Abstract: A fuel element support grid for supporting a plurality of nuclear fuel elements intermediate their ends has at least some of the pairs of intersecting and slottedly interlocked strips including pairs of intersecting integral fluid flow directing vanes along at least one adjacent edge of each of the strips of the pair. Welds attach the pair of vanes to each other thereby providing welded attachment of the strips. The welds may be at the intersection of the vanes remote from their areas of integral attachment to their respective strips or they may be adjacent to their areas of integral attachment to their respective strips.

Abstract: A BWR fuel assembly having an array of spaced fuel rods, an outer hollow tubular flow channel surrounding the fuel rods so as to direct flow of coolant/moderator fluid therealong, and a hollow central water cross extending through the channel and composed of radially extending members dividing the fuel rods into separate fuel rod mini-bundle subassemblies which each has fuel rod spacers being displaced from one another along the length of the subassembly, includes features on at least one of the spacers of each subassembly which minimize degradation of CHF performance. These features are coolant flow diverting scoops mounted on the outer peripheral strap of the spacer. The scoops are disposed in spaced apart relation along an upstream side of the outer strap so as to extend inwardly along and in spaced relation from an upstream side of respective ones of the terminal end portions of the interleaved inner straps of the spacer which with the outer strap form a ring of perimeter cell openings in the spacer.

Abstract: A grid for use in nuclear fuel assemblies is made up of double grid members which are deformed so as to provide channels for the coolant. At least the upper portions of these channels are inclined relative to the axes of the fuel rods and are disposed in such a manner as to cause circulation of fluid about each individual rod and within the assembly. In one embodiment the grid is positioned between the positioning grids and serves primarily as a coolant deflector. In another embodiment so constructed as to serve the positioning grid, as well as a flow deflector, the channels are straight in their lower portions i.e. parallel to the axes of the fuel rods. In their upper portions they curve to provide the desired deflection of the cooling fluid and the straight sections have a slight bow outward, relative to the plane of the grid member of which they are a part. This outwardly bowed portion engages the fuel rod and acts as a positioning spring.

Abstract: Fuel elements (16) support grids have openings (22,24) in the intersecting matrix strip (12,14) edges adjacent their points of intersection in which box-shaped conduit means (20) with integral mixing vanes (30 and 32) on the flow exit end (28) are secured. The vanes (30,32) create flow in two offset and oppositely transverse directions (34 and 36) relative to the direction of flow through the conduit means in order to generate thermal-hydraulic performance improving vortices (18) in the flow subchannels defined by the diagonal gaps between fuel elements (16). The box-shaped conduit means (20) also improve grid strength and rigidity.

Abstract: In a nuclear reactor fuel element for receiving mutually parallel rods, the improvement includes a rectangular grid-shaped spacer including planar webs crossing and facing the rods defining grid mesh openings receiving the rods, the webs including two outer webs forming an outer corner of the spacer and defining a corner grid mesh opening at the outer corner, the outer corner having an outward curve being curved in a direction parallel to the longitudinal direction of the rods, the outer webs having edges at the curve transverse to the rods being drawn inward toward the rods in the corner grid mesh opening forming a bevel in longitudinal direction of the rod.

Abstract: A BWR fuel assembly having an array of spaced fuel rods, an outer tubular flow channel surrounding the fuel rods to direct flow of coolant fluid therealong, and a central water cross extending through the channel and dividing the fuel rods into separate subassemblies which each has fuel rod support spacers being displaced from one another along the length of the subassembly, includes features in each subassembly which minimize degradation of CHF performance. These features relate to intermediate flow mixing nonsupport grids disposed along each subassembly between and in spaced relation from the uppermost pairs of the spacers. The grid includes first and second groups of mixing vanes disposed at its downstream side. The vanes of the first group are attached on portions of the outer strap and on respective portions of the inner straps which together with the outer strap portions define the perimeter cell openings.

