Abstract: A fault current limiter, with a superconducting device (1; 21; 31; 41; 51; 61; 71; 72) comprising a sequence of superconducting elements (2a-2f), each with—a substrate (3a-3d), —a superconducting film (5a-5d), and —an intermediate layer (4a-4c) provided between the substrate and the superconducting film, wherein the superconducting films (5a-5d) of adjacent superconducting elements (2a-2f) of the sequence are electrically connected, in particular in series, is characterized in that the substrates (3a-3d) of the superconducting elements (2a-2d) are electrically conducting substrates (3a-3d), wherein the electrically conducting substrate (3a-3d) of each superconducting element (2a-2f) of the sequence is electrically insulated from each electrically conducting substrate (3a-3d) of those adjacent superconducting elements (2a-2f) within the sequence whose superconducting films (5a-5d) are electrically connected in series with the superconducting film (5a-5d) of said superconducting element (2a-2f), and that the in

Abstract: A device for assisting in the underwater extraction or insertion of an elongate element disposed in a pipe is provided. The device includes a clamping and vibration-generating assembly including a sealed housing bearing a gripper and including a member for tightening the gripper on the pipe, an adjustable vibrator for vibrating the housing and the gripper, and a member for measuring the vibration produced by the vibrator on the pipe in order to determine the optimum vibration The device also includes a controller for remotely controlling the gripper and the vibrator. A method for assisting in the extraction or insertion of an elongate element is also provided.

Abstract: The method for detecting at least one structural defect in a spherical particle (33) comprises at least the following steps of passing the particle (33) into at least one induction coil (15); exciting the induction coil (15) in order to induce Foucault currents in the particle (33); acquiring an output signal at the terminals of the induction coil (15); and analyzing the signal in order to establish whether or not the particle (33) comprises a structural defect. A plurality of output signals are acquired by passing the particle (33) successively into one or more induction coils (15) with different positions of the particle (33), the or each induction coil (15) being excited at least each time the particle (33) passes in order to induce Foucault currents in the particle (33).

Abstract: A fault current limiter and a method for the production thereof has a superconducting device (1; 21; 31; 41; 51; 61; 71; 72) comprising a sequence of superconducting elements (2a-2f), each with an electrically conducting substrate (3a-3d), a superconducting film (5a-5d) and an electrically insulating intermediate layer (4a-4c) provided between the substrate and the superconducting film. The superconducting films (5a-5d) of adjacent superconducting elements (2a-2f) of the sequence are electrically connected, in particular in series, wherein the electrically conducting substrate (3a-3d) of each superconducting element (2a-2f) of the sequence is electrically insulated from each electrically conducting substrate (3a-3d) of those adjacent superconducting elements (2a-2f) within the sequence whose superconducting films (5a-5d) are electrically connected in series with the superconducting film (5a-5d) of said superconducting element (2a-2f).

Abstract: The flexible glove holder (1) includes a flat structure (13) with three branches (2, 3 and 4) forming an S-shape on which the glove is wound. The holder (1) is then pushed into the opening of the glove box. This rapid action method makes it possible to avoid knotting the gloves when they must be drawn toward the outside for an operation within the box and also allows the implementation of biological protection on the opening of the glove box as well as a protection of the agents against radiation.

Abstract: In a method for detecting a leak in a double pipe, a medium located in an intermediate chamber between the interior and exterior pipe is moved toward a first end of the pipe, whereupon the medium flows in from the second end. On the first end the medium is examined for any leakage of a characteristic material, upon the detection of which a leakage signal is generated and a location of the leakage is calculated based on the transport time of the characteristic material from the leakage to the first end and on the mass flow of the medium. A corresponding device contains a conveyor unit for moving the medium through the intermediate chamber. A material sensor is disposed at the first end for examining the medium for the characteristic material. A control and analysis unit is provided for generating a leakage signal and calculating the location of the leakage.

Abstract: A relief valve for discharging a dielectric gas between two volumes (V1, V2) of a high-voltage or medium-voltage interrupting chamber. There is used as a closure member a flexible metal blade secured to the body, the closure member therefore being opened by deformation of the flexible blade from a closed position (FIG. 1) in which it is pressed against a closure member seat formed in the body to a fully open position in which it fits closely against a stop member secured to the valve body while remaining within its elastic limit, the open passage for the gas being open in this fully open position (FIG. 1A) and the return of the blade from its fully open position to its closed position being possible because of its flexibility.

Abstract: A method is provided for operating a nuclear reactor. The method includes operating the nuclear reactor for at least one plutonium equilibrium cycle during which the core contains plutonium-equilibrium nuclear fuel assemblies; subsequently, operating the reactor for transition cycles, at least some of the plutonium-equilibrium nuclear fuel assemblies being progressively replaced with transition nuclear fuel assemblies and then with uranium-equilibrium nuclear fuel assemblies; and then operating the nuclear reactor for at least one uranium equilibrium cycle.

Abstract: In an electrical connection for high-voltage or medium-voltage switchgear, a bar (2) is inserted in a recess (6) provided with a projection (10). In the invention, the dimensions are established so that the axes (AA, BB) of the bar (2) and of the projection (10) can be inclined relative to each other. Spring-forming conductor elements (12, 14) establish the electrical connection even in the event of tilt. A high-performance electrical contact can thus be obtained compactly, which makes it possible to perform assembly/disassembly operations on electrical equipment without any additional element of the telescopic ferrule or separable bar type.

