Abstract: The invention relates to a fuel assembly in the form of an elongated channel having several corners. The channel is connected to a coolant intended to flow through the channel. A bundle of similarly elongated fuel rods, retained by a plurality of spacers (8), is arranged in the channel. The spacer (8) comprises a number of cells surrounded by an outer frame which is formed from a band placed on edge. According to the invention, the band is extended on the upstream side of the spacer (8) by a skirt (12), in which openings (13) are provided. In certain of these openings deflection fins (14) have been arranged in order to deflect coolant, flowing along the assembly wall (6), in a direction towards the center of the respective spacer (8).

Abstract: A fuel assembly has a water rod which consists of a coolant ascending path and a coolant descending path, the coolant ascending path opening below a fuel support of a lower tie plate, the coolant descending path opening above the fuel support and adapted to guide downwardly the coolant that has flowed up the coolant ascending path to the upper portion of the water rod. The lateral cross section of the coolant ascending path is more than 25 times that of the coolant descending path.The nuclear reactor with these fuel assemblies loaded in the core is operated as follows. After startup of the reactor when the reactor power is low, all the control rods inserted in the core are withdrawn completely. Then, the reactor power is controlled by regulating a liquid level formed in the water rods. This reactor operation method prolongs the lifetime of the control rods, thereby reducing the number of times they have to be replaced.

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

Abstract: In a boiling water reactor having discrete bundles of fuel rods confined within channel enclosed fuel assemblies, an improved fuel design of bundles of fuel rods interior of the channels is disclosed. Specifically, partial length rods are utilized which extend from the bottom of the channel only part way to the top of the channel. These partial length rods are shortened with respect to the remaining rods and are symmetrically distributed throughout the fuel bundle with the preferred disposition being in the second row of the bundle of fuel rods from the channel wall. The symmetrical distribution of the partial length rods is at spaced apart locations one from another. The partial length rods extend from the bottom of the fuel bundle and terminate within the boiling region. during shutdown of the reactor, an improved cold shutdown margin is produced at the top of the fuel assembly due to the improved moderator-to-fuel ratio and reduction in plutonium formation at the upper portion of the bundle.

Abstract: A fuel assembly has a plurality of first fuel rods each of which contains nuclear fuel material but does not contain burnable poison, and a plurality of second fuel rods each of which includes nuclear fuel material and burnable poison. The amount of burnable poison in a lower region of the fuel assembly is smaller than that in an upper region thereof. When each of the second fuel rods is divided into an upper region and a lower region, a region of the divided regions in the second fuel rods containing a maximum burnable poison concentration Gmax and a region of the divided regions in the second fuel rods containing a minimum burnable poison concentration Gmin are located in the lower region of the fuel assembly. The burnable poison concentration of the upper region of each second fuel rod is between Gmax and Gmin. The fuel assembly may moderate a maximum linear heat rating with an increased spectral shift effect.

Abstract: A fuel assembly for a light water cooled and moderated nuclear reactor comprises a bundle of fuel rods and a structure for holding the bundle in position comprising upper and lower end pieces or nozzles joined together by guide tubes which support grids for maintaining the fuel rods at the nodal points of a regular array. The upper end piece comprises an adapter plate fixed to some at least of the guide tubes and having an upwardly directed shroud arranged to bear directly or indirectly on the upper core plate of the reactor and encircling a coolant passage defining an internal volume into which all guide tubes open. The adapter plate has coolant passages around the shroud. This arrangement makes it possible to direct an adjustable fraction of the cooling water flow outwardly of a cluster guide sleeve associated with the assembly and belonging to the upper internals of the reactor.

Abstract: A nuclear reactor fuel assembly includes an elongated fuel channel having opposite channel sides. Fuel rods containing nuclear fuel are mutually spaced apart in the fuel channel and parallel to the longitudinal direction of the fuel channel. A water tube inside the fuel channel has an outer surface and is parallel to the fuel rods. The water tube has a lower end with an inlet opening and an upper end with an outlet opening for liquid water. A longitudinal rib inside the fuel channel is secured to and interconnects two of the opposite channel sides and is spaced apart from the others of the channel sides. The longitudinal rib is longitudinally divided into two partial ribs each being secured to the outer surface of the water tube.

