent cells separated by the plate. The two legs are connected by a loop straddling the plate and are connected to each other by a weld at the base of the loop, through a window formed through the plate. The legs of each spring are also mutually connected by mechanical locking means which retain the two legs with respect to each other and with respect to the respective plate.

Abstract: A grid key and method for keying exterior grid cells in a nuclear fuel assembly. The grid key has a main body portion having first and second ends and is bent at approximately a 45 degree angle near the first end. Two tabs extend outward from the first end at a right angle to the main body portion to define a T-shape. The T-shape end is inserted into the window of the exterior grid strip such that the top of the T-shape is parallel to the longitudinal axis of the grid assembly. The main body portion is then rotated 90 degrees to position the top of the T-shaped end to be perpendicular to the longitudinal axis of the grid assembly and behind the exterior grid strip. The main body portion is then pulled away from the exterior grid strip in a vertical rotating motion, causing the top of the T-shaped end to pull the exterior grid strip away from the center of the cell defined by the grid assembly.

Abstract: A zirconium alloy for use in spacer grids for nuclear reactor fuel claddings, which consists essentially of, on a weight percent basis,2.5 to 10% Nb,0.01 to 1.5% of one or more components selected from the group consisting of Y and rare earth elements and oxides thereof,0.05 to 1% of one or more optional element selected from the group consisting of Fe, Cr, Mo and V, andthe remainder Zr and incidental impurities.

Abstract: An improved nuclear fuel assembly (10) of the type having a plurality of intersecting metal strips (14) welded at the strip intersections (32). At least some of the strips (16a, 18a) have nonlinear upper or lower edges (32a, 44a) at the intersections such that some of the intersection welds (34) at the strip upper or lower edges are at different elevations (34b) relative to intersection welds at other upper or lower edges (34a, 34c, 34d).

Abstract: A grid for the fuel rods of a light water reactor.It is formed by cylinder portions (11, 13) of polygonal section having cut-out parts (12) in which the projecting portions (15) of those adjacent cylinder portions are overlapped against which the rods (1) bear. The portions are then assembled.

Abstract: A nuclear fuel rod support grid has a plurality of straps being interleaved with one another to form a matrix of hollow cells. Each cell receives one fuel rod and is defined by intersecting pairs of opposing wall portions of the straps which are shared with adjacent cells. A plurality of fuel rod engaging and clamping springs and dimples are associated with the wall portions of the straps and protrude into the cells so as to clamp a fuel rod therebetween. A pair of spacers separate from the grid straps but detachably mounted to the wall portions thereof defining each cell are installed in each cell along the strap walls portions defining each cell and at a pair of diagonal opposite corners of the cell. Each spacer has a right angle configuration in cross section for fitting into the respective one cell corner. One spacer supports the springs and the other spacer supports the dimples.

Abstract: Integral vanes 4 with optimized size, shape and bend angles maximize coolant mixing and fuel rod 12 heat transfer downstream. Recessed weld nuggets 5 with no vane cutout are optimized for size, strength and corrosion resistance. Staggered arches 20',22' and springs 20,22 minimize turbulence and reduce grid pressure drop and promote coolant mixing. Crowned arches 20',22' and springs 20,22 decrease scoring of fuel rods 12 and are sized to minimize turbulence and pressure drop. Minimum cutouts in unslotted section of grid strip 46,46' give 15-20% strength increase. Intermediate weld and tapered end slots 48 give 15% strength increase. Ribbed and round dimple stiffeners 38,39 on outer strips increase buckling resistance, reduce handling damage and spreads accidental loading. Outer strips 32 are optimized for strength, handling, turbulence generation and pressure drop. They also divert enough flow to interior of fuel assembly to match thermal power distribution and eliminate fuel rod corrosion concerns.

Abstract: A nuclear fuel assembly grid comprising an improved outer grid strap wherein abutting outer grid strap segments are joined at a point of intersection with an inner grid strap. The normally preformed weld where the inner strap fork tines extend through the outer grid strap thereby fixedly bonds the outer grid strap segments together.

Abstract: A fuel assembly for nuclear reactors comprising a skeleton having two end pieces connected together by elongate elements and several grids spaced apart along the guide tubes and forming cells for holding a bundle of fuel elements in position at the nodes of a regular lattice. The grids comprise median grids adapted for resisting lateral shocks and having fins for creating turbulences in the flow of the coolant along the assembly, bottom grids without fins and ensuring the cross bracing of the elements and top grids with fins and ensuring cross bracing of the elements, the top and bottom grids imposing on the coolant a pressure loss lower than the median grids.

