Abstract: A spacer grid for PWR assemblies is characterized by curved flow channels between adjacent fuel rods and straight, essentially flat strips connecting opposite side plates of the spacer. The latter strips prevent bowing-out of the side plates during fuel assembly fabrication and during operation in the reactor. Additionally, the spacer grid allows accurate positioning of the fuel rods on a square lattice with a precisely defined pitch, and support of the rods in their spacer cells is such that rod bow will be minimized. The direction of the nozzles on the flow channels has been chosen to promote cross-flow of the coolant through the assembly.

Abstract: An array grid includes a plurality of interlocking elongate strips. The strips are structured and configured to provide sufficient lateral support for steam generator tubing while minimizing the risk of attack by stress corrosion cracking to the steam generator tubes.

Abstract: A nuclear fuel spacer grid, fabricated by intersecting a plurality of zircaloy or inconel grid strips and used for placing and supporting a plurality of elongated fuel rods within a nuclear fuel assembly, is disclosed. In the spacer grid of this invention, each of the grid strips is not cut away to form separate springs or dimples for supporting the fuel rods, but has an axial slot extending from one end of each strip to a length. The grid strips are intersected at the slots prior to being welded together into a single grid structure at a welding tap formed at an outside end or a middle portion of each of the slots. Each of the grid strips also has a dipper-shaped coolant mixing vane, or a dipper vane, at each of the upper and lower ends thereof. The spacer grid thus maximizes the thermal hydraulic coolant mixing effect within a fuel assembly and stably supports the fuel rods within the assembly while improving the mechanical/structural strength of the assembly, such as a buckling strength.

Abstract: A fuel assembly, particularly, a fuel assembly including short-length fuel rods and fuel spacers, is used for a boiling water reactor, which is capable of sufficiently reducing the pressure loss of at least one of the fuel spacers positioned above the upper ends of the short-length fuel rods, irrespective of the arrangement of the short-length fuel rods, and also ensuring the structural strength of the fuel spacer. The fuel assembly includes fuel rods located in a square lattice array, two water rods arranged in a region in which seven of the fuel rods are arrangeable, two fuel spacers for holding the fuel rods and the water rods with mutual intervals kept immovable. Each of the fuel spacers includes cells which are connected to each other and in which the fuel rods are to be inserted, respectively, and a band for surrounding the outermost peripheries of the cells. The short-length fuel rods include four first short-length fuel rods arranged in the outermost peripheral region of the square lattice array.

Abstract: A duct-type spacer grid for nuclear fuel assemblies is disclosed. In this spacer grid, a plurality of duct-shaped grid elements, individually having an octagonal cell, are closely arranged in parallel and are welded together, thus forming a matrix structure. The grid elements do not pass across the center of the subchannel of the assembly, thus effectively reducing pressure loss. Each of the grid elements is formed as an independent cell, and so they effectively resist against a lateral impact. A plurality of integral type swirl flow vanes, having different heights or same height, axially extend from the top of the grid to be positioned within each subchannel. The swirl flow vanes are bent outwardly, and so they do not contact the fuel rods during an insertion of the fuel rods into the cells. In the spacer grid, the fuel rods are supported within the cells by line contact springs without using any dimple.

Abstract: A lattice high bar for a nuclear steam generator tube support bar array has scalloped indentations along its length. The scalloped indentations are located at points on the high bar where water tubes will contact the high bar. The indentations extend from one edge of the high bar to about two-thirds of the distance across the bar. When the high bars are used in a lattice bar array, only the unscalloped portion of the high bar contacts an adjacent supported tube, thereby reducing the contact area and the likelihood of corrosion and cracking and also reducing the length over which inspection is impeded. Additionally, the flow path created by opposed but overlapping scallops at the 120° intersections at certain points along the high bars improves the flow sweeping over the surface of the supported tube.

Abstract: An open-webbed cage support device providing support that enabling a mechanical device such as a thermal expansion tank to be suspended or mounted adjacent to the thermal water heating device without the need to improvise a “made in the field” support structure.

