Abstract: A fuel pellet for a nuclear reactor contains a matrix made of an oxidic nuclear fuel and a metallic phase that is deposited within or between the fuel grains and is preferably aligned in a radial direction relative to the coating surface of the pellet. A method for producing the fuel pellet includes forming slugs containing a precursor of the metallic phase, which has a melting point lying below the sintering temperature and can be transformed into the metallic phase in sintering conditions, in addition to the oxidic nuclear fuel and other optional additives. The slugs are then sintered. The slugs are heated up so quickly that at least one portion of the precursor is liquefied before being completely transformed into the metallic phase.

Abstract: A fuel pellet for a nuclear reactor contains a matrix made of an oxidic nuclear fuel and a metallic phase that is deposited within or between the fuel grains and is preferably aligned in a radial direction relative to the coating surface of the pellet. A method for producing the fuel pellet includes forming slugs containing a precursor of the metallic phase, which has a melting point lying below the sintering temperature and can be transformed into the metallic phase in sintering conditions, in addition to the oxidic nuclear fuel and other optional additives. The slugs are then sintered. The slugs are heated up so quickly that at least one portion of the precursor is liquefied before being completely transformed into the metallic phase.

Abstract: A nuclear fuel sintered body is produced from a powder which contains at least one fissile heavy metal oxide. During the further treatment of the powder over the course of the process preceding the sintering operation, a dopant that contains at least 100 ppm of an iron oxide compound is added to the powder. The powder is a UO2-containing powder obtained from a dry-chemical conversion process, and if appropriate, a powder which contains further fissile heavy metal oxide (U3O8, PuO2, inter alia). As a result, the sintered body is provided with high plasticity combined, at the same time, with a large grain size. This advantageously reduces an interaction between the nuclear fuel sintered body and a fuel rod cladding tube during an operation of the reactor.

Abstract: A furnace is provided for microwave sintering of nuclear fuel. A stationary wave is generated in an antenna cavity and used to extract microwaves through slots into a resonance chamber containing the nuclear fuel. A position of the slots is adjusted in such a way that a predetermined temperature profile is produced in the nuclear fuel.

Abstract: A furnace is provided for microwave sintering of nuclear fuel. A stationary wave is generated in an antenna cavity and used to extract microwaves through slots into a resonance chamber containing the nuclear fuel. A position of the slots is adjusted in such a way that a predetermined temperature profile is produced in the nuclear fuel.

Abstract: A nuclear fuel sintered body is produced from a powder which contains at least one fissile heavy metal oxide. During the further treatment of the powder over the course of the process preceding the sintering operation, a dopant that contains at least 100 ppm of an iron oxide compound is added to the powder. The powder is a UO2-containing powder obtained from a dry-chemical conversion process, and if appropriate, a powder which contains further fissile heavy metal oxide (U3O8, PuO2, inter alia). As a result, the sintered body is provided with high plasticity combined, at the same time, with a large grain size. This advantageously reduces an interaction between the nuclear fuel sintered body and a fuel rod cladding tube during an operation of the reactor.

Abstract: A method and a furnace are provided for microwave sintering of nuclear fuel. A stationary wave is generated in an antenna cavity and used to extract microwaves through slots into a resonance chamber containing the nuclear fuel. A position of the slots is adjusted in such a way that a predetermined temperature profile is produced in the nuclear fuel.

Abstract: A process and device for triggering an actuator are described, in particular an actuator triggered in cycles for an internal combustion engine. The triggering signal frequency can be changed to prevent resonance effects. The triggering signal frequency is varied between a first and a second limit value over time according to a preselected function.

Abstract: Method for manufacturing sintered oxidic nuclear fuel bodies by molding uranium oxide starting powder, a mixture of uranium oxide and plutonium oxide starting powder or of uranium-plutonium oxide mixed-crystal starting powder to form blanks and by a heat treatment of these blanks with a U.sub.4 O.sub.9 or (U, Pu).sub.4 O.sub.9 crystal phase developed in them to a degree which can be crystallographically detected at a sintering temperature in the range of 1000.degree. to 1400.degree. C. in an oxidizing and subsequently in a reducing gas atmosphere. The starting powder and/or the blanks are preroasted at a roasting temperature below the sintering temperature in a roasting gas atmosphere with oxidizing action and with an oxygen potential in which the U.sub.4 O.sub.9 (U, Pu).sub.4 O.sub.9 crystal phase is developed and cooled down subsequently to a starting temperature below the roasting temperature in an inert or oxidizing cooling-down gas atmosphere.

Abstract: Method for sintering blanks into fuel pellets, in which the blanks are moved through the muffle of a tunnel furnace by pushing the blanks through the muffle on a guiding device which goes through the muffle and protrudes therefrom at least on the input side, in the form of a single-layer column of abutting blanks.

