Abstract: The nuclear reactor comprises a lower stopper sealingly fixed to a lower end of a tubular casing of the pencil that comprises a part which is internal to the casing successively comprising a first cylindrical section having a diameter which is substantially equal to the inner diameter of the tubular casing; a second cylindrical section whose diameter is smaller than the inner diameter of the tubular casing and a third cylindrical section whose inner diameter is smaller than the inner diameter of the tubular casing and greater than the diameter of the second cylindrical section such that 1-2 tenths of a millimetre radial play is created in the gas passable between the outer surface of the third section and the inner surface of the casing.

Abstract: The present invention relates to a fuel rod of a nuclear fuel assembly having a vase-like compression spring adapted to increase the internal volume thereof wherein when the vase-like compression spring is inserted into a cladding tube, it has a relatively smaller volume occupied inside the fuel rod when compared with the existing coil type compression spring, such that the vase-like compression spring can ensure a sufficient space portion receiving the fission gases generated during the operation of the fuel rod, thereby increasing the burn-up performance of the fuel rod and the mechanical integrity thereof.

Abstract: A method and device are described to form a heat producing plant with replaceable fusion-based reaction cartridges, where the fuel is embedded in casings in the preferred embodiment, and the heat can be converted into electrical or mechanical energy. The replaceable unit consists of sheets containing individual heating elements that are addressed sequentially to trigger the heat producing reactions. A controller governs the triggering activity until all the elements are used. The resulting heat can be converted into mechanical energy using turbines and into electrical energy using the Seebeck effect. This inventive device can be used in mobile environments as well as at fixed locations where heat, mechanical power or electricity are needed.

Abstract: The invention relates to a fuel assembly for pressurised water nuclear reactors comprising a plurality of nuclear fuel rods each of which comprises a plurality of pellets with nuclear fuel. The assembly includes both pellets with high-concentration gadolinium oxide (greater or equal to 6% by weight) and pellets with medium-concentration gadolinium oxide (greater than 2% by weight and less than or equal to 4% by weight). The invention also relates to a method for loading the core of a nuclear reactor.

Abstract: The present invention relates to a fuel rod for a nuclear plant and a plenum spring arranged to be provided in a fuel rod. The fuel rod (1) comprises a cladding tube (2) sealed at its ends by end plugs (3, 4), a plurality of fuel pellets (5) stacked on each other inside the cladding tube (2) such that they form a column of pellets and said plenum spring (6) arranged to hold with a spring force the column of pellets against the lower second end of the cladding tube (2) during operation. The plenum spring (6) comprises a first length variable part (8) which abuts the uppermost located fuel pellet (5) in the column of pellets with an end portion (9), a second part (10) which allows engagement of the plenum spring (6) against an inner surface of the cladding tube (2) by a radially outwardly directed pressure and a third part (11) which allows releasing of the second part (10) of the plenum spring (6) in the cladding tube (2) during operation of the nuclear plant.

Abstract: The present invention relates to a fuel rod for a nuclear plant and a plenum spring arranged to be provided in a fuel rod. The fuel rod (1) comprises a cladding tube (2) sealed at its ends by end plugs (3, 4), a plurality of fuel pellets (5) stacked on each other inside the cladding tube (2) such that they form a column of pellets and said plenum spring (6) arranged to hold with a spring force the column of pellets against the lower second end of the cladding tube (2) during operation. The plenum spring (6) comprises a first length variable part (8) which abuts the uppermost located fuel pellet (5) in the column of pellets with an end portion (9), a second part (10) which allows engagement of the plenum spring (6) against an inner surface of the cladding tube (2) by a radially outwardly directed pressure and a third part (11) which allows releasing of the second part (10) of the plenum spring (6) in the cladding tube (2) during operation of the nuclear plant.

Abstract: Method of fabricating a fuel rod, comprising providing an effective amount of a metal oxide in the fuel rod to generate steam and mitigate the tendency for secondary hydriding. Fuel rods fabricated according to the method of the invention are also provided.

Abstract: Apparatus for the determination of radiation induced growth due to burnup of a nuclear reactor fuel assembly in a reactor core.

Abstract: A new design concept of boiling water reactor fuel rod is disclosed. The new design is characterized by an upward shift in the location of the fuel pellet stack inside the fuel cladding. The resulting axial power shift upward decreases two-phase and total pressure drop and has a stabilizing effect. A device for affecting such fuel pellet displacement is a crushable tube placed under the fuel pellet stack, which also helps to mitigate fuel-clad mechanical interaction and reduces the likelihood of clad failure.

Abstract: The present invention relates to a fuel assembly with a substantially square cross section for a light-water reactor. The light-water reactor comprises a plurality of fuel rods (4) extending between a top tie plate (5) and a bottom tie plate (6). A fuel rod (4) comprises a cladding tube (7a) with a first and a second end which surround a column with fissionable material (7b). According to one aspect of the invention, at least one fuel rod (4) is provided with an axial gap (19) in the fissionable material (7b), such that fissionable material (7b) is arranged on both sides of the axial gap (19) in the fuel rod (4).

