Abstract: Method of making a fuel assembly lattice member and the lattice member made by such method. The method includes placing a plurality of elongate metal straps on a computer controlled conveyor which successively conveys the straps into alignment with each of a plurality of computer controlled piercing and drawing dies belonging to a progressive die machine. The dies are selectively actuated by the computer to form such elements as curved deflector vanes and spring members on each strap member. After the piercing and drawing operations are completed, the straps are joined by welding to form a lattice member of hexagonal cross section, the lattice member defining a plurality of rhombic-shaped fuel rod cells and a plurality of generally rhombic-shaped guide tube thimble cells therethrough. The rod cells are capable of receiving respective ones of a plurality of fuel rods and the thimble cells are capable of receiving respective ones of a plurality of thimble tubes.

Abstract: In a method of assembling a nuclear fuel assembly, a deflecting jig is inserted into grid cells in each of a plurality of grids. The diameter of the deflecting jig is enlarged to urge a spring of at least one pair of dimples and spring, associated with the grid cell to deflect the springs away from the dimple. A plurality of elongated key members are inserted into the grid cells through a plurality of openings defined at intersections between the straps forming walls of the grid cells. Each key member is rotated about its axis to cause hooks of the key member to project from a wall surface of the strap in a direction opposite to the projecting direction of the springs. The key member is then moved in a direction to engage the hooks with the wall surface of the strap. Urging of the spring by the deflecting jig is released to allow the same to be withdrawn from the grid cells and, subsequently, the fuel rods are inserted into the respective grid cells.

Abstract: A flow deflector grid (10) for a nuclear fuel assembly, comprising a plurality of metal strips (12,14) which intersect in a regular array to form an egg-crate type lattice, which defines a plurality of coolant flow channels (16). Each channel has sidewalls (42,44) defined by the strips, a height dimension defined by the height of the strips, a plurality of corners (46) defined by the strip intersections (26), a channel central axis parallel to the height dimension, and a flow cross section normal to the channel axis for coaxially receiving a fuel rod (18) spaced within the channel sidewalls. A unitary flow deflector member (30) is attached to and situated in the corner of each channel so as to be cradled between first and second sidewalls.

Abstract: A nuclear fuel perimeter strip grid corner-piece (12) of increased flatness having at least two flat side sections (18,20) on either side of a transverse bend line (22) is provided. The flat side section (20) or sections (20 and 32) which have small cut-outs for arches (34), as opposed to large spring (36) cut-outs, as the fuel support features adjacent to the bend line (22) of variable radii at portions (24 and 26) are stress-relieved by means of slots (30) of length equal to 1/2 to 1/3 of the width of the flat section. The slot (30) is of a width less than twice the material thickness, so as not to weaken the structure near bend (22).

Abstract: In a fuel bundle for a boiling water nuclear reactor, modification of the spacers at the peripheral spacer band is made to maintain a more uniform spacing of the peripheral fuel rods from the channel walls to avoid critical power limitations. The conventional fuel bundle construction include a plurality of side-by-side sealed vertically disposed nuclear fuel rods in a square array supported at a lower tie plate, at least some of the fuel rods fastened to an upper tie plate, and held in designed spaced apart relation as a unitary mass by intermittent vertically placed spacers. A square sectioned channel surrounds the upper tie plate, the lower tie plate, and the fuel rods and spacers therebetween. The square sectioned channel functions to confined fluid flow interior of the fuel bundle between the tie plates and through the fuel rods. At the same time, the channel separates a core bypass region exterior of the channel having high moderator density from the flow path interior of the fuel bundle.

Abstract: A spacer for retaining parallel, elongated fuel rods includes a plurality of cells which are formed from tubular sleeves internally provided with fixed supports and at least one spring arranged opposite to the fixed supports. The spring is intended to make contact with a fuel rod inserted into the sleeve and is formed as a leaf spring which is cut out of the wall of the sleeve and which, when the sleeve is empty, is bent into the sleeve. The leaf spring is adapted, in tensioned position when the fuel rod is inserted into the sleeve, to be returned to a position substantially coinciding with the wall of the sleeve.

