摘要:
An improved nuclear fuel element is disclosed for use in the core of nuclear reactors. The improved nuclear fuel element has a composite cladding of an outer portion forming a substrate having on the inside surface a metal layer selected from the group consisting of copper, nickel, iron and alloys of the foregoing with a gap between the composite cladding and the core of nuclear fuel. The nuclear fuel element comprises a container of the elongated composite cladding, a central core of a body of nuclear fuel material disposed in and partially filling the container and forming an internal cavity in the container, an enclosure integrally secured and sealed at each end of said container and a nuclear fuel material retaining means positioned in the cavity. The metal layer of the composite cladding prevents perforations or failures in the cladding substrate from stress corrosion cracking or from fuel pellet-cladding interaction or both. The substrate of the composite cladding is selected from conventional cladding materials and preferably is a zirconium alloy.
摘要:
A cladding tube is provided having an axis and a cross-section perpendicular to the axis. The cross-section includes (1) an outer circumferential substrate having an inner surface, (2) a zirconium barrier layer bonded to the inner surface of the outer circumferential substrate, and (3) an inner circumferential liner bonded to the inner surface of the zirconium barrier layer. The inner circumferential liner includes a plurality of facets aligned substantially in parallel with the cladding tube axis. The facets--which define the geometry of the cladding interior--facilitate mixing among the gases in the cladding interior. Also provided is a fuel element including (1) a cladding tube having an faceted inner liner as described above, (2) nuclear fuel material disposed within said cladding tube in a fuel region, and (3) a plenum or plenums located in one or both end regions (beyond the nuclear fuel region) within the cladding tube. In the event of steam entering the cladding interior, the plenum(s) serves as a reservoir making steam available to dilute locally high hydrogen/steam regions. At least a portion of the nuclear fuel is a uranium dioxide having an oxygen to uranium mole ratio in excess of 2.
摘要:
A particulate mixture of uranium dioxide and additive of magnesium silicate composition is formed into a compact and sintered to produce a nuclear fuel wherein the uranium dioxide grains have an average grain size of at least about 20 microns and wherein substantially all of the grains are each enveloped with glassy magnesium silicate phase.
摘要:
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.
摘要:
A fluorescent light fitting (1) comprises an elongate metal casing (2) of hollow cross-section with spaced-apart fluorescent tube holders (6) projecting from at least one wall (5) of the casing (2) and with another wall (4) of the casing provided with a removable or releasable baseplate (14) on which internal electrical components (13) are mounted, with means (18, 19, 20) to fasten the baseplate (14) to the fitting (1).
摘要:
There is provided an assembly for preferentially separating and collecting particles that are gathered from the surface of an article such as an item of baggage. The assembly features an impactor and a suction anvil that is displaceable from a collection medium. The anvil is displaceable from the collection medium so that the medium may be removed and analyzed for traces of substances such as explosives or narcotics. There is also provided, in combination with the assembly, a vacuum head and conduit for gathering the particles and a suction unit for creating the suction force. The collection medium containing collected particles is moved from the impactor to an analyzer by a stage movement device. The analyzer includes an analysis unit, such as an Ion Mobility Spectrometer, and a displaceable heater anvil.
摘要:
An improved nuclear fuel element for service in power generating, water cooled nuclear reactors, comprising a fuel cladding container of an alloy of zirconium provided with a barrier lining of unalloyed zirconium metal metallurgically bonded to the container's inner surface, and enclosed therein fissionable nuclear fuel including an additive of aluminum silicate.
摘要:
Cladding for nuclear fuel elements which is formed with a zirconium metal barrier layer bonded to the inside surface of a zirconium alloy tube and which is sized by a cold working tube reduction process and is heat treated after final reduction at a temperature and for a time period which allows substantially complete recrystallization of the zirconium metal barrier layer and provides a fine-grained microstructure therein and which stress-relieves but does not fully recrystallize the zirconium alloy tube. The crystallographic structure of the zirconium metal barrier layer may be improved by compressive deformation such as shot-peening.
摘要:
The device comprises a track made up of two spaced rails adapted to extend across a bath. The spacing of the rails is fixed. There are stops on the underside of the track to contact the upper, inner sides of the bath to hold the track in place in the bath. A seat has wheels to engage the rails to enable the seat to reciprocate across the bath. There is a brake operable to hold the seat in a predetermined position on the track. The device is easily assembled and dismantled, easily used and simple in structure.
摘要:
2-Iminothiazoline derivatives of the formula: ##STR1## and the corresponding 4,5-dihydro counterparts, wherein the respective meanings of the symbols are set forth in the specification, useful as insecticides and acaricides.