Abstract: A spring-and-spacer assembly for maintaining fuel rods upright in a fuel assembly of a nuclear reactor core is provided. The spring is in the form of a continuous loop with first and second legs having mid-leg rod-contact regions. Bend regions are positioned on each side of each contact region extending toward the interior of the loop spring. In most positions, the spring is used to load two adjacent fuel rods. In configurations in which there is an unpaired fuel rod, a plate having a tab for contacting the spring is provided. The spring provides the desired force, such as about 2.5 pounds per fuel rod, in a small rod-to-rod spacing of less than about 0.14 inches.

Abstract: An improved upper tie plate is disclosed in a fuel bundle for a boiling water nuclear reactor. The tie plate resides in a fuel bundle including an upper tie plate, a lower tie plate, a matrix of sealed fuel rods supported therebetween, and a surrounding channel. Both the lower tie plate and the improved upper tie plate have two functions; they support the fuel rods in vertical upstanding relation between the tie plates and interior of the channel and permit the passage of moderating coolant through the channel from the bottom of the channel to the top of the channel. This moderating coolant enters through the lower tie plate in the liquid form, passes into the matrix of upstanding fuel rods where steam is generated and exits outwardly through the improved upper tie plate as a water steam mixture at the top of the fuel bundle.

Abstract: A combination of flow trippers with spacer deflectors in the two phase steam/water region of a fuel bundle in a boiling water reactor is disclosed. Spacers with deflectors are placed immediately above the flow trippers. The flow trippers are located on either an inside channel wall surrounding the fuel bundle or the outside of water chambers within the fuel bundle. Additional flow trippers may be located adjacent to the spacers, above the flow trippers that are below the spacers. The spacers are provided with deflector skirts overlying the flow trippers. In operation of the fuel bundle, excess water flows in the two phase region in a film on the unheated inside walls of the fuel channel or the outside walls of the water chambers. The film flow is perturbed by the flow trippers and is deflected toward the fuel rods. The overlying deflector skirts or tabs on the spacers further deflect the liquid toward the fuel rods to improve cooling and to increase the power generation capability of the fuel bundle.

Abstract: An improved lower tie plate having increased fluid flow resistance is disclosed for use in a boiling water nuclear reactor. The fuel bundle includes the lower tie plate, an upper tie plate, and a plurality of fuel rods supported therebetween in vertical upstanding relation, with the fuel rods surrounded by a square sectioned channel. In the preferred embodiment, some of the upper fuel rods are of partial length. The surrounding channel confines the fluid flow through the fuel bundles between the tie plates for the extraction of heat from the fuel rods undergoing a fission reaction. The lower tie plate includes a first group of apertures for the support of the fuel rods to selected positions in the 9x9 matrix; appropriate numbers of these apertures are threaded for tying the upper and lower tie plates together with tie rods. The matrix is interrupted at larger apertures for the support of moderator containing water rods.

Abstract: An advanced boiling water reactor (BWR) fuel design is described that preferentially directs more unvoided water coolant into the upper portion of the fuel assembly. This allows relatively more fuel to be placed in the lower portion of the fuel assembly. This arrangement allows a more nearly optimun moderation of neutrons in the upper portion of the assembly while preserving a higher volume of fuel in the lower portion. In addition to providing a more nearly optimum distribution of water in the assembly, the larger number of fuel rods can be used in the lower portion to reduce the linear heat generation rate (power peaking) in the assembly.

Abstract: A fuel assembly including a plurality of fuel rods and water rods. The fuel rods are arranged with a predetermined pitch and two water rods are disposed adjacent to each other in a diagonal direction of the fuel assembly. More particularly, the fuel rods are arranged in a lattice of nine rows by nine columns and the two water rods are disposed inside a region corresponding to a space sufficient for disposing seven fuel rods at the center of the fuel assembly. Each of the water rods has an outer diameter greater than the pitch of the fuel rods.

Abstract: A nuclear reactor fuel assembly includes an elongated fuel assembly box. Fuel rods containing nuclear fuel are mutually spaced apart in the fuel assembly box and parallel to the longitudinal direction of the fuel assembly box. A water tube inside the fuel assembly box is parallel to the fuel rods. The water tube has a lower end with an inlet opening and an upper end with an outlet opening for liquid water. A shield is fastened inside the water tube and spaced apart from both of the ends of the water tube. A flowthrough opening is formed in the shield or between the shield and the water tube for the liquid water.