Abstract: A boiling water reactor fuel rod assembly is provided having a plurality of fuel rod spacers which are slidably receivable within an outer channel. Each of the rod spacers is formed of at least one lattice which defines a plurality of fuel rod retaining cells. The lattice is constructed of a plurality of pairs of oppositely facing springy support strips, with each support strip having a plurality of spring-loaded indentations. In an unloaded condition, oppositely facing indentations of each pair of strips, which define each cell, are displaced closer to one another. In a loaded condition, the oppositely facing cell indentations are forced away from each other by the fuel rods so that the springloaded indentations support and retain the fuel rods.

Abstract: A spacer for a fuel assembly of a pressurized water reactor includes a first group of first webs standing on end and extending parallel to one another in a plane. Each of the first webs has longer sides and shorter sides. One of the longer sides of each of the first webs has a slit formed therein with a narrowed point and an impressed indentation. A second group of second webs stand on end and extend at right angles to the first webs. Each of the second webs has longer sides and shorter sides. Another of the longer sides of each of the second webs has a slit formed therein with a narrowed point and an impressed indentation. Each respective one of the first webs is connected to a respective one of the second webs to form a grid by inserting the webs into each other at the slits and locking the narrowed point of one web into place in the impressed indentation of another web with a plug-in connection.

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 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 for a light-water nuclear reactor includes a plurality of vertical fuel rods (10, 42) which are arranged, in spaced relationship in a lateral direction, between a bottom tie plate (11, 44) and a top tie plate (12, 43), the bottom tie plate, defining through-going vertical channels (50) for conducting water through the bottom tie plate and into the spaces between the fuel rods. The bottom tie plate also defines horizontal channels (51, 52) which cross the vertical channels and which are preferably arranged, at edges (54) on the bottom tie plate, in open communication with the spaces between the fuel rods. Helical springs (61, 62) with horizontal symmetry axis are arranged in at least some of the horizontal channels where the horizontal channels cross the vertical channel so as to trap debris in the water passing upwardly through the through-going vertical channels.

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: An improved spacer is disclosed which contains an Inconel grid and a Zircaloy surrounding band. The Inconel grid can be fabricated from the extremely thin and highly elastic spring metal utilizing a modification of a prior art cell construction that includes paired inwardly bent vertical spring legs with cantilevered and rod encircling upper and lower arm pairs The spring legs extend at spaced apart locations between the upper and lower arm pairs and have a medial spring rod contacting portion for biasing the rods into stops on the rod encircling arm pairs. The springs at the upper and lower ends are provided with spring dimple stops to prevent over stressing of the spring during assembly or handling of the fuel bundle into which the spacer is incorporated. The rod encircling arm pairs have an offset from center where the two arms meet at their distal ends to complete encirclement of the rods. This offset from center enables the cells to be fastened in cell pairs at their respective embracing arms.

Abstract: In a grid for the nuclear fuel assembly, a grid member with springs and a grid member with dimples of the grid are arranged face to face such that grid cells of the grid member with springs and the grid member with dimples communicate with each other. Fuel rods are inserted into the grid cells of the respective grid members while the springs and the dimples are shifted sufficiently relative to each other so as not to contact the fuel rods. Subsequently, the grid members are moved to align the respective grid cells whereby the fuel rods are clamped by contacting with the dimples and springs. The grid members are then connected to each other. The grid cells of the grid member with dimples includes a thimble cell, and the grid cells of the grid member with springs include a thimble cell in alignment with one another.

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: 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: A fuel bundle and fuel bundle assembly sequence utilizing a peanut sectioned large water rod is shown locking spacers into place along the axial length of the water rod. In a first embodiment, clearance is defined relative to tabs welded on the large water rod so that spacer assembly to the water rods can occur. In a second and preferred embodiment, spacers are individually equipped with springs locking into complimentary apertures in the peanut sectioned water rod. In both embodiments, the spacers are threaded onto the peanut sectioned water rod and locked into alignment for the receipt of the fuel rods. An improved suspension of the water rod relative to the lower tie plate is disclosed in which a transition piece connects the large water rod to a flexible rod which is threaded at its lower end. This rod is screwed into a threaded aperture in the lower tie plate.

