Abstract: In one embodiment, the fuel bundle for a liquid metal cooled reactor includes a channel, a nose assembly secured to a lower end of the channel, and a plurality of fuel rods disposed within the channel. At least one of the fuel rods has at least one guard ring surround the fuel rod and spacing the fuel rod from adjacent fuel rods.

Abstract: In one embodiment, the fuel bundle for a liquid metal cooled reactor includes a channel, a nose assembly secured to a lower end of the channel, and a plurality of fuel rods disposed within the channel. At least one of the fuel rods has at least one guard ring surround the fuel rod and spacing the fuel rod from adjacent fuel rods.

Abstract: A liquid-metal cooled fast reactor core having a nuclear fuel assembly constituted of nuclear fuel rods with varying cladding thicknesses in reactor core regions, in which: the nuclear fuel assembly (1) of a liquid-metal cooled fast reactor includes nuclear fuel assemblies (1a, 1b and 1c) in inner, middle and outer reactor core regions, respectively, and is installed in a hexagonal duct (3) with nuclear fuel materials (2-2a, 2-2b and 2-2c) surrounded by respective claddings (2-1a, 2-1b and 2-1c), and the claddings (2-1a, 2-1b and 2-1c) of a nuclear fuel rod (2a) in the inner reactor core region, a nuclear fuel rod (2b) in the middle reactor core region and a nuclear fuel rod (2c) in the outer reactor core region are formed at different thicknesses. The reactor core can flatten power distribution using a single-enrichment nuclear fuel in the liquid-metal cooled fast reactor.

Abstract: A device and technique for placing and moving a ferromagnetic element in an annulus between coaxially arranged cylindrical tubes. The device includes an electromagnetic ram moved along the interior of a cylindrical tube. The movable ferromagnetic element is magnetically coupled to the electromagnetic ram and moved by magnetic force to a location in the annulus defined by the tubes and magnetically coupled to the electromagnetic ram for movement in and removal from the annulus.

Abstract: A fuel element for a nuclear reactor has fuel rods with nuclear fuel guided through spacers. The spacers are equipped with devices that exert a swirling impulse upon a coolant flowing along the fuel rods. In order to present as little flow resistance as possible for the coolant, these swirl-introducing devices have the form of a vane with a spoonlike or bladelike shape and they extend into the coolant flow. Owing to the shape—here the vane is curved in the longitudinal and in the transverse directions—practically all cross sections of the vane have such a high geometrical moment of inertia that even a vane made of a thin sheet metal is sufficiently rigid. Fuel elements configured according to the invention are particularly suitable for use in boiling water nuclear reactors.

Abstract: A crud-resistant nuclear fuel element cladding in which the axial locations that experience nucleate boiling during reactor full power operation are highly polished so that the maximum size of any surface defect on the highly polished surface is approximately 0.1 microns. The remainder of the cladding surface remains unpolished so that crud is more evenly redistributed over the entire fuel cladding surface to limit the thickness of the crud that is formed to less than 35 microns.

Abstract: A fuel assembly for a nuclear reactor, comprising a number of parallel fuel rods which are retained by means of spacer grids, arranged along the fuel rods, as well as guide thimbles wherein the guide thimbles, are fixed to the spacer grids. The guide thimbles with associated fuel rods are further fixed between a top nozzle and a bottom nozzle. In the top nozzle, through-holes are arranged for connection to a top sleeve joined to the upper end of the respective guide thimble. In the top sleeve, a first locking element is arranged for cooperation with a second locking element arranged on a guide sleeve, which guide sleeve is insertable through that hole in the top nozzle which corresponds to the respective top sleeve. The locking elements are interlocked in connected position by means of a locking sleeve insertable into the guide sleeve. The locking sleeve comprises a third locking element in the form of a through-opening arranged in the wall, a corbelled-out portion being arranged in the edge of the opening.

Abstract: The invention provides an intertube thermal conductance rate limiting device for a nuclear reactor fuel channel having an inner pressure tube and outer calandria tube. The device comprises a wire screen placed in the annular region between the pressure tube and calandria tube which limits the contact area between the two tubes. By reducing the contact area, the screen limits the thermal conductance rate to the calandria tube. This reduces or eliminates the potential for film boiling or "dryout" of the calandria tube.

Abstract: An apparatus is used for cutting guide tubes of a nuclear fuel assembly below an end-piece and removing the end-piece. The apparatus includes a mount which may be removably locked and centered on the end-piece. Cutting tools insertable in the guide tubes each include a hollow shaft whose end part is split by longitudinal slits into radially expandable fingers each having a cutting edge. A stem movable axially along each shaft cooperates therewith for spreading the fingers out radially and retracting them. The shafts are mounted for rotation on a plate which is vertically movable with respect to the mount by a jack and carries a motor for simultaneously rotating all shafts. The shafts are carried by an expansion unit movable vertically with respect to the plate by a jack and including the stems. A method for separating the end-piece with the apparatus is also described.

