Abstract: A fuel assembly for use in a pressurized water nuclear reactor includes an assembly having guide tubes joined at their upper ends to posts having heads against which is biased a holddown plate spaced from a flow plate. The holddown plate is slidably mounted on the posts. The flow plate is fixed to the posts. The joints have one either post or tube member with spring fingers with projecting steps to lock in abutting relation behind the flow plate with a ring projection on the other captured in a recess in the adjacent finger surfaces. This structure provides a quick connect joint between the tube and the post.

Abstract: A method and an apparatus for inspecting a core shroud by remote operation. The apparatus is a robotic scanning device which can be installed in the narrow space between the core shroud and the jet pumps and which can scan azimuthally and vertically around the circumference of the core shroud. The scanning device provides gross positioning to the area of interest and precise motion control in a limited scanning range. The scanning uses a thin wide arm to support a bank of transducers at its bottom end, and is rigidly mounted to a precision two-axis positioner at its top end. The arm is of narrow thickness to pass through the 0.5-inch access opening and to allow radial flexibility to absorb surface contour variation over the inspection area. The transducer mounting includes a water jet thruster to provide a radially inwardly directed reaction force to maintain the transducers in contact against the shroud. The arm is fabricated with a row of longitudinal holes extending throughout its length.

Abstract: A method for mitigating crack initiation and propagation on the surface of metal components in a water-cooled nuclear reactor. An electrically insulating coating doped with a noble metal is applied on the surfaces of IGSCC-susceptible reactor components. The preferred electrically insulating material is yttria-stabilized zirconia doped with palladium or platinum. The presence of an electrically insulating coating on the surface of the metal components shifts the corrosion potential in the negative direction without the addition of hydrogen. Corrosion potentials .ltoreq.-0.5 V.sub.SHE are believed to be achievable even at high oxidant concentrations and in the absence of hydrogen, although the coatings are believed to be particularly suited to applications where a reductant, such as hydrogen, is present.

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: The surface of the component (1, 2) to be protected is scanned, a jet of semitransferred arc plasma (17) into which a metal powder is introduced. The process can be applied to the production of a layer of coating (18) on the outer surface of a region of welding connection (3) between a nozzle (1) and a primary pipe (2) of a pressurized water nuclear reactor or to the coating of the inner surface or the connecting surface of an adapter passing through the reactor vessel head.

Abstract: An improved method for assembling bundles of nuclear fuel rods which reduces damage to the fuel cladding surface as the fuel rods are passed through an array of spacers. In particular, the invention prevents or greatly reduces the severity of longitudinal scratches on the fuel rods. The method uses thin-walled metallic tubes having a wall thickness of 0.003 to 0.006 inch and a yield strength in excess of 140,000 psi. The predetermined tube thickness ensures that the tube remains elastic. The tube deflects the cell springs when inserted in the spacer cells and reduces the load exerted on the fuel rods.

Abstract: A nuclear fuel assembly debris filter. Each fuel rod has a ring attached to the lower end cap. The rings are shaped and sized to define a space between the lower end cap and ring such that the space serves to trap, or filter, debris before it reaches the elevation of the fuel cladding. The rings may be circular, elliptical, or any suitable shape that provides the desired filtration effect.

Abstract: The device includes a first tubular support (11) carrying on its outside surface means for fixing to a handling tool, a second tubular support (18) mounted coaxially inside the first support (11) for rotation about its axis. A flexible strip (55) carrying a monitoring probe at one of its ends is engaged in a slideway support carried by the second support (18) and including an end part (65) mounted to pivot about an axis which is perpendicular to the axis (25) of the second support (18). The strip (55) is moved translationally along the axial direction (25) by a conveyor bolt (53). The inside surface of the tubular piece (3) is monitored by moving the probe fixed to the end of the flexible strip (55) rotationally about the axis (25) and in axial translation, inside the annular space (8) between the sleeve (5) and the tubular piece (3).