Abstract: In a fuel bundle for a boiling water nuclear reactor comprising a plurality of fuel rods (20) secured within an array and extending between upper and lower tie plates (24, 22), and including at least one additional partial length fuel rod (20') extending from said lower tie plate (22) but terminating short of said upper tie plate (24), an improvement in the form of a removable extension rod (32) secured to said at least one additional fuel rod (20') and extending substantially to said upper tie plate (24). The removable extension rod (32) also permits variance in the reactivity of the partial length fuel rod (20') particularly in the two phase region of the bundle (10).

Abstract: A fuel assembly avoiding the generation of irradiation damage, a Zr alloy used for the same, and a manufacturing method thereof. According to one embodiment, a super-saturated solid-solution Zr alloy powder having a crystal grain size in the range of 1000 nm or less and containing Fe, Ni and Cr is prepared by mechanical alloying, and the alloy powder is subjected to HIP, hot-working, cold-working and final heat-treatment.

Abstract: A core of a light-water reactor comprises a plurality of fuel assemblies each including a number of fuel rods. The fuel rod is provided with at least one area interposed between fuel areas in a clad of the fuel rod. The interposed area contains extremely reduced or substantially no fissile nuclide. At least two areas or layers with high enrichment of the fissile nuclide are formed in the axial direction of the reactor by the location of the interposed areas throughout the whole fuel assemblies arranged in the light-water reactor core.

Abstract: A fuel bundle is disclosed in which interspersed part length fuel rods define between the end of the fuel rods and the upper tie plate void regions which are not otherwise occupied. Full length fuel rods adjacent to these regions are provided with an expanded upper plenum region which effectively increases the fuel rod diameter at the end of the upper two phase region of the fuel bundle. Under normal circumstances and a fuel bundle with only full length fuel rods, such an expansion of the upper regions of the fuel rods would cause unacceptable pressure drop. Where such expansion occurs adjacent the vacated volumes created by the part length fuel rods, unacceptable pressure drop does not occur. Consequently, and with the expanded plenum volume, a longer length of active fuel pellets can be accommodated within the full length fuel rods.

Abstract: A gas cooled nuclear fuel element. A cylindrical tube having an open lower end contains nuclear fuel disks stacked one upon the other to define an annular space between the tube and disks. An upper and a lower end fitting in the tube support the stack of fuel disks. Each disk has an axial bore or channel for coolant flow. The disks may also be provided with grooves extending radially on the upper or lower face from the axial channel to the outer edge of each disk. The lower end fitting has a central bore that is coaxial with the axial channel in the disks. Coolant flows into the annular space, radially between disks, and then axially out the disks and lower end fitting.

Abstract: A nuclear fuel rod, in which a cladding tube contains fuel pellets therein and two plugs stop end openings of the cladding tube, in which a stopper member stops the fuel pellets from their moving through a spring member arranged between the stopper member and one of the plugs for biasing the stopper member onto the fuel pellets, and a getter tube is also arranged between the stopper member and the one of the plugs, and in which at least one of the spring member, the stopper member and the getter tube is made of a nonmagnetic steel.

Abstract: A fuel assembly for a nuclear reactor comprising a number of fuel rods arranged in a regular fashion in a channel box which is surrounded by water gap in a reactor core. Some of fuel rods disposed at portions facing the water gap through which no control blade is inserted or drawn out, have atomic number densities of fissionable material contained in the fuel rods. The atomic number density of each of these fuel rods is made smaller than that of the fuel rod disposed in the fuel assembly at portions other than the portions referred to above.

Abstract: A fuel rod for a nuclear reactor fuel assembly includes a metal cladding tube having two closed ends. A column of nuclear fuel pellets is disposed in the cladding tube. A compression spring has helical coils and is coaxial with the column of pellets within one of the ends of the cladding tube. A shim has two sides and is disposed between the column of pellets and the helical spring. A pair of leaf springs on one of the sides of the shim is locked to and biased against the coils of the helical spring.

Abstract: The fuel element comprises a plurality of modular capsules (5) arranged in sequence axially within a sheath (2). Each of the capsules (5) comprises a tubular case (10) closed at both ends by a porous element (13, 14) and enclosing a stack of pellets (11) in contact with the inner surface of the case (10) without radial clearance. The outside diameter of the capsules (5) is such that a very small radial clearance exists between the outer surface of the capsule (5) and the inner surface of the sheath (2).

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 porous plug is installed in the central region of a fuel rod of annular fuel pellets and prevents relocation of fuel fragments from the inner surface of each fuel pellet while providing a getter for gases produced in the fuel rod during operation of the nuclear reactor.