Abstract: In a nuclear boiling water reactor, an improved lower tie-plate and fuel channel interface for a boiling water reactor fuel bundle is disclosed. The fuel bundle has a lower tie-plate for supporting fuel rods and permitting the introduction of fluid interior of the fuel bundle. An upper tie-plate maintains the lower tie-plate supported rods in side-by-side relation and has apertures for discharging a mixture of water and steam. The fuel rods extend between the tie-plates for the generation of steam with some of the fuel rods forming a threaded connection fastening the tie-plates together. A polygon sectioned channel, preferably square, surrounds the tie-plates and fuel rods for the confining of fluid flow between the tie-plates interior of the bundle. The interface of the channel as it surrounds the lower tie-plate is reconfigured.

Abstract: A fuel assembly of the present invention comprises a plurality of fuel rods which are held by an upper tie plate and lower tie plate at the ends thereof and a moderating rod which is arranged between the fuel rods and held by the lower tie plate at its lower end. The fuel rods are arranged in a lattice form having 9 rows and 9 columns, and the moderating rod contains a passage for a coolant and has a cruciate cross-sectional form. The ratio A.sub.M /A.sub.C of the area A.sub.M of a moderator region in the moderating rod in the cross-sectional plane in which the moderator is present to the area A.sub.C of the coolant passages in said fuel assembly is within the range of 0.07 to 0.11, and the area A.sub.M is 75% or more of the total area of the fuel lattice units in which none of the fuel rods is arranged, but the moderating rod is arranged.

Abstract: In a nuclear fuel bundle having a lower tie-plate, an upper tie-plate and a surrounding channel therebetween, an improved water rod is disclosed for preferable use when fuel rods held between the tie-plates are placed in a 9 by 9 array. Typically, seven fuel rods are omitted centrally of the 9 by 9 array with the middle or fifth row having three rods removed and paired rods being removed in the 4th and 6th row with displacement of the removed pair towards opposite corners. Into the volume created by the removal rods, there are placed two "D" sectioned rods, the "D" rods each being round in cross-section except for a truncating chord, this truncating chord defining the straight back of each "D". In the preferred embodiment one of the "D" water rods is provided with spacer tabs for maintaining spacers separating the fuel rod at their correct elevations. This rod is inserted with an alignment that permits the tabs to pass through the spacers.

Abstract: A fuel assembly of the present invention comprises fuel rods which are arranged in 9 rows and 9 columns (9.times.9) in a channel box. The channel box has a width L between outer walls thereof and a width D between inner walls thereof, both of which satisfy the following equation:0.12.ltoreq.(P-L)/Dwherein P denotes the fuel assembly pitch in a reactor core. A sufficient cold shutdown margin for a reactor core can be secured by determining the widths L and D so as to satisfy the above-described equation, even if the average enrichment of the fuel assembly is increased to 4 wt % or more.

Abstract: Disclosed is a fuel assembly comprises a plurality of cylindrical fuel rods with a plurality of fuel pellets sealed therein, a plurality of small units each having a predetermined number of the fuel rods bundled spaced with a fixed intercentral distance and being arranged in such a manner that the intercentral distance between the component fuel rods falling on the mutually juxtaposed sides of the adjacent small units is larger than the intercentral distance between the adjacent fuel rods in the small units, and at least one water rod near the center of a cluster of the plurality of the small units.

Abstract: A fuel assembly for a boiling water reactor is provided with at least one vertical channel for a by-pass flow through the fuel assembly. The channel is supplied with water through a vertical supply tube surrounded by the base of the assembly, the supply tube being arranged with its lower end in the vicinity of the lower end of the base.

Abstract: A fuel assembly comprises a plurality of fuel rods, moderator rods disposed among the fuel rods, upper and lower tie plates for holding both end portions of the fuel rods and the moderator rods, and fuel spacers for keeping distances between the fuel rods and the moderator rods constant. The fuel assembly is characterized in that there is provided a space region extending from the upper tie plate to the lower tie plate and having a space enough to dispose at least one of the fuel rods. At least one of the moderator rods being disposed adjacent to the space region. The fuel rods, the moderator rods, and the space region are disposed in a grid form.