Abstract: Each of short-length fuel rods 3 is arranged at a position other than in 3×3 corner regions 6 to 9 in such a manner as not to be simultaneously adjacent to a water rod 5 and others of the short-sized fuel rods. Gd fuel rods 4 are arranged at positions excluding the outer periphery, and the number of those of the Gd fuel rods 4 adjacent to the short-length fuel rods 3 is one-half or less the total number of the Gd fuel rods. At a transverse cross-section of a region upward from upper ends of the short-sized fuel rods 3, the amount of burnable poison contained in a polygonal region 10 whose vertexes are located at centers of those of the first fuel rods 3 arranged at the outermost layer is smaller than the amount of burnable poison outside the region 10. With this configuration, a critical power can be improved in consideration of both a distribution of the flow of coolant and a distribution of a thermal power in the fuel assembly.

Abstract: A spacer of a fuel assembly having intersecting webs undergoes reduced longitudinal expansion as a result of corrosion during an operating period. The webs have intersection locations at which assembly gaps are provided. The assembly gaps have widths which correspond essentially, at most over a fraction of their total length, to the wall thickness of an intersecting web, but are wider in a remaining region. Since corrosion layers growing from an edge of an assembly gap toward the intersecting web cannot touch the web, no solid pressure, which could lead to longitudinal expansion, builds up.

Abstract: A sub-assembly for a spacer in a nuclear fuel bundle includes at least first and second ferrules lying adjacent one another for receiving respective nuclear fuel rods. Each ferrule has fuel rod contacting points along one side of the ferrule for abutting a fuel rod within the ferrule, and a substantially I-shaped opening along a side of the ferrule opposite the one side. A substantially I-shaped spring adapted to seat within the opening includes a spring body lying in a plane and having opposite horizontal end portions connected by a vertical stem portion, a central portion of each of the horizontal end portions projecting away from the substantially I-shaped opening to one side of the plane and a center portion of the vertical stem projecting into the substantially I-shaped opening to an opposite side of the plane.

Abstract: A nuclear fuel spacer grid, fabricated by intersecting a plurality of grid strips and used for placing and supporting a plurality of elongated fuel rods within a nuclear fuel assembly, is disclosed. The spacer grid of this invention has a plurality of dimple vanes on its grid strips. The dimple vanes are designed to guide the coolant from one cell to neighboring cells of the spacer grid, thus accomplishing a desired coolant mixing effect and increasing the thermal allowance of the fuel rods and accomplishing a high performance fuel assembly. The spacer grid also has a multi-spring structure, consist in of one arc-shaped main spring and two bow-shaped sub-springs. The main spring directly supports the fuel rod within the spacer grid, while the sub-springs have the same radius of curvature as that of the external surface of the fuel rod and effectively support the fuel rod when the main spring fails to support the fuel rod.

Abstract: An improved support grid of a nuclear reactor fuel assembly is described. The support grid has a plurality of first and second straps which are assembled so as to form an eggcrate structure defining grid cells in a square arrangement. The support grid includes a plurality of mixing vanes integrally formed on a side edge of the first and second straps adjacent to an area where the straps cross. The mixing vanes slanted to be adjacent to a fuel rod are each shaped to show no welding apertures formed therein in their horizontal planes of projection thereby maximizing the coolant impinging area to agitate and swirl a coolant flow.

Abstract: A fuel assembly for a nuclear reactor is described, the fuel assembly including: a plurality of fuel pins (12) extending substantially parallel to the axis of the assembly and to each other; at least two structural grids spaced apart from each other, the grids being in contact with said fuel pins (12) and maintaining said fuel pins substantially mutually parallel and preventing contact therebetween, wherein the fuel assembly further comprises at least one mixing grid (50) situated intermediate said at least two structural grids, the fuel assembly being characterized in that said mixing grid (50) is positioned and fixedly located out of substantial contact with said fuel pins (12), the mixing grid also having turbulence inducing means (61) to promote turbulence in a coolant (62) flowing through said fuel assembly in use and in that the mixing grid is formed from sheet metal wherein the plane of the metal sheet from which the mixing grid is formed lies in a plane which is transverse to the axis of the fuel pin