Abstract: In a fuel bundle having a matrix of parallel side-by-side fuel rods supported between a lower tie plate and an upper tie plate, a new ferrule and spring construction for the required spacers used to maintain the fuel rods in their required precise side-by-side alignment is disclosed. Paired ferrules are each provided with apertures for capturing a single spring between the ferrules. The springs are provided with a continuously looping main body having protruding tabs on opposite sides of the springs. The paired ferrules are confronted at their respective apertures for the capture of the springs. The shape of the apertures permits insertion of the spring after the ferrules have been welded together. The springs are compressed while being inserted. After insertion the springs return to their original shape and are confined between the ferrules. After insertion of the fuel rods, the springs are compressed to an intermediate position, but are still confined within the ferrule apertures.

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: 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: In a grid in a nuclear fuel assembly for supporting fuel rods, elongated straps intersect with each other to define grid cells. At least one pair of punched sections are formed, in spaced relation to each other, in each of peripheral walls of the respective grid cells. At least one of elongated spring elements is formed in the peripheral wall of each grid cell. Each spring element is formed such that a portion of the peripheral wall of the grid cell between the pair of punched sections bulges and projects into the grid cell. The spring element is capable of being deflected toward the peripheral wall of the grid cell. A pair of projections are formed in the peripheral wall of the grid cell respectively at both longitudinal ends of the spring element such that a pair of portions of the peripheral wall of the grid cell bulge. Both longitudinal ends of the spring element are connected respectively to the pair of projections.

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: In an assembly method for a nuclear fuel assembly, a grid member with springs and a grid member with dimples of the grid are arranged face to face such that grid cells of the grid member with springs and the grid member with dimples communicate with each other. Fuel rods are inserted into the grid cells of the respective grid members while the springs and the dimples are shifted sufficiently relative to each other so as not to contact the fuel rods. Subsequently, the grid members are moved to align the respective grid cells whereby the fuel rods are clamped by contacting with the dimples and springs. The grid members are then connected to each other.

Abstract: An improved spacer is disclosed which contains an Inconel grid and a Zircaloy surrounding band. The Inconel grid can be fabricated from the extremely thin and highly elastic spring metal utilizing a modification of a prior art cell construction that includes paired inwardly bent vertical spring legs with cantilevered and rod encircling upper and lower arm pairs. The spring legs extend at spaced apart locations between the upper and lower arm pairs and have a medial spring rod contacting portion for biasing the rods into stops on the rod encircling arm pairs. The springs at the upper and lower ends are provided with spring dimple stops to prevent over stressing of the spring during assembly or handling of the fuel bundle into which the spacer is incorporated. The rod encircling arm pairs have an offset from center where the two arms meet at their distal ends to complete encirclement of the rods. This offset from center enables the cells to be fastened in cell pairs at their respective embracing arms.

Abstract: A grid spacer for a nuclear reactor fuel assembly is formed of two superposed combs. Each comb has a base strip which extends the width of the assembly. To it are attached parallel grid strips which are free at their other ends. The grid strips are perpendicular to the base strip and are formed for spring engagement with the fuel rods of the assembly. The combs can be inserted from the sides of the assembly, so that an additional or substitute spacer can be added to the assembly without disassembling the latter.

Abstract: A spring-and-spacer assembly for maintaining fuel rods in a upright preferred position in a fuel assembly of a nuclear reactor core is provided. The spring has a leg portion and two loop portions, one at each end of the leg. Each loop engages an ear formed in a ferrule of the spacer. Each loop contains a dimple which contacts an ear of the ferrule. The central leg portion has a dimple, or a projection, which contacts a fuel rod and biases the fuel rod against stops. The spring load is transmitted to the ferrule ears by the dimples in the spring loops. Preferably, the spring rotates about the dimple when flexed, contributing to spring flexibility. The high spring flexibility permits use of the spring in connection with small rod-to-rod spacing fuel assemblies. This construction permits providing a low-mass, low-surface area spring, in turn providing for low neutron absorption and low flow obstruction.

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 nuclear reactor fuel assembly includes at least one uprightly disposed spacer having a grid of intersecting sheet-metal struts defining meshes therebetween. Mutually parallel rods are each disposed in a respective one of the meshes. Strip-like contact springs are parallel to the rods and each have a side facing toward and a side facing away from a respective one of the struts. Each of the contact springs are disposed in a respective one of the meshes and have two strip ends both being retained on the one strut. Each of the contact springs have a contact location being resilient relative to the one strut for contacting a rod. The contact location is spaced apart from both of the strip ends. Each of the contact springs has an undulatory transverse curve disposed at the contact location on the side of the contact spring facing toward the one strut. The contact springs are continuously smooth and flat from the contact location to the strip ends resting on the one strut.

