Abstract: A nuclear reactor fuel assembly with two support plates and a holding rod connecting the two support plates rigidly with mutual spacing, the holding rod having a longitudinal axis passing through both support plates, and being held at one end in a lead-through in one of the two support plates, includes, in the lead-through, an elongated holding body for the holding rod rotatable about the longitudinal axis thereof, and displaceable in direction of the longitudinal axis thereof coaxially with the lead-through; the holding body being rigidly connectible by a rotation relative to the holding rod about the longitudinal axis thereof to an end of the holding rod and tightenable against a holding shoulder in the one support plate and detachable from the holding rod; and a spring element braced against the support plate and pressing the holding body elastically against the holding shoulder.

Abstract: A nuclear fuel assembly includes and upper yoke, a base, an elongated, outer flow channel disposed substantially along the entire length of the fuel assembly and an elongated, internal, central water cross, formed by four, elongated metal angles, that divides the nuclear fuel assembly into four, separate, elongated fuel sections and that provides a centrally disposed path for the flow of subcooled neutron moderator along the length of the fuel assembly. A separate fuel bundle is located in each of the four fuel sections and includes an upper tie plate, a lower tie plate and a plurality of elongated fuel rods disposed therebetween. Preferably, each upper tie plate is formed from a plurality of interconnected thin metal bars and includes an elongated, axially extending pin that is received by the upper yoke of the fuel assembly for restraining lateral motion of the fuel bundle while permitting axial movement of the fuel bundle with respect to the outer flow channel.

Abstract: A tool for the manufacture of a fuel assembly, said tool comprising for each end of an assembly an inner metal plate which can be applied to the bottom of an end member, an outer metal plate which can be displaced, under the action of a jack, along sliding columns fixed to the inner plate, in longitudinal translation with respect thereto and threaded ties traversing corresponding openings in the end member and in the inner and outer plates, able to engage with the internal thread of the guide tubes, and each provided with a head on which is supported a spring for compensating the action of the jack. A method for utilizing the tool is set forth, also.

Abstract: A mechanically attached load pad for the duct of a liquid metal nuclear reactor fuel assembly.

Abstract: Improvements to guide tubes for the fuel assemblies of light water nuclear reactors, said assemblies being immersed in operation in the cooling water of the core of such a reactor, the guide tubes being of the type made from zircaloy and fixed at their two ends respectively to an upper end part and a lower end part made from stainless steel or Irconel and which incorporate devices for braking the fall of the control rods which they house during the rapid shutdown of the reactor, wherein the said braking devices are constituted by means for restricting the diameter of the guide tubes comprising for each guide tube a zircaloy inner sleeve spot welded to the said guide tube and whose internal diameter permits the passage, with a calibrated clearance, of the corresponding control rod, the sleeve being distributed over the lower portion of each guide tube and associated with orifices made in the actual guide tubes to produce the progressive hydraulic absorption of the end of the fall of the control rods.

Abstract: A fuel assembly for a boiling water reactor comprises a plurality of fuel rods (2, 2'), which constitute four partial bundles and are surrounded by a fuel channel system (1) comprising one partial tube for each partial bundle. Each of the four partial bundles rests on a bottom tie plate (19) and is positioned with respect to the others by means of a common top tie plate (31), which is provided with a lifting loop (33) which is sufficiently strong to be able to lift the four partial bundles simultaneously, a major part of the lifting force being transmitted to said bottom tie plates via a plurality of supporting fuel rods (2').

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

Abstract: Disclosed is a remotely operable releasable sealing coupling which provides fluid-tight joinder of upper and a lower conduit sections. Each conduit section has a concave conical sealing surface adjacent its end portion. A tubular sleeve having convex spherical ends is inserted between the conduit ends to form line contact with the concave conical end portions. An inwardly projecting lip located at one end of the sleeve cooperates with a retaining collar formed on the upper pipe end to provide swivel capture for the sleeve. The upper conduit section also includes a tapered lower end portion which engages the inside surface of the sleeve to limit misalignment of the connected conduit sections.

Abstract: In a fuel assembly for a nuclear reactor a fuel element spacer formed of an array of laterally positioned cojoined tubular ferrules each providing a passage for one of the fuel elements, the elements being laterally supported in the ferrules between slender spring members and laterally oriented rigid stops.

Abstract: The present invention relates to an upper neutron protection device for a nuclear reactor assembly.This device comprises at least one container partly filled with a neutron-absorbing product and maintained within a wall located in the upper part of the assembly by at least one spacing plate.Application to fast neutron reactors.

Abstract: A nuclear reactor fuel assembly for a nuclear reactor comprises a housing with a wall and spacer means removably located within the housing, the spacer means comprising a plurality of spacer cells each adapted to receive an elongated fuel rod for the purpose of locating a bundle of such fuel rods in spaced-apart relationship within the housing. A portion of the housing which confronts the spacer means is provided at least at one location with a first locking means, and one of the spacer cells is provided with a second locking means movable between active and inactive positions. This second locking means is prevented from moving past the first locking means in the direction of elongation of the fuel rods when the second locking means is in its active position but is able to move past the first locking means when in its inactive position. The second locking means is moved from its inactive position to its active position by the insertion of a fuel rod into said one spacer cell.