Abstract: A top guide assembly for securing a top guide to a shroud which enables the top guide to be remotely removed without removing any other parts of the shroud or the core support structure is described. In one embodiment, the top guide assembly includes a hanger for being secured in a groove formed in an inner surface of the shroud, and the hanger includes a ledge having a plurality of openings therein. The top guide rests on an upper surface of the ledge. The assembly also includes wedges for being positioned in pockets formed in the top guide and tightly fit between the hanger and the top guide, and threaded studs for extend through respective aligned bores in the wedges and openings in the ledge. A nut and a keeper are engaged to one end of each stud to retain the wedge between the hanger and the top guide grid.

Abstract: A fuel assembly spacer grid including swirl deflectors respectively arranged at interconnections between interconnecting longitudinally and laterally-extending straps on upper ends of the interconnecting straps adapted to support fuel elements of a nuclear fuel assembly. Each of the swirl deflectors has four vanes bent to have an air vane shape. By virtue of this configuration, an improvement in the efficiency of the spacer grid cooling the fuel elements. The spacer grid also includes springs each configured to generate not only a main spring force caused by a displacement of the spring occurring when the spring comes into contact with a fuel element placed in a reactor core, but also an additional spring force caused by hydraulic pressure applied to the spring. Each spring, which is in a fixed state at one end thereof, has a free bent portion at the other end.

Abstract: The present invention relates to a fuel assembly for a light-water nuclear reactor with a substantially square cross section which comprises fuel rods (4) extending between a bottom tie plate (16) and a top tie plate (17). A coolant is adapted, during operation, to flow upwards through the fuel assembly. According to one aspect of the invention, the fuel assembly comprises a plurality of fuel units (3) stacked on top of each other, wherein each fuel unit (3) comprises a plurality of fuel rods (4) extending between a top tie plate (17) and a bottom tie plate (16). The fuel units are arranged attached to a support structure (4a, 14, 14a, 14b) extending through the whole fuel assembly such that axial gaps are formed between the fuel units (3). One of the tie plates is freely movable relative to the support structure.

Abstract: A fuel assembly (1) comprising a plurality of elongated elements (3) filled with nuclear fuel and at least one component (5, 6, 7) for retaining the elongated elements (3), wherein the retaining component (5, 6, 7) is completely or partly made of a ceramic material.

Abstract: A spacer grid with H-springs for use in a nuclear reactor fuel assembly is disclosed. In the spacer grid, two sets of intersectional grid strips are arranged in sets at an angle to each other prior to being encircled by a plurality of perimeter strips, thus forming a plurality of four-walled cells individually placing and supporting an elongated fuel rod therein. A plurality of regularly spaced openings are formed on each of the grid strips and perimeter strips at portions corresponding to the cells. An H-shaped spring is set in each of the openings and has a specifically curved rib capable of being brought into conformal surface contact with a fuel rod placed in each of the cells. The H-shaped spring thus elastically supports the fuel rod. Two positioning dimples are provided on each of the strips at positions above and below each of the openings.

Abstract: A support rod 14 carrying one or more separation devices 12, e.g., swirlers, is releasably secured in a fuel bundle. The support rod and separation devices are sized to pass through openings in the spacers S otherwise containing full length fuel rods. The lower end of the support rod is releasably connected to the upper end of a part-length fuel rod PLR which in turn is releasably connected to the lower tie plate. The support rod, separation devices and part-length rod may be installed and removed relative to the fuel bundle as an integral assembly with the part-length rod and separation devices passing through the openings in the spacers. When installed, the separation devices lie above upper spacers in the vent volumes to flow liquid on and into the interstices of the surrounding fuel rods.