Abstract: An improved spacer and method of making a spacer is disclosed for use in a nuclear fuel bundle wherein a plurality of fuel rods enclosed within a channel are maintained in parallel side-by-side relation by a plurality of the spacers. Each spacer is placed within the fuel bundle at selected elevations between upper and lower tie plates. The improved spacer is a member of the class of spacers wherein solid strips of material are welded at interstitially placed tube members between the fuel rods to form the continuous spacer grid. The improvement constitutes forming separate upper and lower reduced section grids from separate, normally aligned, first and second parallel sets of grid members. One grid is formed for the top of the spacer; the remaining grid is formed for the bottom of the spacer. Tube members placed interstitially between the fuel rods are used to interconnect the grids.

Abstract: A debris screen for a fuel assembly for a reactor to which coolant fluid is supplied comprises a substantially planar plate member having an array of coollant openings extending through the plate member dimensioned to trap at least a portion of debris particles carried by the coolant; and a skirt member enclosing the periphery of the plate member; each of the coolant flow openings having a coolant entry region at a lower surface, a coolant exit region at an upper surface and a coolant flow path extending between the entry and exit regions, the flow path including an intermediate segment laterally offset from the entry and exit regions to cause coolant to change direction of flow in the intermediate segment and thereby prevent at least a portion of the debris particles from passing through the plate members.

Abstract: A nuclear fuel support grid 10' of egg-crate structure has wave defining strips 12a, 12b, 12c, 12d defined by bends 16' inclined from the vertical and opposing cantilevered springs 18' with inclined spring bases 20' opposing them for support of fuel rods 22 intermediate their ends. The "inclined waves" defined by inclined surfaces formed by bends 16' and spring bases 20' of cantilevered springs 18' provide lateral components to the coolant flow in patterns which enhance DNB and corrosion behavior.

Abstract: A fuel assembly has a spring detent spacer grid of intersecting strips for capturing and retaining deleterious debris carried by reactor coolant before it enters the active region of a fuel assembly. A plurality of fuel end caps are peripherally grooved to receive springs projecting from the strips. The end caps are thus captured by springs and debris is wedged and trapped on opposite sides of the strip and against the end caps by pairs of adjacent integral leaves projecting from the stips intermediate and substantially symmetrically arranged about their intersections.

Abstract: Each of cylindrical members composing a fuel spacer of separate cell type is formed at a edge portion thereof with a positioning notch or a positioning projection, which is located just opposite to one of fuel rod supporting projections formed on the inner surface of the cylindrical member. In manufacturing of the fuel spacer, the positioning notches or projections of the cylindrical members are engaged with the positioning projections or recesses formed on fuel spacer assembly jigs for precise and easy positioning of cylindrical members.

Abstract: A nuclear fuel assembly having an array of longitudinally extending fuel rods and axially spaced transverse grids with cells receiving the fuel rods therethrough employs anti-fretting protective devices for protecting lower end portions of tubular claddings of the fuel rods from damage-inducing contact with debris entrained in upward flow of coolant through the fuel assembly. Each device is in the form of a hollow sleeve disposed about and extending coextensive with the lower end portion of one fuel rod cladding. The sleeve has an upper portion which extends through one grid cell between lower and upper ends thereof, and a lower portion which extends below the grid cell from the lower end thereof to a bottom end of the fuel rod cladding spaced below the grid cell lower end.

Abstract: A nuclear fuel assembly support grid includes a multiplicity of spring structures for engaging fuel rods extending through the cells of the grid. Each spring structure is formed on each cell wall section to form a matrix of fuel rod receiving cells in the grid. Each spring structure is composed of a pair of spaced apart upper and lower opposite outer portions being integrally attached at their outer ends to the respective wall section, and a middle portion disposed between in laterally spaced relation from the outer portions and integrally connected at its outer ends with respective inner ends of the outer portions. The integrally-connected outer and middle portions are defined by a pair of generally U-shaped slots formed in a reverse interlocking relation to one another in the wall section of the one cell.