Abstract: An end plug is inserted into the end of a nuclear fuel pin cladding tube after loading mixed oxide fuel pellets into the tube from a containment area. During the pellet loading operation, a disposable sleeve and an end plug carrier protect the external surfaces of the cladding tube and the end plug from contamination. The sleeve, mounted on the end of the cladding tube, is inserted into a seal arranged in a wall of the containment area. The end plug, located within a recess in the plug carrier, is then inserted into the end of the cladding tube by sliding the carrier through the sleeve. Upon removal of the cladding tube, the sleeve and the carrier are retained in the seal for ejection into the containment area during the next pellet loading operation.

Abstract: A resistance welding method for a fuel rod is presented in which the gas seal opening is closed with a sealing material of the same composition as the end plug material. The method enable to perform welding stably in a pressurized welding chamber, and the process is amenable to automation. The sealing material body is made of a wire, and is pressed against the conical shaped opening provided on the end plug. The welding method avoids contaminating the weld with undesirable impurities from the electrode material, and the welding operations is designed so that there is no need to reshape the end of the electrode or adjust the gap between the sealing material and the seal opening.

Abstract: A TIG welding system for controlling the weld shape for the seal welding of a small pressurization hole in the end plug of nuclear fuel rods. The controlled shape of the seal weld enables improved ultrasonic detection capabilities. The system achieves the desired weld shape by controlling the pressure differential between the interior and exterior volumes of the fuel rod. The weld box pressure is decreased in accordance with Boyle's law while the weld material for sealing the hole is molten. The system uses an output from the weld electronics as an input to a programmable logic controller ("PLC"). After a programmed time delay, the PLC outputs a signal to a solenoid valve to open a "ballast" volume. The expansion of gas from the weld box into the ballast volume causes a sudden drop in pressure to a level below the pressure inside the fuel rod. As a result of this pressure differential, the molten weld material forms a concave weld upon solidification.

Abstract: A composite holddown spring for applying an axial force to a fuel pellet stack in a nuclear reactor fuel rod. The composite holddown spring comprises a shape-memory alloy spring portion and a conventional metal spring portion. The shape-memory alloy spring portion has a two-way memory characteristic such that it contracts to a low temperature configuration at ambient temperatures wherein the axial force exerted by the shape-memory alloy spring portion is minimized and expands to a high temperature configuration at operating conditions wherein the axial force exerted by the shape-memory alloy spring portion is maximized. Somewhat conversely, the conventional metal spring portion weakens and contracts at operating temperature and strengthens and expands at atmospheric temperature.

Abstract: A process is presented for fabricating a fuel rod including an elongated fuel tube, a lower end plug for sealing one of the openings, and an upper end plug for sealing an opposite opening. The steps include sealing an opening of the aperture by melting the lead portion of the upper end plug in such way that welding is carried out along the lead portion and a welded portion formed by the welding is disposed below the lower portion of the chamfer. The elongated fuel tube has openings at opposite end thereof, and a plurality of fuel pellets inserted therein. The upper end plug has an end face and an outer peripheral surface, a chamfer formed at an intersection between the end face and the outer peripheral surface, an aperture formed in the center of the upper end plug, a groove formed around the aperture, and a lead portion formed between the aperture and the groove.

Abstract: A low pressure drop easy load fuel assembly rod end cap 40 for pressurized water reactor fuel assembly rods 10 has a solid Zircaloy radiused tip 42. The tip 42 blends into a longitudinal profile defined by a smooth convex curve 44,46 which blends into a substantially cylindrical surface portion 48 of a diameter substantially equal to the diameter of the fuel cladding tube or other shank 50.