Abstract: A channel box and/or a spacer of a fuel assembly is a welded construction and made of a Zr-Nb-Sn alloy comprising 0.5-2.2 wt % Nb, 0.5-1.5 wt % Sn contained so as to satisfy the relation of Sn(wt %) 22.times.Nb(wt %)--3.0, and balance Zr or a Zr-Nb-Sn-Mo alloy comprising 0.5-2.2 wt % Nb, 0.5-1.5 wt % Sn contained so as to satisfy the relation of Sn(wt %).gtoreq.2.times.Nb(wt %)--0.3, 0.1-0.8 wt % Mo, and balance Zr. The welded portion, its heat affected zone and the unwelded portion of the channel box and/or the spacer have substantially the whole equilibrium phase structure.

Abstract: A bimetallic spacer for supporting fuel rods in position in a nuclear reactor fuel assembly substantially comprises inner and outer structural elements of a first metallic material and spring elements of a second metallic material. The structural and spring elements together define a lattice, the interstices of which receive the individual fuel rods. The structural elements and spring elements in the spacer are connected together by forming the structural elements with openings and fitting the ends of the spring elements in the openings. At one end of the opening in the structural element, two slots can be provided for forming a tongue-shaped member which is moved aside to make space for the spring element and then moves back when the end of the spring element is in position, thus preventing a possible vertical return movement of the end of the spring element.

Abstract: A fuel assembly (10) has a lower end fitting debris collector (40) assembled in the form of a welded assembly of an "eggcrate" grid (21) and cast base (40) with hollow legs (42). Fastener seats (46) in hollow legs (42) permit guide tubes (14) with internally threaded ends to be joined to the upper surface of the lower end fitting debris collector (40) by means of slotted fasteners (50). Bevels (62) and notches (64) in the grid bars (26 and 24a, respectively), provide an embodiment with contoured seats for fuel rod end caps (22). Otherwise, end caps (22) rest on grid (21) at the intersection of slottedly interlocked bars (24 and 26). Thin strips (30) mounted in slots between bars (24) and bars (26) provide small debris catching openings in grid (21).

Abstract: A nuclear reactor fuel assembly for accommodating mutually parallel rods disposed side by side therein includes a spacer formed of two mutually parallel grid sections, each of the grid sections including outer straps flatly facing the rods, each of the grid sections including main sleeves being positioned like positions of the same color in rows and columns disposed at right angles on a chess board leaving a free intermediate position between each two occupied positions, the main sleeves dividing the grid sections into grid mesh openings at the positions each able to receive a respective rod therein, each main sleeve in one of the grid sections being aligned with a main sleeve in the other grid section forming pairs of main sleeves, connecting straps each interconnecting the main sleeves of a pair of main sleeves forming contact springs for rods, each of the connecting straps having a width being smaller than the circumference of one of the main sleeves, and spacer sleeves each being disposed between and rest

Abstract: Device for the spacing and holding in place of fuel rods arranged in accordance with a mesh network in a nuclear reactor, incorporating a spacing structure having recesses regularly arranged in accordance with a mesh network superimposed on the mesh network of the rods, cylindrical sleeves formed from rings connected by elastic strips curved towards the inside of each sleeve and means for fixing the sleeves to said structure.

Abstract: A grid for supporting and spacing nuclear fuel rods, particularly at the nodes of a triangular array, has a peripheral frame of regular polygonal, typically hexagonal, shape and at least two beds of wires spaced in the longitudinal direction of the fuel assembly. Each bed has at least two series of mutually parallel wires secured to said frame at the end thereof, the wires of a same one of said series being parallel to two opposed side of said frame and all said wires defining passages for said fuel elements.

Abstract: Disclosed is an interlocking egg-crate hexagonal grid for supporting a nuclear fuel pin in a hexagonal array. The grid is formed from strips bent at an angle of about 120.degree. at each vertex. Over some faces of each hexagonal cell the strips are coplanar but are arranged, by stacking and interlocking, to avoid any double thickness of metal in that plane. Springs and dimples are formed in the faces of each cell to hold the fuel pin substantially centered.