Abstract: A nuclear fuel rod has a sheath closed by end plugs and a stack of fuel pellets in the sheath. The stack is retained in abutment against one of the end plugs during handling of the fuel rod by a radially expandable element having a cross-sectional area in rest condition such as it frictionally engages an internal surface of said sheath. When the fuel rod is brought to the reactor operating temperature, the radially expandable element is contracted clear of frictional contact by temperature responsive means of a shape memory alloy operatively associated with said radially expandable element and having a transformation temperature above atmospheric temperature.

Abstract: An improved water displacer rod includes an elongated hollow thin-walled tube with a pair of end plugs attached to opposite ends of the tube to hermetically seal the tube and a plurality of support pellets disposed in a stacked relationship within the tube. The pellets allow the thin-walled tube to be laterally flexible while still able to resist collapse due to high external pressure. Each pellet is preferably formed of a body having a hollow annular cross-sectional shape and a pair of end webs extends across and closing opposite ends of the body. The body defines a central void and the webs seal the void. Thus, when the pellets are stacked within the tube, each void is sealed individually one from the next. A double barrier is provided in the displacer rod by the hermetically sealed tube and the individually sealed pellets.

Abstract: Fuel and fertile rod for a nuclear reactor. It comprises a can, a column of fissile and/or fertile pellets within the can and end plugs welded to the two ends of the can. The column of pellets is held in place by two tubular spacers of limited thickness and with rounded edges abutting against the two ends of the fuel column and set with a fixed dimension to the can. The column of fissile and fertile pellets can also be held in place by a supplementary positioning setting of the fertile pellet column.

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 control rod for a nuclear fuel assembly has structures formed of boron carbide mounted inside it. The boron carbide structures are provided deformable members between them which will deform at operating temperatures to accommodate the dimensional increase of the boron carbide structures and reduce the level of deformable stress on the rod cladding.

Abstract: An improved nuclear fuel rod comprising a tubular metallic cladding containing a plurality of nuclear fuel pellets has a plurality of ceramic wafers therein, each of which wafers being disposed between a major portion of adjacent fuel pellets. The ceramic wafers are formed from a sintered mixture of natural or depleted uranium dioxide and 1-8 percent by weight gadolinium oxide. The wafers are of a diameter substantially the same as that of the fuel pellets and have a thickness of between 10-100 mils. The wafers freeze out harmful fission products released by the fuel pellets and minimize or prevent pellet-clad interaction failures, while also providing flexibility in power shaping in the reactor system.

Abstract: A nuclear fuel assembly for high utilization of the nuclear fuel is disclosed. Alternate fuel rod assemblies are axially shifted relative to each other to create zones of high hydrogen-to-uranium ratios at the ends of the core for high utilization of the fuel at the core ends. Each fuel rod assembly comprises separate upper and lower fuel rods. The axial shift provides intermeshing of the separation between axially aligned fuel rods at the core center. Seed blankets are located at the ends of the core and lower enriched sections are located at the core center during beginning of core life. After a specified amount of fuel depletion from reactor operation, the upper and lower rods are interchanged and an opposite axial shift is employed. The high utilization fuel assembly provides for burnup gradient utilization, axial blanket utilization, plutonium production and burnup, axial power flattening, and less use of enriched uranium.

Abstract: A nuclear fuel cartridge comprises a sheath, and nuclear material inside the sheath. A continuous liquid permeable passageway extends from one end of the nuclear material to the other, and an annular end member is disposed at each end of the nuclear material. Inner spacing members also of annular form may be disposed in intermediate positions along the sheath between portions of the nuclear material.

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: A device for shutting down a nuclear reactor during an undercooling or overpower event, whether or not the reactor's scram system operates properly. This is accomplished by double-clad fuel safety rods positioned at various locations throughout the reactor core, wherein melting of a secondary internal cladding of the rod allows the fuel column therein to shift from the reactor core to place the reactor in a subcritical condition.

Abstract: A fuel assembly for a liquid metal fast breeder reactor having an upper axial blanket region disposed in a plurality of zones within the fuel assembly. The characterization of a zone is dependent on the height of the axial blanket region with respect to the active fuel region. The net effect of having a plurality of zones is to establish a dispersal flow path for the molten materials resulting during a core meltdown accident. Upward flowing molten material can escape from the core region and/or fuel assembly without solidifying on the surface of fuel rods due to the heat sink represented by blanket region pellets.

Abstract: The production of a novel nuclear fuel utilizing clean uranium 233 in combination with other nuclear materials is made possible by utilization of an equally novel reactor configuration and method of operation. Clean uranium 233 is produced from thorium in a light water reactor while utilizing discrete separation of the thorium being irradiated from the fissile fuel. This clean uranium 233 is then incorporated directly as fissile isotope enrichment into a new nuclear fuel which may be done without encountering the usual difficulties and hazards in the handling of uranium 233 or the expense and delays associated with gaseous diffusion enrichment. The thorium from this process may be directly reprocessed for reactor charging without radiation hazard also.