Abstract: A bullet includes a frontward facing aperture. Contained within the aperture is a relatively hard bullet frontal element that provides advantageous bullet impact performance. In one embodiment, the frontal element is a steel sphere that provides advantageous penetration and weight retention when the bullet impacts laminated glass, such as an automobile windshield.

Abstract: Heat conductive fins are welded along both sides of a belt-like member with a margin left along edges of the both sides, thereby to form a unit. The unit is welded to a body with the heat conductive fins from the outside of each fin. Next, another belt-like member is covered over a gap between adjacent belt-like members, and these members are welded from the outside. With this arrangement, there is no need to weld in a narrow and long space and the entire welding step is carried out from the outside, which makes it easier to assemble a cask.

Abstract: A canister is provided for storing, transporting, and/or disposing of spent nuclear fuel. The canister includes a canister shell, a top shield plug disposed within the canister, and a leak-tight closure arrangement. The closure arrangement includes a shear ring which forms a containment boundary of the canister, and which is welded to the canister shell and top shield plug. An outer seal plate, forming an outer seal, is disposed above the shear ring and is welded to the shield plug and the canister.

Abstract: A fragmenting projectile includes a multi-wall projectile casing with each wall thereof formed by a sleeve. Each pair of adjacent sleeves is defined by inner and outer sleeves that mate in a threaded engagement. Explosive material is disposed in an innermost sleeve.

Abstract: The invention concerns a spacer and a fuel assembly for a nuclear reactor. The spacer has a plurality of cells (10) for holding elongated elements. The cells (10) are defined by a plurality of side portions (12). At least one of said cells (10) has at least one side portion (12) from which a flow-influencing member (20) is formed in that it is folded out from the side portion (12). The side portion (12) from which the flow-influencing member (20) is folded out comprises a first (22) and a second (24) edge surface which are connected to each other and which correspond to the directions of a first (26) and a second (28) edge of said flow-influencing member (20) in a non folded out state of the flow-influencing member (20). The first edge surface (22) has an extension in at least a first direction (14) in which a cooling medium is intended to flow. The second edge surface (24) has an extension in a direction which is perpendicular to said first direction (14).

Abstract: An automatically scramming nuclear reactor system. One embodiment comprises a core having a coolant inlet end and a coolant outlet end. A cooling system operatively associated with the core provides coolant to the coolant inlet end and removes heated coolant from the coolant outlet end, thus maintaining a pressure differential therebetween during a normal operating condition of the nuclear reactor system. A guide tube is positioned within the core with a first end of the guide tube in fluid communication with the coolant inlet end of the core, and a second end of the guide tube in fluid communication with the coolant outlet end of the core. A control element is positioned within the guide tube and is movable therein between upper and lower positions, and automatically falls under the action of gravity to the lower position when the pressure differential drops below a safe pressure differential.

Abstract: A system and method for moving a canister of spent nuclear fuel from a first location, which may be within a nuclear power generation facility to a second location such as a storage cask that is used for short-term or long-term storage of spent nuclear fuel includes a first lifting mechanism for engaging a transfer cask and a second lifting mechanism for engaging and lifting the canister of spent nuclear fuel. Preferably, the method is practiced by first positioning a canister of spent nuclear fuel within the transfer cask and then engaging the transfer cask with the first lifting mechanism. The canister is engaged with the second lifting mechanism. The transfer cask having the canister positioned within is moved to the vicinity of a storage cask, and the canister is lowered from the transfer cask into the storage cask by the second lifting mechanism without disengagement of the first lifting mechanism from the transfer cask.

Abstract: A bullet that has a controlled fragmentation on impact with a target. The bullet includes a generally cylindrical body having a nose, a mid-portion and a heel. The body includes an aperture that starts at the nose, extends past the mid-portion of the bullet and ends near the heel of the bullet. The aperture also includes ay least one scored area along the sides of the aperture and extending along at least some or all of the aperture. The heel portion includes a scored area that terminates at a location that aligns with the scored area along the sides of the aperture in the bullet.

Abstract: A full-caliber projectile having a cylindrical guide region (5) and an ogival projectile tip (7). To improve the stabilization of the projectile (1) inside a gun barrel (2) in a simple manner, and therefore improve the intermediate ballistics and hit accuracy over those of comparable projectiles, a guide ring (8), which is segmented in the circumferential direction, and whose outer diameter is smaller than the inner diameter of a gun barrel (2) of the same caliber, is secured to the projectile tip (7) such that the radially spaced guide-ring segments (9) detach from the projectile (1) in the gun barrel (2) when a predetermined firing acceleration occurs in the gun barrel, and the segments (9) are pushed toward the projectile (1), axially relative to the cylindrical guide region (5), by dynamic pressure until they rest against the inside wall (18) of the gun barrel (2) and against the projectile (1).

Abstract: Separation devices are disposed in the vent volume above part-length rods and above one or more of the spacers above the upper ends of the part-length rods. The separation devices preferably comprise swirlers located above the lattice openings which would otherwise receive the rods but for the underlying part-length rods. In this manner, flow is directed laterally outwardly onto the surfaces and into the interstices of the full-length fuel rods for improved power performance while simultaneously adverse pressure drops across the spacers are minimized.