Abstract: Removable cruciforms are selectively installed at predetermined, spaced elevations within ice baskets associated with a nuclear power system, each ice basket having a generally cylindrical sidewall with plural, annular retaining rings secured therein at predetermined, spaced elevations, each cruciform being installed at predetermined, axially displaced elevations, engaging a corresponding annular retaining ring. Each cruciform comprises a pair of brackets joined together between parallel base portions by respective support plate assemblies and slide plates in telescoping, sliding relationshp, defining with the base portions, a spring housing of generally square configuration within which a generally C-shaped spring is received. A pair of legs extends integrally from the longitudinal edges of the base portion of each bracket, angularly disposed so as to extend radially within the ice basket.

Abstract: An improved retention strap for maintaining a fuel assembly grid in an assembled condition during manufacture in a grid assembly fixture includes four members extendible along the respective outer grid straps, between the corners and about the periphery of the grid. Each member has a pair of end posts and a cross member extending between and connected with the end posts. The end posts of the members are disposed adjacent the respective corners of the grid when the grid is in the assembled condition. Pairs of brackets interconnect respective ones of the end posts of the members, whereas pairs of releasable connectors fasten respective others of the end posts of the members so as to form diagonally opposite pairs of substantially rigidly squared first fixed and second openable corners. Also, the retention strap includes a pair of clamps disposed at each of the fixed and openable corners formed by the end posts.

Abstract: The invention relates to a spacer arranged to retain and fix elongated fuel rods into bundles insertable into a nuclear reactor fuel assembly, said spacer being of a zirconium alloy having a low neutron absorption. To counteract play and hence wear in case of increasing burnup when the springs relax and the rod diameter is reduced by shrinkage, the spacer is made with different textures in the springs (2, 3) and the surrounding structure (1, 6). The difference in texture gives the springs a great axial irradiation growth and the surrounding structure a small axial irradiation growth, which contributes to a remaining deflection tendency of the springs in relation to the surrounding structure during the life of the fuel assembly.

Abstract: Zirconium alloy or Zircaloy grid straps in a fuel assembly grid have predetermined texture (or grain orientation) to offset stress relaxation which occurs upon irradiation of the grid. Particularly, by providing "f-factor" values of the material greater in generally orthogonal, longitudinal directions of the straps than in the strap height direction, the grid strap material will undergo irradiation shrinkage in the longitudinal directions which will serve to offset stress relaxation and maintain sufficient spring force on the fuel rods extending through the cells formed by the grid straps.

Abstract: An improved, grid-type flow distribution baffle for both providing lateral support for an array of heat exchange tubes and for generating a sludge-sweeping water current within a steam generator is disclosed herein. Generally, the improved baffle comprises a plurality of grid members for defining an array of square, tube-capturing cells, wherein each wall of the cell is closely adjacent and contactable with the side of the tube. Each of the cells is circumscribed by a flange at one of its ends which includes a substantially circular opening for allowing the tube to extend through the cell. The flange includes four flat portions spaced 90.degree. apart for rendering the flange flush with the center portion of each of the square walls which form the cells of the baffle. These flat portions allow the flange to closely circumscribe the tube without coming into contact with it, thereby avoiding "point contact" between the flange and the tube.

Abstract: A nuclear reactor fuel of the kind comprising multi-pins (10) located in a hexagonal wrapper (11) and stabilized by a series of spacing grids (12) has an internal grid support cage (13) formed by six vertical limbs (20) inside the wrapper. The limbs of the cage have upturned parts (14) which engage into the cellular structure of the grids such as lying between two adjacent unit cells (16). The cells have tabs (21 in FIG. 3 and 52 in FIG. 5) which can be welded to the upturned parts.

Abstract: A grid structure (42) is mounted within the upper portion (24) of a tapered canister (24), for receiving a relatively loosely packed rectangular array of rods (22) and rearranging the rods into a relatively tightly packed rectangular array at the lower end of the grid. The grid structure comprises a multiplicity of flat, vertically oriented trapezoidal segments (78, 80) interconnected to form a plurality of vertically overlapping grid layers (74, 76). The layers alternate between a row orientation and a column orientation, and thus form a substantially continuous honeycomb of longitudinal cells (64) for guiding individual rods. The cross-sectional area of each cell decreases from the uppermost layer (74a) to the lowermost layer (74i) such that the rods are funneled by the cells to form the tightly packed array.