Abstract: An improved grid structure is provided for a nuclear reactor fuel assembly whose sole purpose is to promote a crossflow mixing of the coolant through the fuel assembly rather than the support of the fuel rods. The grid straps form an egg-crate configuration creating cell openings for receiving the fuel rods. Associated with each cell opening is at least one coolant flow mixing vane that projects over the cell opening and four dimple protrusions which are open to the flow of coolant therethrough. The dimple protrusions extend into the cell opening to a further extent than the mixing vane so as to prevent damaging impact of the fuel rod with a vane upon transverse movement of the fuel rod across the cell opening. In reducing the pressure drop of the coolant flow through the assembly, the height of the inner grid straps is substantially less than the height of the outer border strap.

Abstract: An improved bottom nozzle of a fuel assembly includes a housing and a modified adapter plate formed by a network of ligaments which extend across the housing and are connected to the side walls of the housing a short distance below its upper peripheral edge so as to define an open region therein. The improved bottom nozzle also includes a debris trap having a structure disposed within the open region of the housing upon the adapter plate and adapted to capture and retain debris carried by collant flowing from openings in the lower core plate of the nuclear reactor to the fuel assembly. The trap structure is composed of a plurality of straps aligned with one another in a crisscross arrangement and defining a plurality of interconnected wall portions which form a multiplicity of small cells each having open opposite ends and a central channel for collant flow through the trap.

Abstract: A debris trap is mounted within a bottom nozzle of a fuel assembly so as to capture and retain debris carried by coolant flowing from the lower core plate openings of the nuclear reactor to the fuel assembly. The trap includes a structure disposed below the adapter plate of the bottom nozzle and between the corner legs of the nozzle. The structure is composed of a plurality of straps aligned with one another in a crisscross arrangement and defining a plurality of interconnected wall portions which form a multiplicity of small cells each having open opposite ends and a central channel for coolant flow through the trap. A plurality of spring-like fingers are punched out of the wall portions and bent to extend into the cell channels toward the downstream end of the trap structure to provide means to capture and retain pieces of debris carried through the channels by flowing coolant.

Abstract: Nuclear reactor fuel assembly having a grid-shaped spacer with square grid meshes, wherein mutually parallel rods are arranged, respectively, in a grid mesh, the spacer having flat outer straps extending transversely to the rods and an intermediate strip extending parallel to the rods between two of the respective outer straps, the intermediate strip being inclined relative to the two outer straps, including a rejection rise formed at the outside of the intermediate strip and extending in direction of a diagonal of a grid mesh located at a corner between the two outer straps, the rejection rise being disposed transversely to the two outer straps and being inclined downwardly towards two respective ends of the intermediate strip in longitudinal direction of the rods.

Abstract: In a nuclear reactor fuel assembly, a relatively flexible mounting member for mounting a large coolant conducting tube to the lower tie plate whereby excessive side forces on the fuel rod spacers are avoided in the event of lateral displacement of the fuel assembly such as during a seismic event.

Abstract: A hollow water cross disposed in an outer flow channel of a fuel assembly so as to divide an array of fuel rods in the assembly into a plurality of subgroups is composed of a plurality of hollow panels which extend radially from a central axis of the water cross and define an open inner flow channel. The panels are interconnected at their outer ends with angularly displaced portions of the outer channel and at their inner ends with one another so as to define a central channel portion which extends the axial length of the water cross. The improvement relates to a cross brace disposed within the central channel portion of the water cross generally along the central axis thereof. The cross brace includes radially-extending portions which extend within and parallel to the respective water cross panels and interconnect with dimples formed in each panel so as to reinforce and stiffen the water cross and thereby the outer channel of the fuel assembly.

Abstract: A fuel assembly for a boiling water reactor comprises four bundles of vertical fuel rods (5). The bundles are surrounded by a common fuel channel (2) and each provided with a top tie plate (10) and a bottom tie plate (11). The four bottom tie plates are supported by a common supporting plate (18) which is inserted into, and supported by, the inlet sleeve (15) of the fuel assembly. Each bottom tie plate (11) includes an annular horizontal contact surface (24) abutting the supporting plate, and a non-round guide portion which is arranged, with no mentionable play, in a corresponding, non-round, through-hole (19) in the supporting plate (18).