Abstract: A part length fuel rod tip and group of tip grasping tools is set forth for the removal, inspection and replacement of part length fuel rods from a fuel bundle having a part length rods interspersed with a majority of conventional full length rods. The part length fuel rod tip includes a longitudinal keyway allowing torque to be exerted on the fuel rod and a horizontal slot enabling grasping of the fuel rod for vertical withdrawal and replacement movement of the fuel rod. The tools include a torque socket for applying high torque forces to the part length rod for unscrewing the rod when the rod becomes stuck at its threaded connection to the lower tie plate, a tip grasping tool for permitting normal unscrewing torque and grasping for vertical withdrawal and replacement, and finally a tool having both high torque and grasping characteristics.

Abstract: The invention relates to a method of sealing a fuel rod (1) after pressurization with helium. The method comprises supplying helium to the fuel rod via a fill hole (3) provided through the plug (2). Over the fill hole (3) there is placed a body (4) which, upon sealing, is welded against the plug by means of resistance projection welding.

Abstract: To inspect the integrity of pressurization holes in nuclear fuel rod final end plugs, quality assurance apparatus includes an adapter providing a test chamber into which an end plug is inserted. Instrument gas is introduced into the test chamber through an inlet port for flow to the atmosphere through the pressurization hole. A mass flow meter measures the gas flow through the pressurization hole to determine if it is capable of supporting requisite pressurization of a nuclear fuel rod when the end plug is assembled thereto.

Abstract: A fuel assembly for a boiling water nuclear reactor contains a plurality of vertical fuel rods, which are arranged between a bottom tie plate and a top tie plate in a surrounding vertical casing part. At its lower end the casing part is connected to a bottom part which is provided with an inlet opening for water for conducting water in through the bottom tie plate, through the space between the fuel rods in the vertical casing part and out through the top tie plate. A debris catcher with a low flow resistance to water is provided below or above the bottom tie plate and at a distance from the bottom tie plate.

Abstract: A removable and reusable cap for fuel rod ends to prevent grid damage during loading permits fuel end configurations to match utility's special tooling for fuel assembly repair and reconstitution. The elastomeric transitory fuel rod guidance ends expand over a flange and temporarily snap into place in a groove in the fuel rod end to provide a tapered guiding surface.

Abstract: The lower connector (10) comprises a transverse element (12) having a box-shaped structure. The transverse element (12) comprises a reticular structure (13) resistant to bending and limited externally by a frame (14), the cross-section of which corresponds substantially to the cross-section of the assembly. The structure (13) has large-size cells. The transverse element comprises, furthermore, a retaining plate (20) pierced with small-size orifices and superposed on and fastened to the recticular structure (13) parallel to the latter and with a spacing (b), to form the upper part of the connector (10) and delimit a free space for steadying the cooling water of the reactor and for recovering debris carried along by the water, forming the hollow central part of the box-shaped structure.

Abstract: A method of controlling the gas atmosphere in a welding chamber includes detecting the absence of a fuel rod from the welding chamber and, in response thereto, initiating the supplying of a flow of argon gas to the chamber to purge air therefrom. Further, the method includes detecting the entry of a fuel rod in the welding chamber and, in response thereto, terminating the supplying of the flow of argon gas to the chamber and initiating the supplying of a flow of helium gas to the chamber to purge argon gas therefrom and displace the argon gas in the chamber. Also, the method includes detecting the withdrawal of the fuel rod from the welding chamber and, in response thereto, terminating the supplying of the flow of helium gas to the chamber and initiating the supplying of argon to the chamber to purge the air therefrom.

Abstract: A trepan is provided in a flat end face of an end plug about an external opening of an axial bore through the end plug. The trepan includes an annular groove encircling the external opening and an annular end face portion extending between the annular groove and the external opening. The ratio of the depth of the groove to the diameter of the annular end face portion of the trepan is within a range of from about 1:3 to 1:6. The ratio of the depth of the groove to the width thereof is within a range of from about 1:1 to 1:2. When an axially-directed welding arc is applied to the trepan in the flat end face of the end plug a melting of the material of the trepan into the end face occurs which forms a weld seal such that the trepan is replaced by a shallow concavity overlying the weld seal and extending across the region substantially encircled originally by the annular groove of the trepan.