Abstract: A device is described for supporting a nuclear fuel rod in a fuel rod assembly which allows the rod to be removed without disturbing other rods in the assembly. A fuel rod cap connects the rod to a bolt which is supported in the assembly end fitting by means of a locking assembly. The device is designed so that the bolt is held securely during normal reactor operation yet may be easily disengaged and the fuel rod removed when desired.

Abstract: Alignment tool for the remotely controlled recalibration of resilient protruding contact dimples or springs in substantially square spacer grid meshes of nuclear reactor fuel assemblies, including an outer centering tube adapted to the cross section of a spacer mesh and rigid and resilient contact dimples protruding into the interior of the mesh in given directions, the outer centering tube having a window formed therein in the vicinity of the contact dimple, a gripper-actuating tube being concentrically surrounded by and axially movable within the outer centering tube, a pendulum rod having a free end and being disposed in the interior of the gripper-actuating tube and being axially fixed relative to the gripper-actuating tube and able to oscillate in the given protrusion direction of the resilient contact dimple to be recalibrated, a gripper attached to the free end of the pendulum rod, a restoring spring for exerting pressure on the gripper, and a run-on incline formed on the pendulum rod being engageable

Abstract: A composite nozzle for a fuel assembly adapted for installation on the upper or lower end thereof and which is constructed from two components. The first component includes a casting weldment or forging designed to carry handling loads, support fuel assembly weight and flow loads, and interface with structural members of both the fuel assembly and reactor internal structures. The second component of the nozzle consists of a thin stamped bore machine flow plate adapted for attachment to the casting body. The plate is designed to prevent fuel rods from being ejected from the core and provide orifices for coolant flow to a predetermined value and pressure drop which is consistent with the flow at other locations in the core.

Abstract: The object of the invention is a nuclear reactor fuel assembly including fuel elements arranged in a supporting frame comprising two endpieces, the upper (1) and the lower (2) respectively, to which are attached the ends of a plurality of vertical tubes (3), each endpiece 1(2) including a plane base 11(21) in which are arranged two series of orifices 7 for retaining the tubes (3) and for the flow of the cooling fluid.In accordance with the invention the base (11,21) of each endpiece (1,2) is joined side by side with an inner plate (15,25) equipped with the same series of orifices (70) for retaining the tubes (3) and for the flow of the fluid, and the orifices (70) have an oblong cross-section and are equipped with parts for attachment which cooperate with corresponding parts (31) for attachment of the said tubes (3) by transverse displacement of the inner plate.

Abstract: Device for fixing a zircaloy guide tube of a fuel assembly of a pressurized ordinary water nuclear reactor to the steel end plate thereof.This device comprises a ring nut having two threads with opposite pitches, a screwdriver sleeve with teeth, integral in rotation with a pole but mobile in translation by means of an elastic return system along the said pole between a first low position in which the teeth carried by the said screwdriver sleeve are located in recesses in the upper part of the ring nut, which they thereby lock in rotation with the pole and the end fitting and a second upper position in which the teeth are disengaged from the recesses and where the ring and end fitting rotate independently of one another.Application to fuel assemblies of nuclear reactors of the PWR type.

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: An improved nuclear fuel assembly in which the lowermost grid is located close to the lower end fitting of the assembly, and a conventional Zircaloy-clad fuel rod is fitted with a stainless steel tip having a bevelled notch thereon for engaging resilient means on the grid within about one inch (2.5 cm) from the lower tip of the fuel rod. The notch mechanically restrains the fuel rod from lifting upwards during reactor operation, yet is shallow enough to permit removal of the fuel rod in the event reconstitution is required. The stainless steel tip is mechanically secured to the Zircaloy end cap of the fuel rod, and is located in a low importance flux region of the core so that the higher neutron poison absorption cross section of stainless steel is of little consequence. Since the lowermost grid secures each fuel rod within one inch of the lower end of the rod, there is little likelihood that the coolant flowing over the lower ends of the fuel rods will induce significant vibrations.

Abstract: A fuel assembly in a nuclear reactor comprises a locking mechanism that is capable of locking the fuel assembly to the core plate of a nuclear reactor to prevent inadvertent movement of the fuel assembly. The locking mechanism comprises a ratchet mechanism that allows the fuel assembly to be easily locked to the core plate but prevents unlocking except when the ratchet is disengaged.