Abstract: A water cross for delivering non-boiling water to the center of a BWR fuel assembly for improved moderation and fuel economy. A cruciform skeleton is assembled from grid straps and connecting straps positioned at axial locations along stiffening rods. The skeleton is inserted into a flow channel to provide support for rectangular or square water tubes which are inserted through the skeleton into the flow channel to form an internal water cross. A method for forming a water cross is also disclosed.

Abstract: A nuclear fuel spacer grid with improved outer straps. The grid has an egg-crate array of interleaved grid straps creating cells for enclosing the fuel rods. The grid also has four outer straps connected together in a square-shaped array surrounding the grid strap's heightwise edges. The outer straps have a central portion to which is attached the grid straps' heightwise edges. The outer straps also have a top and a bottom resilient lengthwise border portion extending vertically beyond and horizontally outwardly beyond their associated outer straps central portions.

Abstract: A nuclear fuel spacer grid with improved grid straps. The grid has an egg-crate array of interleaved grid straps creating cells for enclosing the fuel rods. Near beginning of life in the reactor, the grid straps bend in a spring-like manner to flexibly grip the fuel rods with their preferably rigid protrusions. In a cell, the protrusions on two non-opposing grid straps are closed to longitudinal coolant flow while the protrusions on the remaining grid straps associated with the cell are open to such flow. Near end of life the grid straps loose resiliency due to irradiation--induced stress relaxation and the fuel rod has a loose fit against the protrusions due to radiation effects. However, the fuel rod is held in position in the cell by the coolant flow therethrough which forces the fuel rod away from the closed protrusions and into contact with the open protrusions. The protrusions in one cell are coplanar. The protrusions in the cells lie in one of two longitudinally separated planes.

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: A partial grid structure is provided for a nuclear reactor fuel assembly for selectively mounting either means for deflecting the upwardly flowing coolant or means for laterally supporting the fuel rods, or both, to substantially eliminate localized neutron flux peaking and thereby increasing the power output of the assembly. The grid structure extends across only a portion of the fuel assembly and is associated with a selective group of fuel rods defined by a predetermined number of the fuel rods contained within the fuel assembly. The grid straps form an egg-crate configuration creating cell openings for receiving the fuel rods of a predetermined fuel rod group. In an alternate embodiment, the fuel rods of the fuel assembly are partitioned into separate groups by the use of separate partial grid structures which are combined to form a grid structure assembly.

Abstract: A fuel assembly for a boiling reactor is constructed according to the accompanying drawing (FIG. 1). Preferably, only partial spacers (6) are used in the fuel assembly. Each partial spacer positions only a minor portion of the total number of fuel rods in the assembly. Groups of partial spacers are arranged axially one after the other, the partial spacers in each group being positioned at at least two different levels and together positioning all fuel rods in the fuel assembly.

Abstract: A spacer grid for a nuclear fuel assembly wherein hangup between diagonally adjacent fuel assemblies in the reactor core during loading and unloading is essentially precluded by providing an inclined plane deflection surface at each corner of the spacer grid.

Abstract: A reusable system for removably attaching the lower end 21 of a nuclear reactor fuel assembly duct tube to an upper end 11 of a nuclear reactor fuel assembly inlet nozzle. The duct tube's lower end 21 has sides terminating in locking tabs 22 which end in inwardly-extending flanges 23. The flanges 23 engage recesses 13 in the top section 12 of the inlet nozzle's upper end 11. A retaining collar 30 slides over the inlet nozzle's upper end 11 to restrain the flanges 23 in the recesses 13. A locking nut 40 has an inside threaded portion 41 which engages an outside threaded portion 15 of the inlet nozzle's upper end 11 to secure the retaining collar 30 against protrusions 24 on the duct tube's sides.

Abstract: A nuclear fuel assembly including a guide tube sleeve having tabs projecting outwardly from the sleeve to modify coolant flow.