Abstract: An improved lower end fitting (L.E.F.) having a bell mouth type of flow jet diffuser decrease pressure drop 10-15%, more evenly distributes flow and adds strength. It includes neutron thimble flux impingement shield of instrument and/or cable. Diffusers are stainless steel of circular cross-sect. and parabolic to optimize diffusion. Shape is based on lower core plate flow hole geometry, L.E.F. design and reactor flow rate. Thinner L.E.F. legs, smaller L.E.F. gussets and thinner L.E.F. flow plates possible.

Abstract: A method of forming a gripper cavity in a nuclear fuel rod end plug includes the basic steps of providing an end plug blank having an internal bore of substantially uniform diameter that opens at an annular outer rim on the end plug blank, cold forming the end plug blank to produce an intermediate end plug in which the annular outer rim is transformed into a conical outer rim having a rounded internal surface that defines an inlet opening to the internal bore of a diameter less than that of the internal bore, and removing an external layer of material from the intermediate end plug and an internal layer of material from the rounded internal surface of the conical outer rim to produce a finished end plug having an internal gripper cavity composed of the internal bore and a cylindrical internal surface defining the inlet opening to the internal bore and being of smaller diameter than the internal bore.

Abstract: A dashpot in a control rod guide thimble for a nuclear fuel assembly includes a lower tubular portion of an elongated main tube of the guide thimble, an auxiliary hollow tube inserted in the lower portion of the main tube, and an end plug attached to a lower end portion of the auxiliary tube. The auxiliary tube has an outside diameter slightly less than an inside diameter of the main tube to permit a close fitting relationship between an exterior surface of the auxiliary tube and an interior surface of the main tube lower portion. The auxiliary tube also has an upper end portion with an inside surface portion in axial cross-section flaring upwardly and outwardly to provide a tapered transition extending between and connecting an interior surface of the auxiliary tube with the exterior surface thereof.

Abstract: A gas cooled nuclear fuel element having a particle fuel retention device which acts as a passive restraint in the event of failure of hot frit. A particle fuel retention device is positioned either in the annular space within the inner frit, in the end cap through which coolant gas flows, or attached to the end cap and extending axially beyond the fuel element.

Abstract: An end cap is mounted on a fuel rod gripper to cover the end portions of fingers thereon to minimize impacts with grid cell dimples. The fingers are defined by circumferentially-spaced and longitudinally-extending slots in the gripper which permit the finger end portions to radially expand and retract between corresponding expanded and collapsed conditions. The end cap includes a body having a forward camming portion and a rearward mounting portion. The rearward mounting portion is hollow and configured to fit over and cover the end portions of the gripper fingers with the forward camming portion extending forwardly thereof. Also, circumferentially-spaced and longitudinally-extending attachment flutes are disposed internally of the hollow mounting portion of the body and project radially inwardly therefrom.

Abstract: The device for pressure-sealed obturation comprises a flexible tubular casing (22) having an open end along the perimeter of which the casing constitutes an inflatable toric seal (30) and a base (22a) in the form of a glove finger on which there is fixed the end of a shaft (21) disposed at the central part of the casing (22). The shaft (21) passes through the base (22a) of the casing (22) in a sealed manner. The device also comprises a plate (38) for retaining the casing (22) comprising at least two parts articulated to one another as well as retention plate (41) for fixing the retaining plate (38) under the base (22a). Ring shaped elements (43) are retained against the toric seal (30) by an articulated spacing device (47).

Abstract: A hollow plug for blocking a heat exchanger tube includes an expansion zone expanded into a frictional connection with the heat exchanger tube. An outer surface in the expansion zone has a first part with a relatively greater surface hardness and a second part with a relatively lesser surface hardness. The first part has a greater surface hardness than the heat exchanger tube. The second part has a lesser surface hardness than the heat exchanger tube. The first part also has a relief pattern.