Abstract: A sintered nuclear fuel compact of UO.sub.2 or the mixed oxides (U, Pu)O.sub.2 and (U, Th)O.sub.2, with which reactivity losses in a nuclear reactor having relatively long fuel element cycles are avoided, has in its sintered matrix neutron poison in the chemical compound form UB.sub.x with x=2; 4 and/or 12 and/or B.sub.4 C. A sintered nuclear fuel compact of this kind is produced by sintering from a compact comprising a mixture of at least one of the mixture components UO.sub.2, PuO.sub.2, (U, Pu)O.sub.2 and (U, Th)O.sub.2 powder with UB.sub.x powder, where x=2; 4 and/or 12 and/or B.sub.4 C powder.

Abstract: UO.sub.2 base powder exhibiting any specific surface and crystallite diameter properties is mixed with rare earth (SE) oxide-containing powder, the particles of which exhibit at least in one surface layer, a crystal lattice of the fluorite type, with the stoichiometric composition (SE.sub.0.5, U.sub.0.5) 0.sub.2.00 and/or form it in sintering; and is compacted to form compacts which are sintered in a gas atmosphere with reducing action at 1500.degree. C. to 1750.degree. C. to form high-density sintered bodies.

Abstract: Method for determining the contents of a fuel rod within a testing range extending in the longitudinal direction of the fuel rod, characterized by the features that(a) the position of a test coil concentrically surrounding the fuel rod is changed from the beginning to the end of the testing range, and(b) in the process, the impedance of the test coil is measured as a function of its position,(c) the test coil is fed with an a-c voltage,(d) the frequency of which is so low that the measurement value in the region of a fuel pellet of pure uranium dioxide is clearly distinguished from that which is measured in the region of a doped fuel pellet.

Abstract: Method for sintering blanks into fuel pellets, in which the blanks are moved through the muffle of a tunnel furnace by pushing the blanks through the muffle on a guiding device which goes through the muffle and protrudes therefrom at least on the input side, in the form of a single-layer column of abutting blanks.

Abstract: Method for the manufacture of oxidic nuclear fuel bodies by a heat treatment of blanks obtained from UO.sub.2 starting power or a mixture of UO.sub.2 and PuO.sub.2 starting powder at a treatment temperature in the range of 1000.degree. C. to 1400.degree. initially in a gas atmosphere with oxidizing action and subsequently in a gas atmosphere with reducing action. The oxygen potential of the gas atmosphere with oxidizing action is kept in a range in which a crystallographically demonstrable U.sub.4 O.sub.9 or (U, Pu).sub.4 O.sub.9 crystal phase is generated in the blanks during the heating to the treatment temperature in this gas atmosphere with oxidizing action.

Abstract: Method for the manufacture of oxidic sintered nuclear fuel bodies by compacting UO.sub.2 -starting powder or a mixture of UO.sub.2 -and PuO.sub.2 starting powder which contains up to 10% by weight rare-earth oxide, especially Gd.sub.2 O.sub.3, as an additive into blanks and subsequent densification of these blanks by a heat treatment in a sintering atomsphere with reducing action. The UO.sub.2 -starting powder used for compacting has a specific surface in the range of 2 to 4.5 m.sup.2 /g and/or a mean crystallite diameter in the range of 80 nm to 250 nm, and the heat treatment in the sintering atmosphere with reducing action is carried out at a temperature in the range of 1,500.degree. C. to 1,750.degree. C.

Abstract: Manufacture of very dense oxidic fuel bodies of UO.sub.2 with rare earth oxides in which pressed blanks are subjected to sintering in an oxidizing atmosphere at relatively low temperature and are sintered in a reducing atmosphere at a higher temperature. This avoids sintering-inhibiting phases and permits very dense bodies with greater content of rare earth oxides to be produced.

Abstract: Manufacture of oxidic nuclear fuel bodies with oxygen-to-metal ratio of 2.0.+-.0.02 at relatively low sintering temperature in range of 1000.degree.-1400.degree. C. Nuclear fuel powder with an arbitrary oxygen-to-metal ratio is mixed with a grain-growth promoting additive (U.sub.3 O.sub.8) and pressed into blanks. The blanks are subjected to a two-stage operation in a furnace at 1000.degree.-1400.degree. C. - an oxidative-sintering stage in a carbon dioxide atmosphere and a reducing stage in a hydrogen containing atmosphere.

Abstract: The continuous casting of steel is supervised and controlled by measuring total heat flow and the ratio of upper to lower heat flow into the mold and causing these two valves directly or indirectly to be represented in a two dimensional field. The resulting operating point must remain within an empirically predetermined range for safe operation without skin rupture.