Abstract: A BWR fuel assembly includes an outer hollow tubular flow channel, a water cross and a plurality of mini-bundles of fuel rods. The outer channel provides an enclosure for directing the flow of coolant/moderator fluid through the fuel assembly. The water cross extends through the outer channel and has a plurality of radially extending members attached along the interior of the outer channel which divide it into a plurality of separate compartments. One mini-bundle of elongated fuel rods is located in each compartment between the interior of the outer flow channel and exterior of the radially extending members of the water cross. Each fuel rod mini-bundle is comprised of an interior array of fuel rods with each fuel rod being of a first predetermined diameter size, and a peripheral array of fuel rods with each fuel rod being of a second predetermined diameter size greater than the first diameter size.

Abstract: A fuel assembly for boiling water reactors includes, in addition to the usual outer flow channel which surrounds the fuel rods, an inner flow channel having rectilinear sides disposed within the fuel assembly, extending vertically therethrough, and arranged to receive cooling water at or below the bottom of the assembly. The channel is of such size as to span several cooling rods in each direction. A closure is provided in the channel within the critical heat flux zone of the assembly. At least one inner tube extends through the closure. The channel is closed at its upper end, and the inner tube is open at its upper end, which is located near the upper end of the channel. Egress openings are provided in the walls of the channel just above the closure. These openings are so positioned relative to the fuel tubes that jets of water emitted from them do not impinge directly on the fuel tubes, but rather enter the flow spaces between them.

Abstract: A nuclear fuel assembly for a boiling reactor comprises a plurality of fuel rods arranged in four sub-bundles surrounded by a fuel channel of substantially square cross-section. A vertical channel-formed support member for the passage of water, separates the sub-bundles of fuel rods. By arranging each sub-bundle with a reduced corner portion by not locating a fuel rod in that corner of the sub-bundle towards the center of the fuel assembly, the sub-bundles can be located in a separating channel-formed support member with an enlarged central channel. The enlarged central channel makes it possible to contain a larger quantity of non-boiling water in the central part of the fuel assembly, which results in better neutron moderation in the central part of the fuel assembly.

Abstract: A nuclear reactor fuel assembly includes an elongated fuel channel with a square cross section and channel walls, the fuel channel having an imaginary lattice disposed therein with a box-shaped cross section having mesh openings and sides parallel to the channel walls, fuel rods containing nuclear fuel being mutually spaced apart in the mesh openings, and a prismatic water pipe spaced apart from the fuel channel by a given spacing and having a cross section spanning more than one of the mesh openings of the imaginary lattice, the given spacing being completely filled with the mesh openings of the imaginary lattice and the fuel rods disposed therein.

Abstract: A fuel assembly including a channel box, upper and lower tie plates, fuel rods inserted in the channel box and held at upper and lower end portions by the upper and lower tie plates, a water rod disposed among the fuel rods and spacers for keeping the fuel rods and the water rod spaced from one another. The water rod has a diameter larger than that of each of the fuel rods and the upper end of the water rod has a height substantially as high as an upper end of an effective enriched fuel section of each fuel rod.

Abstract: A process is disclosed for providing different irradiation growth rates between a first nuclear element cladding tube of an anisotropic metal and a second cladding tube of the same metal. The process comprises tailoring the tube fabrication of each to produce cladding tubes having a crystalline structure in a desired energy state. The desired energy state is brought about by regulating the size of the final cold-work reduction and the time and temperature of heat treatment following the final reduction. The process is utilized to produce substantially equivalent irradiation growth between fuel rods and water rods. The preferred anisotropic metals are alloys of zirconium.

Abstract: For operating a PWR with spectral shift during all combustion cycles and with undermoderation during some cycles only, the reactor structure is designed for receiving either one of two types of fuel assemblies, having the same geometry. All fuel assemblies have guide tubes for receiving spectral shift clusters containing fissile material but with different elements bundles so as to be able to choose the type of operation.

Abstract: A BWR fuel assembly has a hybrid fuel design composed of both rod-type fuel and plate-type fuel. An outer hollow tubular flow channel of the assembly surrounds the rod-type fuel being provided in the form of a plurality of fuel rods so as to direct flow of coolant/moderator fluid therealong. The assembly also includes a hollow central water cross extending through the channel and composed of radially extending panels dividing the fuel rods into separate fuel rod mini-bundles. The plate-type fuel is attached on the exterior of the water cross panels. This hybrid fuel design substantially avoids PCI constraints and failures.