Abstract: A nuclear reactor fuel element is helically wound with a strip which on one face at regular intervals along its length has dimples, and has a continuous rib on the opposite face. The strip contacts the associated fuel pin cladding via the dimples which effectively act as point contacts, and it contacts the neighboring fuel pins via the rib which also provides point contact. The regions between adjacent dimples are clear of the cladding and provide coolant flow paths thereby avoiding stagnant regions. The dimples may be arranged in two staggered sets one on each side of a central rib, and the strip then wound so that the dimples in each set each align axially with a respective dimple of the other set.

Abstract: In order to multiply by three or four the combustion level of nuclear fuel pellets in fast neutron nuclear reactors, it is proposed that following a normal irradiation period of said pellets in the reactor core, that the irradiated can be replaced by a new can with an internal diameter slightly exceeding that of the first can. Thus, the pellets can undergo a new irradiation cycle in the reactor core. Preferably, the can is destroyed by progressive local melting over its entire length and the new can is preheated to facilitate the introduction of the pellets.

Abstract: Fuel array for an undermoderated nuclear reactor, comprising rods (6) arranged in a prism-shaped casing (1) parallel to the height of this casing (1). The internal surface of each of the walls (2) of the casing (1) is provided with channels (5) each of the channels (5) is located opposite a rod (6) arranged at the periphery of the array. The projecting parts (9) of the walls (2), between two channels (5), occupy part of the space between two peripheral rods (6). In this way, the moderating level remains constant throughout the cross-section of the array.The invention applies, in particular, to pressurized water reactors.

Abstract: The invention relates to a fuel assembly with cooled guide tubes for a nuclear reactor.It consists of a bundle of parallel fuel tubes (1) held in a structure comprising spacer grids, guide tubes (6) and end plates. At least a part of the guide tubes (10) comprises a set of guiding surfaces (16) projecting towards the interior of the tubes (10) over the whole of their length. The projections (16) are formed by embossing of the wall of the tube (10) and permit the guidance of the rod of absorbing material which is moved in the tube and the provision of circulating spaces for the cooling fluid between the tube and the rod of absorbing material.The invention applies in particular to pressurized water reactors and to reactors with neutron spectrum variation.

Abstract: This invention relates to a fuel assembly for fast reactors and aims to reduce stresses induced in fuel pins by interaction between a wrapper tube and a bundle of fuel elements each of which consists of the fuel pin and a wire spacer wound around the fuel pin. The fuel elements consists of two kinds of fuel elements, one of them consists of conventional fuel pins and wire spacers and the other fuel pins of smaller diameter than the conventional fuel pins and wire spacers of larger diameter than the conventional wire spacers whereby the fuel assembly is provided with larger space therein.

Abstract: The invention relates to a method for producing an assembly, as well as to an assembly produced by this method.The foot of the assembly is butt welded to the hexagonal tube prior to the introduction of the bundle of rods into the latter. This introduction takes place in the vertical direction using a jack which passes through the foot of the assembly. The upper neutron protection is then fixed by pressing the tube into recesses. Finally, the vacuum producing system and the plug are fitted in the foot.Application to assemblies for fast neutron nuclear reactors.

Abstract: A nuclear fuel element suitable for use in fast breeder. The fuel element has a clad tube and a wire spacer wound round the clad tube. The clad tube of the fuel element is composed of a first clad tube and a second clad tube which are connected to each other through an intermediate plug. The first clad tube extends upwardly from the intermediate plug. The upper end of the first clad tube is closed by an upper end plug, while the lower end of the second clad tube is closed by a lower end plug. The first clad tube is charged with a multiplicity of fuel pellets, while the second clad tube defines a gas plenum therein. The spaces inside the first and second clad tubes are communicated with each other through vent holes formed in the intermediate plug. The wire spacer is wound round the first clad tube and is fixed at its one end to the end plug attached to the first clad tube and at its other end to the intermediate plug.

Abstract: An improved heat exchanger in which the tube bundle therein comprises a plurality of tubes supported intermediate their ends by at least one annular enlargement disposed around and frictionally secured to the outer surface of at least one of the tubes with the annular enlargement contacting the outer surface of each tube next adjacent thereto. Means are also provided for encircling and maintaining the tubes in spaced relation in contact with the annular enlargements. Method of constructing the tube bundle for the heat exchanger is also disclosed.