Abstract: A grid with coolant deflecting channels for used in nuclear fuel assemblies is disclosed. In the grid, two sets of intersecting grid strips are arranged in sets at right angles to each other prior to being encircled by four perimeter strips, thus forming a plurality of four-walled cells individually placing and supporting an elongated fuel rod therein. Each of the grid strips is made up of two narrow sheets which are deformed at a plurality of regularly spaced portions to provide nozzle-type coolant deflecting channels. The channels individually have an upright Y-shaped or reversed Y-shaped configuration capable of so deflecting coolant as to mix low temperature coolant with high temperature coolant. The channels thus form a uniform temperature distribution within a fuel assembly. The channels are so inclined with respect to the axes of the fuel rods as to form wide and linear positioning springs at middle portions thereof.

Abstract: Each of short-length fuel rods 3 is arranged at a position other than in 3.times.3 corner regions 6 to 9 in such a manner as not to be simultaneously adjacent to a water rod 5 and others of the short-sized fuel rods. Gd fuel rods 4 are arranged at positions excluding the outer periphery, and the number of those of the Gd fuel rods 4 adjacent to the short-length fuel rods 3 is one-half or less the total number of the Gd fuel rods. At a transverse cross-section of a region upward from upper ends of the short-sized fuel rods 3, the amount of burnable poison contained in a polygonal region 10 whose vertexes are located at centers of those of the first fuel rods 3 arranged at the outermost layer is smaller than the amount of burnable poison outside the region 10. With this configuration, a critical power can be improved in consideration of both a distribution of the flow of coolant and a distribution of a thermal power in the fuel assembly.

Abstract: A nuclear fuel core in a pressurized-water reactor including fuel assemblies, each of which comprise a top tie plate; a bottom tie plate, the top tie plate and the bottom tie plate having through-openings for passing coolant flowing from beneath upwards through each of the fuel assemblies; elongated elements, arranged between the top tie plate and the bottom tie plate; a mixing cross section having a mixing center, the mixing cross section extending through four orthogonally arranged fuel assemblies and having a size corresponding to at least that of two fuel assemblies; and a plurality of spacers for retaining and mutually fixing the elongated elements, the plurality of spacers having flow control members for controlling coolant flow around the mixing center. A nuclear fuel core in a boiling water reactor is also disclosed.

Abstract: A spacer for a nuclear fuel bundle comprises a plurality of discrete, generally cylindrical ferrules, with each ferrule having a pair of circumferentially spaced fuel rod contacting portions along one side of the ferrule and three superposed openings in the ferrule along an opposite side thereof. A leaf spring having opposite end projecting portions and a central projecting portion is disposed between adjacent ferrules with the end projecting portions and the central portion disposed within the openings of the ferrule. The central portion includes a boss projecting inwardly for engagement against the fuel rod in one ferrule and the end projections contain bosses projecting inwardly and spaced from the fuel rod of the one ferrule. The end projections bear against an adjacent ferrule. The spring is captured between the two ferrules and contacts the ferrules at a plurality of laterally and vertically spaced contact points so that the spring is stabilized against flow-induced vibration.

Abstract: The invention relates to a fuel assembly (1) and a spacer (7) for a nuclear reactor wherein the spacer comprises a plurality of cells (9) for retaining and mutually fixing parallel elongated elements (3, 8) extending through the cells to form a bundle in the fuel assembly. The cells are tubular and internally provided with four elongated, non-independently resilient supports (10), formed in the sleeve material, or with two elongated, non-independently resilient supports (10), formed in the sleeve material, and two independently resilient supports (16), wherein the supports are intended to provide an all-sided positioning of the elongated element. (FIG.

Abstract: An arrangement of fuel rod support members having dimples and springs is presented to prevent abrasive wear of the fuel rods caused by bouncing of the fuel rods against the supporting members caused by vibrations in a diagonal direction of the support grids. The supporting members are disposed such that dimples are respectively provided on one pair of adjacent walls located on one side of the vibrational direction while springs are respectively provided on adjacent walls located on the opposite side of the vibrational direction.