Abstract: An apparatus and process utilizing a large water rod of a fuel bundle in a boiling water reactor fuel assembly as a radiation heat sink during a loss of coolant accident. Core cooling spray is collected at the top end of the bundle's large water rod by a collector and distributed by a distributor to coat the inside wall surfaces of the water rod. In the case of a water rod which is not bottom vented, the water rod body is modified so as to separate the downward flow of liquid water from the upward flow of steam. During normal plant operation, the large water rod serves as a water-filled moderator tube to provide a more uniform power distribution across the fuel bundle.

Abstract: A BWR fuel assembly has a bundle of spaced fuel rods, an outer tubular flow channel surrounding the fuel rods so as to direct flow of coolant/moderator fluid along the fuel rods, and a hollow central water cross with opposed walls, a lower flow inlet end, an opposite upper flow outlet end, and an open inner cruciform flow channel for subcooled moderator fluid flow through the fuel assembly. The water cross extends through the outer flow channel and is interconnected with the outer channel so as to divide it into separate compartments and the bundle of fuel rods into a plurality of mini-bundles thereof. Also, a pair of upper and lower tie plates are connected to the opposite ends of the fuel rods in each mini-bundle thereof so as to provide a separate fuel rod subassembly in each of the compartments. The tie plates have flow openings defined therethrough for allowing the flow of the coolant/ moderator fluid into and from the separate fuel rod subsasembly.

Abstract: In a channel contained fuel bundle for a boiling water nuclear reactor, an improved channel is disclosed. The channel contains a plurality of fuel rods held in spaced apart relation by at least upper and lower tie-plates and/or spacers. In the reactor, the channel contains fuel rods extending between a lower support plate and an upper support grid. When the reactor is operating, the channel confines water flow intimately about the rod bundle on the inside and assures steam generation in a predictable pattern. Water exterior of the channel is at a different and typically lower pressure. To accommodate control blades (which control the fission process) outside of the fuel bundles, the channel is provided with a polygon cross section, most typically a square cross section. In operation, the flat walls tend to bulge due to primarily pressure effects but also due to thermal and radiation effects.

Abstract: An improved channel is disclosed which has a reduced average thickness in its upper portion. The lesser average thickness corresponds to a lower pressure difference acting on the channel sides, over the upper portion of the channel. The reduction in average thickness is accomplished by cutting flow trippers into the inner surface of the channel walls and/or cutting grooves into the outer surface of the channel. The axial variation of channel average thickness increases water volume adjacent to the upper part of the channel to provide increased neutron moderation, to minimize the steam void reactivity coefficient, and to provide a greater cold shutdown margin. The material removed to produce the flow trippers increases the cross-sectional area inside the channel and reduces pressure drop in the upper portion of the channel. The flow trippers divert water flowing on the channel walls to the fuel rods adjacent to the channel walls, permitting higher reactor power operation.

Abstract: A nuclear fuel assembly containing a plurality of vertical fuel rods and possibly occasional vertical water-filled rods, which are surrounded by a fuel channel of substantially square cross-section and which are divided, by means of a vertical channel for water of substantially cruciform cross-section, into four sub-bundles. Each fuel rod contains a stack of circular-cylindrical pellets of a nuclear fuel arranged in a cladding tube. Each sub-bundle consists of, in all, twenty-five rods arranged in a lattice containing 5.times.5 rods. The cladding tube of each fuel rod has a wall thickness in the range 0.50 to 0.70 mm and an external diameter in the range 8.5 to 10.3 mm.

Abstract: A BWR fuel assembly having an array of spaced fuel rods, an outer tubular flow channel surrounding the fuel rods so as to direct flow of coolant/moderator fluid along the fuel rods, 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, includes features which eliminate or at least minimize degradation of CHF performance and the penalties and uncertainties associated therewith. Each subassembly has spacers which surround its fuel rods and maintain them in side-by-side spaced relationship. The spacers are axially displaced apart between the bottom and top of the subassembly.

Abstract: This invention is directed to a fuel assembly for boiling water reactors incorporating an advanced type of "water rod.