Abstract: A reusable system for removably attaching the upper end 10of a nuclear reactor duct tube to the lower end 30 of a nuclear reactor fuel assembly handling socket. A transition ring 20, fixed to the duct tube's upper end 10, has an interior-threaded section 22 with a first locking hole segment 24. An adaptor ring 40, fixed to the handling socket's lower end 30 has an outside-threaded section 42 with a second locking hole segment 44. The inside 22 and outside 42 threaded sections match and can be joined so that the first 24 and second 44 locking hole segments can be aligned to form a locking hole. A locking ring 50, with a locking pin 52, slides over the adaptor ring 40 so that the locking pin 52 fits in the locking hole. A swage lock 60 or a cantilever finger lock 70 is formed from the locking cup collar 26 to fit in a matching groove 54 or 56 in the locking ring 50 to prevent the locking ring's locking pin 52 from backing out of the locking hole.

Abstract: A bottom end member (17b) on a retrievable fuel pin (13b) secures the pin (13b) within a nuclear reactor (12) by engaging on a transverse attachment rail (18) with a spring clip type of action. Removal and reinstallation if facilitated as only axial movement of the fuel pin (13b) is required for either operation. A pair of resilient axially extending blades (31) are spaced apart to define a slot (24) having a seat region (34) which receives the rail (18) and having a land region (37), closer to the tips (39) of the blades (31) which is normally of less width than the rail (18). Thus an axially directed force sufficient to wedge the resilient blades (31) apart is required to emplace or release the fuel pin (13b) such force being greater than the axial forces on the fuel pins (13b) which occur during operation of the reactor (12).

Abstract: A reconstitutable fuel assembly for a nuclear reactor which includes a mechanical, rather than metallurgical, arrangement for connecting control rod guide thimbles to the top and bottom nozzles of a fuel assembly. Multiple sleeves enclosing control rod guide thimbles interconnect the top nozzle to the fuel assembly upper grid. Each sleeve is secured to the top nozzle by retaining rings disposed on opposite sides of the nozzle. Similar sleeves enclose the lower end of control rod guide thimbles and interconnect the bottom nozzle with the lowermost grid on the assembly. An end plug fitted in the bottom end of each sleeve extends through the bottom nozzle and is secured thereto by a retaining ring. Should it be necessary to remove a fuel rod from the assembly, the retaining rings in either the top or bottom nozzles may be removed to release the nozzle from the control rod guide thimbles and thus expose either the top or bottom ends of the fuel rods to fuel rod removing mechanisms.

Abstract: A typical embodiment of the invention provides a nuclear fuel assembly lock structure for control rod guide tubes. Illustratively, a sleeve telescopes over an end portion of a control rod guide tube which bears against an internal shoulder of the tube. The upper end of the sleeve protrudes beyond the control rod guide tube spider and is locked in place by means of a resilient cellular lattice or lock that is seated in a mating groove in the outer surface of the sleeve. A special tool is provided for disengaging the entire lock structure, washer, spider, spring and grill from the end of the fuel assembly in order to enable these components to be removed in an assembled state and subsequently replaced on the fuel assembly after inspection and repair.

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

Abstract: A fuel assembly having a lower end fitting and a spidered actuating rod interacting therewith for holding the assembly down on the core support stand against the upward flow of coolant. Locking means and bracing means for interacting with projections on the support stand are carried by the lower end fitting and are actuated by the movement of the actuating rod operated from above the top of the assembly. The locking means include weak springs mounted near some but not all of the end fitting posts, for engaging the support stand. Stiff springs are mounted internal to the other posts, for uring the posts against adjacent support stand projections to provide a bracing for the locking means as the spider portion of the actuating rod presses against the locking spring. The angle and spring rate per unit length of the bracing spring are preset to assure a fairly constant locking force during the life of the assembly.

Abstract: An easily dismountable fuel assembly for a nuclear reactor comprising a bundle of parallel fuel slugs held spaced apart by cross-pieces transverse to the slugs and by assembly bearing tubes which take the places of some of the slugs, the tubes being longer than the slugs and being secured at each end to a respective plate for maintaining the fuel assembly rigid. Each tube is secured to at least one end plate by a cylindrical sleeve comprising a connection complementary with a corresponding connection borne by the respective end of the tube and formed with a profile for engagement by a tool for rotating the sleeve around its axis in one direction for securing it to the tube and clamping the tube to the end plate in the axial direction, and in the other direction for releasing the tube from the plate.

Abstract: A method of refueling a nuclear reactor having a core containing a plurality of fuel rod bundles which are built up from a plurality of fuel rods includes replacing at least one burnt up fuel rod bundle with a fuel rod bundle which is at least partly composed of fuel rods from other fuel rod bundles burnt up in the reactor, the mean content of fissile material in the fuel rod bundle thus composed being higher than the mean content of fissile material in the fuel rod bundle which is replaced by the composed fuel rod bundle.

Abstract: A nuclear reactor fuel assembly comprises a bundle of parallel rods which are transversely spaced by cross-pieces, and is supported by support tubes which extend between, and are fixed at their ends to, two grids. The grids have cells which are aligned with the fuel rods and through which the fuel rods can be withdrawn. The grids are detachably connected to end plates by sockets which are removably engaged in the end plates and cells of the grids.