Abstract: A modular fuel assembly has a plurality of axially stacked subassemblies. The stacked subassemblies includes upper and lower subassemblies which incorporate top and bottom nozzles, and a plurality of intermediate subassemblies disposed between the upper and lower subassemblies. Each subassembly includes a plurality of elongated guide thimble segments, a plurality of fuel rod segments and a pair of support grids mounted to the guide thimble segments and supporting the fuel rod segments. The guide thimble segments of the upper and lower subassemblies are releasably mounted to the respective top and bottom nozzles thereof.

Abstract: A pressurized water reactor fuel assembly (10) has a fastener or bolt (40) of stainless steel with a longitudinal groove (48) attaching zircaloy guide tubes (16) to stainless steel lower end fitting (14). The guide tubes have internally threaded zircaloy plugs (52) for mating with the threads (46) of bolt (40) with points (50) created in the threads (46) by groove (48) providing increased friction. The groove (48) acts to accommodate stresses set up by differential thermal expansion of zircaloy and stainless steel. Apertured stainless steel cups (60) receive the plugged ends of guide tubes (16) to capture them and provide connections to lower grid (22) of stainless steel.

Abstract: In a BWR- or PWR-type nuclear reactor, the fuel rods in the fuel assembly are cooled by a coolant flow which is pumped through the fuel core. Depending on the degree of burnup of the fuel rods, the coolant flow to the fuel assemblies may need to be changed for the cooling to be matched to local need. To control coolant flow on the basis of the degree of burnup of the fuel rods, the irradiation growth of elongated elements in the fuel assembly has been utilized.

Abstract: An end stop is adapted for engaging the sealing plug positioned in the end of a nuclear fuel rod and so as to permit the evacuation of the fuel rod to facilitate girth welding of the plug onto the rod, and to permit pressurization of the fuel rod and an enclosing welding chamber to facilitate the seal welding closure of the axial opening in the end stop. The end stop includes an axial passage extending therethrough having a welding electrode coaxially positioned therein to facilitate the seal welding closure of the fuel rod sealing plug. An air channel extends between the axial passage and an outlet on the surface of the end stop. A one-way valve is positioned in the air channel for permitting the free passage of a gas from the axial passage to the outlet into the welding chamber while precluding passage of a gas in the reverse direction.

Abstract: An end cap is mounted on a fuel rod gripper to cover the end portions of fingers thereon to minimize impacts with grid cell dimples. The fingers are defined by circumferentially-spaced and longitudinally-extending slots in the gripper which permit the finger end portions to radially expand and retract between corresponding expanded and collapsed conditions. The end cap includes a body having a forward camming portion and a rearward mounting portion. The rearward mounting portion is hollow and configured to fit over and cover the end portions of the gripper fingers with the forward camming portion extending forwardly thereof. Also, circumferentially-spaced and longitudinally-extending attachment flutes are dispsoed internally of the hollow mounting portion of the body and project radially inwardly therefrom.

Abstract: An end plug is welded to a nuclear fuel rod tube by a girth weld having a melt-zone arcuately extending through the tube wall and into the plug, wherein the melt-zone and the end of the tube are separated by a predetermined distance. The distance is chosen such that heat is dissipated from the weld-zone to prevent damage to the rod and to prevent damage to the weld end stop. This weld enables the use of a substantially solid cylindrical end plug having a first end disposed inside the tube, a second end, and a hollow cavity extending to the second end for axially aligning the cylinder and fuel rod with a frictionally engaging weld stop during formation of the girth weld.