Abstract: The spacer-grid comprises at least one single-piece plate (1) through which extend a group of openings (2) at least a part of which constitutes an even network of passages (2) for the fuel rods and the guide tubes of the fuel assembly. The spacer-grid may be formed by one single-piece plate (1) of great thickness or by the association of a plurality of parallel single-piece plates interconnected by an outer girdle element.

Abstract: A nuclear fuel assembly grid includes a multiplicity of dimple and spring structures for engaging fuel rods extending through the cells of the grid. Each of the dimple and spring structures have a pair of outer portions and a middle portion with opposite lengthwise edges thereon. The edges of the middle portions of the dimple structures and the outer and middle portions of the spring structures have one-sided chamfers defined thereon, whereas the edges of the outer portions of the dimple structures have double-sided chamfers defined thereon. The one-sided chamfers are longer than the double-sided chamfers.

Abstract: A nuclear fuel assembly grid includes a multiplicity of spring structures for engaging fuel rods extending through the cells of the grid. Each spring structure is formed on each cell wall section to form a matrix of fuel rod receiving cells in the grid. Each spring structure is composed of a pair of spaced apart upper and lower opposite outer portions being integrally attached at their outer ends to the respective wall section, and a middle portion disposed between and integrally connected at its outer ends with respective inner ends of the upper and lower outer portions. The upper and lower outer portions extend in alignment with one another and in generally diagonal relation to the direction of the central longitudinal axis of the one cell between upper and lower portions of the wall section. The middle portion which contacts the fuel rod extends in generally transverse relation to the direction of the central longitudinal axis of the one cell.

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: 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 fuel assembly for nuclear reactors which comprises the usual upper and lower tie plates and fuel rods extending between them is made debris-resistant by providing a grid spacer in contact, or very nearly so, with the lower tie plate and so positioned as to subdivide the usual openings in the lower tie plate which are provided for the passage of cooling water. This causes debris to be trapped in the openings of the lower tie plate, and keeps it from contacting the fueled portion of the assembly.

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: The invention relates to a nuclear reactor spacer grid member for use in a liquid cooled nuclear reactor and to a ductless core component employing a plurality of these spacer grid members. The spacer grid member is of the egg-shell type and is constructed so that the walls of the cell members of the grid member are formed of a single thickness of metal to avoid tolerance problems. Within each cell member is a hydraulic spring which laterally constrains the nuclear material bearing rod which passes through each cell member against a hardstop in response to coolant flow through the cell member. This hydraulic spring is also suitable for use in a water cooled nuclear reactor. A core component constructed of, among other components, a plurality of these spacer grid members, avoids the use of a full length duct by providing spacer sleeves about the sodium tubes passing through the spacer grid members at locations between the grid members, thereby maintaining a predetermined space between adjacent grid members.

Abstract: A nuclear fuel assembly grid includes a fuel rod engaging spring structure formed on each cell wall section of inner straps being interleaved with outer straps to form a matrix of fuel rod receiving cells in the grid. Each spring structure is composed of a pair of laterally spaced spring leg members each extending vertically and anchored at their respective pairs of opposite ends to the wall section and a fuel rod engaging cross spring member which extends diagonally between and integrally connects to the spring leg members. The leg members and cross member are respectfully curved and arched in configuration along respective longitudinal sections so as to project from the wall section toward the longitudinal axis of the grid cell. Further, the cross spring member is preferably disposed approximately forty-five degrees to the direction of the longitudinal axis of the cell and to the direction of coolant fluid flow through the grid and fuel assembly in which the grid is used.

Abstract: The fuel rods located in areas of a nuclear reactor core where water jetting damage to the rods can occur are secured together by a clip, in order to change the mass subject to fretting damage. The change of mass changes the amplitude of the induced fuel rod vibration, thus reducing possible fuel rod fretting an/or damage. To repair such damage, the combination of clip(s) and an inert rod are used to replace a damaged fuel rod.

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: A grid for use in a PWR assembly includes a peripheral girdle and at least two sets of parallel plates. The plates of one set are at an angle with respect to those of the other set so that the sets defined cells for the fuel rods. The parallel plates are distributed in at least two beds spaced apart in the longitudinal direction of the assembly. In a fuel assembly having a triangular array of fuel rods, three successive beds of mutually parallel plates are provided.

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.