Abstract: A method of forming a nuclear fuel assembly grid, as well as the resulting grid itself, are disclosed. In the formation of the grid, formed straps having slits are prepared, arranged into a grid form by intersecting the straps with each other through the slits, and the intersections of the associated straps are brazed. Prior to the step of arranging the straps, those portions to be brazed are subjected to a pretreatment, in which an paste, prepared of a mixture of a filler metal and a vehicle, is applied to the portions to be brazed to form a thin film thereon.

Abstract: A spacer includes a plurality of ferrules welded to one another to form a structural integral matrix for locating fuel rods in a fuel bundle. Each ferrule has a pair of stops along one side of the ferrule and a central opening along its opposite side. An elongated flat spring having openings straddling a central cross-piece is disposed along an outer edge of the ferrule with the spring openings receiving band portions of the ferrule above and below the opening through the ferrule. The intermediate cross-piece bears against an adjoining ferrule whereby the end portions of the spring bear against the rod in the one ferrule, biasing it against the opposite stops. Thus ferrule/spring construction reduces the quantity of material of the ferrule, thereby improving performance without sacrificing structural integrity.

Abstract: A spacer for retaining nuclear fuel rods in laterally spaced relation to one another includes first and second sets of spacer strips extending in mutually perpendicular diagonal directions relative to a generally rectilinear peripheral spacer band. The strips have linearly extending sections with adjacent sections angularly related to one another and meeting at apices. The sections of each strip alternately intersect a diagonal line across the spacer with the apices alternately located on opposite sides of the diagonal line. Alternate apices have springs projecting to one side of the strip for engaging fuel rods and apices between the alternate apices have stops projecting on opposite sides of the strip for engaging the fuel rods. Slots are provided in the strips enabling intermeshing of the strips with one another to define discrete cells peripherally encompassing and retaining fuel rods within the spacer.

Abstract: A grid-shaped spacer includes a sheet-metal web having a web aperture formed therein defining two spaced mutually opposite aperture edges. The aperture edges oppose an elongation of an elongate spring which is curved about a direction transverse to its own longitudinal direction and which has a tab that engages through the web aperture at each of two spring ends. At least one of the tabs is snapped into a notch formed in one of the spring edges opposing the elongation of the spring.

Abstract: A fixturing tool includes a sleeve having a central region with a circular axial opening and four leaf springs projecting from each of the opposite ends of the central region. The central region is cruciform in cross-section with arcuate side walls between the projections of the cruciform. Unit cells are arranged on a base having openings corresponding in location to the centers of the unit cells in their final assembly in a spacer for a nuclear fuel rod bundle. Fixturing devices are freely and loosely disposed within the unit cells and pins are partially inserted through the fixturing devices to expand the leaf springs to engage the unit cells. Once the cells with fixturing devices and partially inserted pins are centered over the base openings, the pins are advanced into the openings in the base to accurately align each unit cell relative to one another to enable final welding of adjacent cells to one another.

Abstract: The present invention relates to a structural member for nuclear reactor pressure tubes. More particularly, the present invention relates to a new structural member that is used as a beam designed to support the loads and stresses of multiple transversely disposed nuclear reactor fuel channel pressure tubes.

Abstract: Disclosed is a grid structure for supporting fuel rods in a nuclear reactor. The grid structure is formed of a plurality of interconnected thin metal grid straps that are welded or brazed together to provide a structural network of interconnected open grid cells, similar to an "egg crate divider". The grid straps are provided at regular intervals, corresponding to the width of a grid cell, with pairs of spaced, substantially horizontal, slotted spring-like projections and a substantially X-shaped spring-like projection vertically intermediate the horizontal projections. The spring-like projections are designed to support and hold the fuel rods within the grid cells under both balanced and unbalanced forces acting on the fuel rod assembly while it is in service, surrounded by coolant in the nuclear reactor.

Abstract: A nuclear fuel rod spacer grid is formed of slottedly interlocked sets of flat strips. One set of strips is formed with integral coplanar tab portions which have one or more edge portions bent at angles to form integral mixing vanes.