Abstract: A fuel assembly has a fuel spacer consisting of a water rod having an outer diameter greater than that of fuel rods and a large number of circular sleeves into which the fuel rods are inserted. The fuel spacer has four bridge members. Both ends of these bridge members are fitted to two of eight circular sleeves which are adjacent one another in the diagonal direction of the fuel spacer. Both ends of each bridge member are bent so that its center projects outwardly away from the water rod.

Abstract: A BWR fuel assembly having an array of spaced fuel rods, an outer tubular flow channel surrounding the fuel rods so as to direct flow of coolant/moderator fluid along the fuel rods, and a hollow central water cross extending through the outer flow channel and composed of respective pairs of spaced apart sheet members interconnected together at their outer and inner ends so as to define an open inner cruciform flow channel for subcooled moderator fluid flow through the fuel assembly and to the outer channel so as to divide the array of fuel rods into a plurality of fuel rod subassemblies, includes features which improve structural and hydraulic characteristics as well as CHF characteristics. The features which improve structural and hydraulic characteristics relates to closures in the form of perforated plates connected across the bottom and top ends of the sheet members of the water cross.

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: In a nuclear fuel assembly having a plurality of separate fuel bundles secured therein in separate compartments, coolant flow paths are provided to enable the flow of coolant between the separate compartments, thereby equalizing the hydraulic pressure between the separate compartments and minimizing the possibility of thermal-hydrodynamic instability between the separate fuel bundles in the nuclear fuel assembly. A plurality of coolant flow paths are formed through solid structural ribs secured to an outer flow channel of the nuclear fuel assembly to permit coolant flow between the separate compartments.

Abstract: A segmented fuel and moderator rod and fuel assembly for a BWR. The segmented rod has a lower fuel region and an upper moderator region for passing coolant having a void fraction of between about 0-20% through the upper portion of the BWR core which is normally undermoderated. The segmented rod displaces one or more conventional fuel rods in the fuel bundle. A method of moderating a BWR core is also disclosed.

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: An improved nuclear fuel assembly includes a plurality of elongated water tubes arranged in a cross-like pattern spaced among a plurality of fuel rods for providing individual, spaced-apart coolant-moderator water flow paths lengthwise through the assembly. Some of the water tubes also function as tie rods interconnecting upper and lower tie plates of the fuel assembly.

Abstract: A BWR fuel assembly has a bundle of spaced fuel rods, an outer tubular flow channel surrounding the fuel rods so as to direct flow of coolant/moderator fluid along the fuel rods, and a hollow central water cross with a lower flow inlet end, an opposite upper flow outlet end and an open inner cruciform flow channel for subcooled moderator fluid flow through the fuel assembly. The water cross extends through the outer flow channel and is interconnected with the outer channel so as to divide it into separate compartments and the bundle of fuel rods into a plurality of mini-bundles thereof. Also, a pair of upper and lower tie plates are connected to the opposite ends of the fuel rods in each mini-bundle thereof so as to provide a separate fuel rod subassembly in each of the compartments. The tie plates have flow openings defined therethrough for allowing the flow of the coolant/moderator fluid into and from the separate fuel rod subassembly.

Abstract: A fuel assembly with a square cross section for water-cooled nuclear reactors, the fuel assembly having fuel rods disposed in a square array prescribed by spacers defining square grid meshes includes rods without fuel disposed, instead of the respective fuel rods, at individual positions of the square array distant from the marginal edge of the fuel-assembly cross section, for varying moderation ratio of the fuel assembly, the rods without fuel having a square cross section smaller than the cross section of the respective grid meshes only by a clearance sufficient for assembling the rods without fuel in the respective grid meshes and disassembling the rods without fuel from the respective grid meshes.

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

Abstract: A fuel asembly with a fuel channel (2) which surrounds a plurality of fuel rods (1) and which is divided, by means of a stiffening device (3) of cruciform cross-section and four wings (5), into four sub-channels (4) each of which comprises a bundle of fuel rods.Each fuel channel side has a plurality of stamped, inwardly-directed projections (6) arranged vertically one after the other, said projections being welded to one and the same stiffening wing. Each one of the wall portions located between the projections (6) defines, together with two adjacently positioned projections and a portion of the stiffening wing, a communication opening between two bundles located on one side each of the stiffening wing.

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.