Abstract: The present invention relates to a method and to an apparatus for producing nuclear reactor structures, such as spacing grids, by pulse laser welding.The grid is placed in a tight enclosure and having thin plates, which intersect one another, so as to define a certain number of crosspieces. By means of a laser source positioned externally of the enclosure, each of the ends of the crosspieces is fixed and optionally the crosspieces are welded along the intersections of the plates.Application to the construction of zirconium alloy spacing grids.

Abstract: A plurality of independent cells having a regular octagonal or circular cross section are arranged in the form of a lattice. Cross-sectionally square independent cells are substituted for two octagonal or circular cells in the central portion of the lattice arrangement. These two square independent cells are so formed that each side of the cells has the largest possible length when the cells are placed among the adjacent cells having a regular octagonal or circular cross section. Spacer support rods serving also as water rods are inserted into the square cells in such a fuel spacer, which consists of a combination of cells having a regular octagonal or circular cross section and cells having a square cross section as mentioned above, to form a fuel assembly.

Abstract: A spacer for supporting a plurality of fuel rods forming a nuclear fuel assembly. The spacer comprises a peripheral band surrounding a bundle of the fuel rods and a plurality of spacer framework units, each holding therein one fuel rod. The spacer framework units are welded or brazed to the peripheral band so as to be arranged inside the peripheral band. Spring members are integrally formed on each of the spacer framework units. The spacer framework units, the spring members and the peripheral band are made of a zirconium alloy containing 5-25% by weight niobium and 0.1-1% by weight chromium and/or iron.

Abstract: Spacer for centering fuel rods of fuel assemblies in water-cooled nuclear reactors, including a grid of sheet metal webs formed of a zirconium alloy and being disposed on edge, rigid bumps formed from at least some of the webs for contacting a fuel rod, at least some of the webs having relatively wide cutouts and relatively narrow lateral slots formed therein, and resilient contact elements formed of chrome nickel steel and having a head part, a base part, a resilient band connecting the head and base parts together into one piece and a bent-out point formed on the resilient band for contacting a fuel rod, the head and base parts of the contact element being insertable into the cutouts and movable into a locked position in the lateral slots formed in the webs.

Abstract: The frame consists of a base and a plurality of square tubes which are secured to the base in upstanding manner. The base consists of rows of intersecting, inter-fitted and inter-welded metal strips which are disposed in mutually perpendicular groups. The tubes are arranged on the strips in a checkerboard fashion with two walls of each tube substantially flush with two parallel strips. In addition, the rows of tubes are offset to one group of metal strips so that the strips are disposed in planes coincident with the longitudinal axes of the tubes in order to support nuclear fuel elements thereon.

Abstract: A grid of a fuel assembly structure for a nuclear reactor comprises two sets of uniformly spaced straps perpendicular to each other for receiving and supporting cylindrical sleeves. The straps forming cells which receive the sleeves have notches at their edges, and the sleeves are joined to the straps by lap welding at the notches.

Abstract: A nuclear reactor fuel assembly spacer grid. The grid straps form an egg crate configuration creating standard cells to enclose the fuel rods. The standard cells have at least one of their straps with an integral spring portion extending into the standard cell and pushing against the fuel rod. A distinct backup spring is positioned transverse to and behind each of the spring portions of the straps and is positioned so as not to touch the fuel rods. The straps are made of a material having a low neutron capture cross-section while the backup spring is made of a material having good radiation stress relaxation properties.

Abstract: A bi-metallic spacer grid having a Zircaloy perimeter strip consisting of oppositely facing, thin walled metal plates for closely surrounding the array of fuel rods. A rigid, stainless steel cross member extends between internal surfaces of the oppositely facing perimeter plates. In the preferred embodiment, the perimeter plates have cantilevered portions extending above and below the main body of the perimeter strip. The cross members interact with the enlarged portion by urging them outward relative to the perimeter strip as the fuel assembly heats up during operation. The outwardly projecting interface surfaces of each assembly mechanically interact with the interface surfaces of adjacent assemblies providing a mechanical restraint which limits bowing of the assembly. The effectiveness of the spacer grids in limiting bowing is therefore not dependent upon controlling the mechanisms responsible for causing bow.