Abstract: This interrupter device includes a parallel branch (4) in which a vacuum switch chamber is connected for breaking current. The branch is inactive in normal operation, with current flowing in it only when the disconnector (2) has started its opening movement, by progressive transfer of the current from the main power line (1) to the branch (4). Since the vacuum switch (6) is generally at rest, it no longer needs to be dimensioned to satisfy stringent electrical and dielectric requirements for normal operation.

Abstract: A method and an apparatus for test an annular weld at a main coolant line connected to a reactor pressure vessel in a nuclear power plant, include a self-propelled submersible vehicle which is introduced into an opened, flooded reactor pressure vessel. The submersible vehicle has at least one test device to be placed against an inner circumferential surface of the main coolant line and moved in circumferential direction of the main coolant line. The submersible vehicle is advanced into the main coolant line, which is also flooded, and is fixed in the region of the weld by radially deployable spreading or extension arms. The test device is then placed against the weld and is moved therealong in the circumferential direction.

Abstract: The invention relates to a process for producing 228Th from a natural thorium salt, which comprises in succession: a) the separation of the radium from the other radioelements present in this salt, by at least one coprecipitation of the radium by barium sulphate, this coprecipitation comprising: i) the addition of sulphuric acid and a barium salt to an aqueous solution of said natural thorium salt in order to form a barium-radium sulphate coprecipitate and ii) the separation of the coprecipitate from the medium in which it has formed; b) the extraction of the thorium 228 coming from the decay of radium 228 from the coprecipitate thus separated; and, optionally c) the purification and concentration of the 228Th thus extracted. Applications: manufacture of radiopharmaceutical products useful in nuclear medicine, in particular in radioimmunotherapy for the treatment of cancers and AIDS.

Abstract: A collector is provided including at least one photovoltaic cell for converting solar energy into electric energy, and at least one heat sink for converting solar energy into heat energy by heating a fluid, arranged so as to receive solar energy through the photovoltaic cell. The photovoltaic cell includes a plurality of vertically adjacent semiconductor junctions having different forbidden energy bands, each semiconductor junction having a forbidden energy band of greater than or equal to 1.2 eV, in particular greater than or equal to 1.4 eV.

Abstract: A method produces a welded connection between first and second components each having inner and outer sides interconnected by an end face. The first component has a ferritic basic body carrying a plating at the inside and having an end face with a buffer layer of Ni-based alloy. The second component is of austenitic material. The end faces of the components enclose a weld groove. An austenitic root, connecting the plating to the end face of the second component, is welded in the weld groove. An intermediate layer of a nickel alloy having at least 90% nickel is welded onto the root. The intermediate layer is connected to the end faces of the plating and the second component. A weld seam is then produced in the remaining weld groove using a nickel-based welding additive. A method for repairing a welded connection between first and second components is also provided.

Abstract: A nuclear installation has a reactor containment which is connected to a pressure relief line. A Venturi scrubber, which is arranged in a vessel containing a washing liquid, and a throttle device are connected in series in the pressure relief line. The novel system restrains, with particularly high reliability, fine air-transported activities or aerosols during decompression such that release thereof into the environment is practically impossible. The Venturi scrubber and the throttle device are dimensioned in such a way that, in the case of a critical drop in pressure of an air-vapor mixture flowing in the decompression line, a flow speed of said air-vapor mixture of more than 150 m/s, preferably more than 200 m/s, can be adjusted with respect to the throttle device in the Venturi scrubber.

Abstract: A method for producing synthetic hydrocarbons from at least one carbonaceous material is provided. The method includes evaluating the resources of the carbonaceous material available on a determined territory; determining from the resources a total production capacity of synthetic hydrocarbons; determining from the total production capacity, a number of elementary production units required for obtaining the total production capacity, each elementary production unit having an elementary production capacity between a 100 and a 1,000 barrels a day of synthetic hydrocarbons; building the number of elementary production units on the territory; transporting the carbonaceous material from the territory as far as the elementary production units; producing the synthetic hydrocarbons in the elementary production units from the transported carbonaceous material.

Abstract: A method is provided for operating a nuclear reactor. The method includes operating the nuclear reactor for an initial cycle during which a core contains initial nuclear fuel assemblies; then operating the nuclear reactor for transition cycles, at least some of the initial nuclear fuel assemblies being progressively replaced, during the replacement steps preceding the transition cycles, with transition nuclear fuel assemblies or with plutonium-equilibrium nuclear fuel assemblies; and then operating the nuclear reactor for at least one plutonium equilibrium cycle during which the core contains only plutonium-equilibrium nuclear fuel assemblies.

Abstract: A method using diglycolamide for increasing the separation factor between americium and curium and/or between lanthanides during an extraction operation. The operation comprising putting an acid aqueous phase, in which are found the americium, curium and/or lanthanides, in contact with an organic phase non-miscible with water, containing at least one extractant in an organic diluent. The aqueous and organic phases are then separated, and the diglycolamide is added to the aqueous phase.

Abstract: The object of this invention is to provide a device and method for the dry intermediate storage of irradiated fuel elements. The apparatus includes a casing which includes tiered superposed modules made of thermally conductive material and having compartments for accommodating fuel elements with a heat sink arranged on a perforated support plate. The system includes a retaining system which includes a clearance space left between a top module of a tier and a support plate of a tier above the superposed module.

Abstract: A method with which americium may be selectively recovered from a nitric aqueous phase containing americium, curium and fission products including lanthanides and yttrium, but which is free of uranium, plutonium and neptunium or which only contains these three last elements in trace amounts. The method is applicable for treatment and recycling of irradiated nuclear fuels, in particular for removing americium from raffinates stemming from methods for extracting and purifying uranium and plutonium such as the PUREX and COEX™ methods.