Abstract: A fuel assembly includes a cluster of mutually parallel fuel rods. A fuel assembly channel laterally surrounds the cluster of fuel rods and has a substantially rectangular cross section and flat channel walls. Grid-like spacers having meshes formed therein each receive a respective one of the fuel rods for guiding the fuel rods in a plurality of axial positions. At least one support spring laterally supports each respective one of the fuel rods in the mesh guiding the fuel rod. Each of the spacers have inner ribs being aligned parallel to the fuel rods and outer peripheral ribs opposite the channel walls. At least some of the inner ribs are fastened to the peripheral ribs, and the outer peripheral ribs are joined together only by the inner ribs.

Abstract: A spacer array is disclosed in which alternating cells are disposed at differing elevations. In a preferred octagonal spacer cell array, alternate fuel rods within the rows and columns of the fuel bundle matrix are surrounded by octagonal spacer cells at a first elevation. Likewise, and in the same preferred octagonal spacer array, the remaining alternate fuel rods within the rows and columns of the fuel bundle matrix are surrounded by octagonal spacer cells at a second elevation. The octagonal spacer cells of the spacer array at one level adjoin the octagonal spacer cells of the spacer array at an adjacent level. Specifically, each octagonal spacer cell has the top and/or the bottom of as many as four of its eight sides disposed for joinding with one side of as many as four octagonal cells in an adjacent cell layer. Each cell has approximately 0.6 of an inch height, or one-half the 1.2 inch height of the prior art.

Abstract: A hexagonal grid is comprised of castled strips which are (a) bent into a zigzag form, and (b) interleaved with one another so that half-height bridge segments, which extend between and are integral with adjacent full-height castle segments, are placed in edge-to-edge contact so that they align with one another. This forms a grid with no double thickness portions. During fabrication the strips are sandwiched between slotted top and bottom plates. These plates are formed with access openings at sites where three segments intersect and through which welding is carried out. Relatively long spring features are only formed in full-height castle segments. The absence of these features in the half-height bridge segments allows the overall height of the grid to be minimized.

Abstract: A metal component (10) having non-uniform material characteristics which cause the component to undergo differential growth upon exposure to a neutron flux, and a process for producing such a component. The invention is useful for making metal components for use in nuclear reactors, particularly fuel assembly cantilever grid springs (12). By cold working a portion (40) of a cantilever spring on the convex side of the curved region of the spring, a spring can be provided which has a smaller reduction in preload upon exposure to radiation than a conventional cantilever spring.

Abstract: A mixer grid for a nuclear reactor fuel assembly has a plurality of strips arranged in interlocking rows and columns defining a plurality of cells. A stopper is fixed to each corner of each cell for both directing coolant flow, providing coolant mixing and providing a smooth contact surface for the fuel rod. The stopper is either cone-shaped or cylindrical for directing and channeling coolant flow. The stopper also has a smooth, flat chamfered surface for contacting the fuel rod and minimizing damage upon the shifting of the fuel rod. The grid is attached to the nuclear reactor fuel assembly by using guide cells comprising a plurality of support arches for welding to the nuclear reactor fuel assembly.

Abstract: A fuel spacer for a fuel assembly comprises a plurality of tubular ferrules each forming a fuel rod insertion passage, a belt-like support member for supporting the tubular ferrules bundled in a lattice arrangement and a spring member for axially supporting the fuel rods disposed in the ferrules. The adjoining ferrules are joined together horizontally, each of the ferrules has at least one end to which a plurality of cutout portions are formed circumferentially of the end portion and at least one flat portion is formed between adjoining petal portions at which the adjoining ferrules are spot welded. Each of the cutout portions and petal portions of the tubular ferrule has various shapes such as trapezoidal, rectangular, triangular, V or M shape. The cutout portions and petal portions may be formed at both axial ends of the tubular ferrule.