Abstract: A spring retainer is disclosed for use in retaining fuel pellets in a fuel rod both during fabrication and shipment to prevent the fuel pellets from being moved from their design location before installation within a reactor. The cylindrical and solid nuclear pellets containing the reactor fuel are placed within the fuel rods (or cladding) and have an outside diameter slightly less than the inside diameter of the fuel rod. Once the pellets are in place, a two-part spring holder is inserted into the end of the fuel rod. A first compression spring part of the coil spring holder is a conventional coil spring which, acting in compression, bears against the fuel pellets with a preselected force typically forcing the pellets when in the horizontal position into a compacted disposition when the fuel rod is horizontal. This conventional coil spring has a diameter which is less than the inside diameter of the fuel rod.

Abstract: A nuclear reactor fuel rod end plug (100) is adapted to be welded within each end of a nuclear reactor fuel rod cladding tube, especially by means of laser beam welding techniques, although TIG welding techniques may also be employed, wherein an annular groove (126) is defined about the external periphery of the end plug (100) so as to extend radially inwardly of the long land region (118) of the plug (100) within the vicinity of the juncture of the land surface (118) and the shoulder portion (120) at which location the girth weld between the end plug (100) and the cladding tubing will be defined.

Abstract: A solid or hollow replacement rod 40 for use in a pressurized water reactor (PWR) fuel assembly 10 inserts into cells of the spacer grids 18, 20 and 22 past mixing vanes 32, without damaging them, because of its asymmetric tip 42 formed by chamfer 54 and elongated curved surface 52 and its offset "x" formed by the bowed end section 44.

Abstract: A zirconium-based alloy with a high corrosion resistance, consisting essentially of 1 to 2 wt % Sn, 0.20 to 0.35 wt % Fe, 0.03 to 0.16 wt % Ni and the balance substantially Zr. The Fe/Ni content ratio of the alloy ranges between 1.4 and 8. The structure of the alloy has fine intermetallic compound of Sn and Ni is precipitated within the zirconium crystal grain of .alpha.-phase. The alloy may further contain 0.05 to 0.15 wt % Cr. This alloy exhibits reduced hydrogen absorption rate and suffers from no nodular corrosion, so that it can suitably be used as a material of nuclear fuel cladding tubes. The nuclear fuel cladding tube made of this alloys exhibits extended service life when used in a nuclear reactor of high degree of burn-up.

Abstract: A stuck fuel rod capping sleeve to be used during derodding of spent fuel assemblies if a fuel rod becomes stuck in a partially withdrawn position and, thus, has to be severed. The capping sleeve has an inner sleeve made of a lower work hardening highly ductile material (e.g., Inconel 600) and an outer sleeve made of a moderately ductile material (e.g., 304 stainless steel). The inner sleeve may be made of an epoxy filler. The capping sleeve is placed on a fuel rod which is then severed by using a bolt cutter device.

Abstract: The nuclear fuel element according to the invention comprises a can, which is sealed at its ends by plugs, whereof a cylindrical portion is force fitted into the can. The internal diameter of the can can vary between a maximum diameter and a minimum diameter, the diameter of the cylindrical portion being equal to said minimum diameter. Three serrations machined on the cylindrical portion form beads, whose thickness is equal to half the difference between the maximum diameter and the minimum diameter of the can.

Abstract: An improved end plug for attachment on an end of a cladding tube of a nuclear fuel rod facilitates using a gripper tool for loading the fuel rod into a nuclear fuel assembly. The end plug includes an inner portion adapted to be inserted into the end of the tube and an outer portion adapted to extend from the end of the tube when the inner portion is inserted therein. The outer plug portion has a body part disposed adjacent the tube end and a leading part disposed remote from the tube end. The leading part of the outer plug portion has a hollow interior cavity defined therein, an exterior annular truncated surface defined on a terminal end thereof and an exterior annular tapered surface defined on a lateral side thereof. The exterior tapered surface extends between and merges with the body part and the exterior truncated surface and provides sufficient angular inclination so as to facilitate insertion of the end plug when mounted on the fuel rod tube end into the fuel assembly.