Abstract: An unirradiated nuclear fuel assembly component transport system that includes a clamshell-type inner liner that opens along its axial dimension to load and unload the fuel component being transported. The exterior dimensions of the liner conform to a generic overpack tubular container. The overpack is separable into an upper and lower section with the lower section having a V-shaped channel extending along its longitudinal axis. The liner is supported in the V-shaped channel by at least one row of shock mounts on either side of the channel. The lower section of the overpack is secured from rotation and the top section is latchably engaged to the lower section of the overpack.

Abstract: A side-slotted nozzle type double sheet spacer grid for nuclear fuel assemblies is disclosed. The spacer grid includes intersecting inner strips and four perimeter strips. Each inner strip has unit strip parts, each fabricated by integrating two unit sheet parts together into a single structure, such that the two unit sheet parts face each other and a nozzle type coolant channel is defined between the two unit sheet parts. Each perimeter strip is fabricated by integrating an inner thin sheet having the unit sheet parts with a flat outer thin sheet having a width corresponding to the width of the inner thin sheet into a single structure. The coolant channel has one or more outlets formed by cutting an upper portion of one of the two unit sheet parts of each unit strip part. Each unit sheet part has a slot longitudinally formed on each side surface of a spring that is projected from the unit sheet part to support a fuel rod within a four-walled cell.

Abstract: A high energy absorption top nozzle for a nuclear fuel assembly that employs an elongated upper tubular housing and an elongated lower tubular housing slidable within the upper tubular housing. The upper and lower housings are biased away from each other by a plurality of longitudinally extending springs that are restrained by a longitudinally moveable piston whose upward travel is limited within the upper housing. The energy imparted to the nozzle by a control rod scram is mostly absorbed by the springs and the hydraulic affect of the piston within the nozzle.

Abstract: The invention relates to a method of measuring the tritium activity of a drum (1) of radioactive waste containing a quantity of radioactive waste (2) and a free volume, the method consisting of measuring the quantity of 3He produced by the decay of the tritium contained in said radioactive waste during a defined period of time and deducing from it the corresponding activity of the tritium contained in said radioactive waste (2).

Abstract: A method for mitigating stress corrosion cracking in high temperature water includes introducing catalytic nanoparticles and dielectric nanoparticles to the high temperature water in an amount effective to reduce a electrochemical corrosion potential of the high temperature water.

Abstract: A device and method for removing radioactive crud material deposited on surfaces of a nuclear fuel assembly in a nuclear plant is provided. The device comprises a container arranged to accommodate the nuclear fuel assembly, a first pumping means to pump a fluid, composed of water and ice, through the container in order to release the deposit from the nuclear fuel assembly by abrasion and to transport the released radioactive material out from the container. The first pump means also enables the feeding of a gas or steam or both to the fluid that is fed into and through the container in order to create a turbulence in the fluid. The device further comprises means, arranged in a &ggr;-radiation-dampening medium, disposed to receive the radioactive deposit transported out of the container by the fluid.

Abstract: A metallic uranium article having a protective coating of a copper-tin alloy containing from 45 to 50% by weight of copper and from 55 to 50% by weight of tin, said alloy being firmly bonded to the metallic uranium.

Abstract: A segmented lattice rack to store fuels coming from nuclear reactors, whose walls are made of plates joined orthogonally forming a mesh defining multiple cell cavities which are longitudinally coupled forming a sandwich comprising a central part coinciding with the active part of the stored element, being from a material obtained from neutronic poisons, preferably boron treated steel; whilst the end areas coinciding with the non-active part of the stored radioactive element are of normal stainless steel, joined to each other and with the adjacent components by means of welding or pretensioning.

Abstract: A method of inspecting an operation of sealed closure by welding an end opening of a filling channel axially traversing an upper plug for closing the cladding of a fuel rod for a nuclear reactor, the cladding of the rod containing a plurality of pellets of nuclear fuel stacked in the axial direction of the cladding and two closure plugs, one of the plugs or the upper plug being traversed axially by the channel for filling the cladding of the rod with an inert gas and the sealed closure by welding of the filling channel of the upper plug being carried out after filling the cladding with inert gas, in a filling apparatus, by melting central part of the end of the upper plug adjacent to the opening of the filling channel, this method allowing for inspection of the conditions for implementing and carrying out the sealed closure of the upper plug by welding, efficiently and without extending the time needed for the manufacture of the fuel rod.

Abstract: Nuclear fuels are taken from a nuclear reactor pressure vessel, a rail for running is mounted under the reactor pressure vessel drain piping in parallel with a horizontal portion of the reactor pressure vessel drain piping inside a pedestal positioned on the lower side of the reactor pressure vessel, an inspection apparatus is mounted on the-rail, and the inspection apparatus is moved along the rail to inspect the reactor pressure vessel drain piping, whereby the reactor pressure vessel drain piping can be surely inspected while reducing radiation exposure to an inspector.