Abstract: An apparatus for attaching a key member to a nuclear fuel assembly grid and detaching the same therefrom is disclosed. The apparatus includes a supply and recovery mechanism, an inserting and removing mechanism, and a rotating mechanism. The supply and recovery mechanism operates to supply the key member to a prescribed position adjacent to the grid and recover the same. The inserting and removing mechanism is disposed between the supply and recovery mechanism and the grid, and operates to insert the key member supplied from the supply and recovery mechanism into the grid and remove the key member from the grid to recover the same to the supply and recovery mechanism. The rotating mechanism is disposed adjacent to the inserting and removing mechanism, and operates to rotate the key member inserted in the grid in a prescribed direction about the longitudinal axis to attach the same to the grid and rotate the same in a direction opposite to the prescribed direction to detach the same from the grid.

Abstract: A nuclear fuel assembly grid (100) made from a plurality of interlaced corrugated metal strips (102-116) forming an egg-crate configuration so as to define plurality of four-walled cells (118) for receiving respective individual fuel rods (120). The spaced apart vertical bend lines (160,162) of the currugation define vertices (130,132) and consecutive body panels (164,166) which alternate generally inwardly and outwardly between consecutive bend lines. A vertical slot (168) extending from one of the strip upper or lower edges (176) into each panel midway between consecutive bend lines, and overlapping a slot from an interlaced strip to form an hourglass-shaped cell having opposed convex walls and opposed concave walls and four 90 degree corners (150). Spring (148) and stop (153) structure projects from each wall of a cell, for centering and supporting the fuel rod within the cell.

Abstract: A fuel assembly supporting structure for a nuclear reactor fuel assembly which comprises a two-way shape-memory alloy. A shape-memory alloy is selected which has an overall transition temperature range substantially above atmospheric temperature and substantially below a temperature experienced by the shape-memory alloy under reactor operating conditions. By using a shape-memory alloy in the design, the support structure assumes a first configuration for securely supporting one or a plurality of nuclear reactor components at a temperature above the overall transition temperature range and assumes a second configuration for loosely engaging the reactor components below the transition temperature range.

Abstract: A fuel assembly, where crystallographic orientations of a channel box are brought into a random distribution; and cladding tubes, spacers and a channel box are made from highly corrosion-resistant, Fe--Ni, zirconium-based alloy, hardened in the (.alpha.+.beta.) phase or .beta.-phase temperature region, has an average discharge burnup level of 50 to 550 GWd/t.

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: A spacer for a nuclear reactor fuel assembly includes a cell-formed lattice-work for retaining parallel, elongated elements such as fuel rods (4) into a bundle of substantially square cross section. The cells are formed from tubular, preferably round sleeves (1). Each one of these offers a passage for one of the elements for mutually fixing these elements. Each spacer is formed from two sub-spacers (5) somewhat spaced-apart from each other in the longitudinal direction of the bundle. A first sub-spacer in a pair fixes elements lying substantially on one side of a diagonal through the bundle, and a second sub-spacer fixes the other elements such that elements passing through the sleeves (1) of the first sub-spacer pass, possibly with some exception, at the side of the sleeves in the second sub-spacer and vice versa.

Abstract: A nuclear fuel assembly for a BWR comprises a plurality of fuel rods, a polygonal channel box surrounding the fuel rods, a plurality of spacers axially spaced from each other and each keeping the fuel rods laterally spaced from each other, and a plurality of vanes disposed only in a region at and around a corner within the channel box, for generating swirling flows in the region to thicken a liquid film on each fuel rod in the region.

Abstract: In the nuclear fuel assembly, a plurality of plate-shaped straps are assembled perpendicularly to each other into a grid shape so as to construct a supporting grid providing with a plurality of cells each of which inserts a nuclear fuel rod. A cell-size inspection device which inspects the size of each cell of the supporting grid is constructed by a base, a movable plate, a plurality of pin gauges and a sensor. The supporting grid is mounted on the base, while the movable plate is provided such that it can relatively move with respect to the base in a longitudinal direction of the cells. The pin gauges are provided on the movable plate such that they can freely slide along the longitudinal direction of the cells. When the movable plate is moved toward the supporting grid, each of the pin gauges is to be inserted into each of the cells. The sensor senses whether the pin gauge is relatively moved from the predetermined position of the movable plate.

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.