Abstract: A fuel assembly with a top nozzle having an adapter plate, at least one guide thimble connected to the adapter plate, and a burnable absorber rod disposed within the guide thimble, includes a releasable latching structure for releasably interconnecting an end of the absorber rod to the adapter plate. The latching structure includes a recess defined in the adapter plate within a passageway through the plate, a mounting body attached to the end of the absorber rod and extending axially upward therefrom through the passageway and above the adapter plate, and a spring latch disposed about the mounting body above the adapter plate. The spring latch has circumferentially spaced latch fingers extending downwardly toward the adapter plate.

Abstract: An end cap with a tag gas capsule adapted to close an end of a cladding tube of a nuclear fuel element and to introduce a tag gas into the fuel element. The end cap is fixed to the tag gas capsule to form a unitary structure. The end cap has a specific shape or description on its outer surface corresponding to information concerning the specific tag gas and the capsule, so that the description or shape of the end cap can identify the specific capsule and the tag gas contained in the capsule.

Abstract: A nuclear fuel assembly has fuel rods connected to the lower end plate of the assembly. The connecting structure comprises an attachment plate which is superimposed on the lower end plate and which is formed with openings corresponding to the rods. The openings lead out into parallel grooves machined on the lower surface of the plate. Each rod comprises a lower part having three radial branches at 120.degree., each formed with an end extension projecting radially outwardly from the outline of the rod. The extensions engaged in a groove have a height substantially equal to the depth of the groove. Axial fixing and locking against rotation of the rods are thus ensured.

Abstract: A measuring head suitable for determining the pressure of fission gases released inside non-instrumented bars of nuclear fuel (which have reached high irradiation levels), and for connection to said bars by a method which allows no escape of said active gases and does not cause appreciable disturbance either to the fuel or to the released fission gases.

Abstract: A nuclear reactor fuel rod includes a fuel tube and an improved end plug assembly having a pair of hollow end plugs which seal opposite ends of the fuel tube. Each end plug has an outer body portion with an outside diameter substantially the same as the outside diameter of the fuel tube and an inner body portion of reduced diameter inserted into an end of the tube. Each plug has a cavity defined therein which increases the space within the rod for fission gas expansion. An outer region of the cavity within the outer body portion of the end plug is undercut relative to an inner region of the cavity within the inner body portion of the plug. One of the end plugs also has an insert fitted into its inner body portion which prevents fuel chips from falling into the cavity of the end plug. A slot is formed axially in a side wall of the insert which allows communication of gas from the tube into the cavity of the end plug.

Abstract: A nuclear fuel assembly, particularly advantageous for use in a pressurized water reactor, wherein each alternate fuel rod in the assembly is positioned with its fission gas plenum zone at the top of the assembly and the intervening alternate fuel rods are positioned with their fission gas plenum zones at the bottom of the assembly. All of the fuel rods are preferably axially coextensive. An axial blanket region may be formed by providing the fuel zone of each fuel rod with a small zone of natural or depleted uranium at a part of the fuel zone furthest from the fission gas plenum zone. A method of effectively lengthening the active length of a nuclear fuel assembly is also described.

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 top nozzle of a nuclear reactor fuel assembly is removably mounted to the guide thimbles of the fuel assembly by mating and unmating of pluralities of outer and inner sockets defined in the respective top nozzle and guide thimbles. A bearing plate supported on the top nozzle and movable relative thereto between a lower, non-release position and an upper, release position supports a plurality of locking tubes which are inserted at their lower end portions into the outer sockets. When the bearing plate is at its non-release position, the lower end portions of the locking tubes are inserted into the inner sockets and prevent them from unmating from the outer sockets and thereby retain the top nozzle mounted to the guide thimbles. However, when the bearing plate is at its release position, the locking tube lower end portions are withdrawn from the inner sockets and allow them to unmate from the outer sockets and thereby allow lifting of the top nozzle off and removal from the guide thimbles.