Abstract: Guide and retaining assembly for a press compensator comprising: a guide bushing (32) for the compensator (20) in its bore, said guide bushing being designed to be fitted around the compensator, a retaining nut (38) that that is configured to be screwed into the bore, the guide bushing (32) being located between a shoulder on the compensator and the retaining nut (38), and means (44) axially fixing the guide bushing (32) and the retaining nut (38) while maintaining an axial and transverse clearance between the guide bushing (32) and the retaining nut (38), said means (44) being such that the guide bushing (32) is free to rotate relative to the retaining nut (38).

Abstract: A sampling system for taking a sample from the atmosphere in a reactor containment of a nuclear plant, includes a sampling line which is connected to a vacuum system and to an analysis system. The sampling line opens into the reactor containment and has a restriction device connected upstream thereof on the gas side for connection to the atmosphere in the reactor containment. A method for taking such a sample is also provided.

Abstract: The invention relates to a method and an arrangement for avoiding stray currents in a wind power plant. There is an insulating power source having a galvanic decoupled secondary side, an electrical load coupled to the secondary side of the insulating power source through an electrical conductor and a stray current sensitive mechanical component of the wind power plant. The insulating power source is located at a first side of the stray current sensitive mechanical component and the load is located at a second side of the stray sensitive mechanical component. The electrical conductor is coupled to a common ground potential at the second side.

Abstract: A process of incorporating technetium into an electroless deposit, forming an alloy that is extremely resistant to corrosion and reduces the mobility of technetium on a geologic time scale is disclosed and claimed. The process includes providing a liquid containing technetium, such as an aqueous waste stream generated during the used nuclear fuel reprocessing activities. The technetium is collected and concentrated, and provided into an electroless deposition bath. A substrate, such as suitably prepared zero valent iron or stainless steel, is introduced into the bath to initiate autocatalytic electroless deposition of the technetium onto the substrate due to the difference in electrochemical potential between the plating bath and the metals in solution. This causes a layer of technetium metal to form on the substrate.

Abstract: A sensor line for monitoring for and locating leaks in an installation, in which chlorine escapes to the area surrounding the installation if there is a leak. The sensor line contains a carrier pipe. The wall of the carrier pipe has openings which are closed by at least one layer which is permeable for chlorine and contains a halogen-containing siloxane rubber.

Abstract: A nuclear power station component is provided. The nuclear power station includes a metal structure having an external surface; at least one marking placed on the external surface and encoding information related to the component. The marking includes a plurality of luminescent nanoparticles, each provided to emit optical radiation having a certain emission wavelength when said luminescent nanoparticle is excited with optical radiation having a certain emission wavelength.

Abstract: A sealed stopper for an opening in a tubing for joining a chamber and a piping including a fastening ring is provided. The stopper includes a rigid bearing plate and a sealing member carried by the bearing plate, and includes a seal having a planar and flexible central portion with a reduced thickness extending below the bearing plate and a peripheral portion radially deformable by a central expander of the peripheral portion against the inner surface of the fastening ring.

Abstract: The inventive tool is designed to ensure proper plant operation position of the core shroud head bolt assemblies of a boiling water nuclear reactor. The tool exerts an upward pulling force on stuck retainers to return them to the locking position around the nut. The tool includes a frame, an engagement member, and a collar. The engagement member is lowered toward and end of the bolt until it comes into contact therewith. Further movement of the engagement member causes the frame and collar to move upward, lifting the retainer and extending the spring.

Abstract: The invention relates to a method for preparing lead (212) for medical use. This method comprises the production of lead (212) by the decay of radium (224) in a generator comprising a solid medium to which the radium (224) is bound, followed by the extraction of the lead (212) from the generator in the form of an aqueous solution A1, characterised in that the lead (212) contained in the aqueous solution A1 is purified from the radiological and chemical impurities, also contained in said aqueous solution, by a liquid chromatography on a column. The invention also relates to an apparatus specially designed for automated implementation in a closed system of said method. It further relates to lead (212) produced by means of this method and this apparatus. Applications: manufacture of radiopharmaceuticals based on lead (212), useful in nuclear medicine for the treatment of cancers, particularly by a-radioimmunotherapy, or for medical imaging, in both humans and animals.

Abstract: A process which allows separation of americium present in an acid aqueous phase or in an organic phase from the other metal elements also found in this phase, by complexation of the americium with a water-soluble ethylenediamine derivative; and a process for selective recovery of americium from an acid aqueous phase containing, in addition to americium, other metal elements, which comprises the application of this separation process.

Abstract: The rod contains substantially cylindrical oxide nuclear fuel pellets based on enriched uranium oxide. The H/D ratio of the height over the diameter of the pellets lies in the range 0.4 to 0.6. The initial diametral clearance between the pellets and the cladding does not exceed 200 ?m.

Abstract: A device for identifying a metal substrate present in a strongly metallic environment that may also be dusty. The device includes a passive radio-frequency identification (RFID) label, a label carrier suitable for being attached to the metal substrate and to position the label at a distance therefrom, and a RFID reader having an antenna that includes, as an induction loop, two sections of a coaxial cable having a substantially identical length and each including a metal core and a metal pleat surrounding the core, the two sections being linked together, on the one hand, at one end thereof by connecting the core of one to the pleat of the other and conversely and, on the other hand, at the other end thereof by connecting only the pleats together, the cores thereof being separated at said other end.

Abstract: A pipeline shut-off device (10) comprising a tube section (10a) arranged in a pipeline (3) and having a shut-off member (19), wherein the shut-off member (19) can be destroyed in the closed position by a device (22) arranged in the region of the pipe section (10a), with the device for destroying the shut-off member (19) being able to be actuated from the outside.

Abstract: A sintered fuel pellet for a water nuclear reactor fuel rod including a peripheral wall extending along a central axis and two end faces. At least one of the end faces includes at least a first chamfer extending from the peripheral wall towards the central axis with a first non-zero slope with respect to a plane perpendicular to the central axis and a second chamfer extending from the first chamfer towards the central axis with a second non-zero slope with respect to a plane perpendicular to the central axis, wherein the first slope is different from the second slope.

Abstract: Position-indexed storage device comprising a support and a basket installed on the support, the basket comprising a plurality of compartments distributed around a longitudinal axis, the basket comprising a central passage with a longitudinal axis, the support comprising a shaft with a longitudinal axis, the shaft being housed in the passage such that relative displacement is possible between the basket and the support along the longitudinal axis, and mechanical means for displacement of the basket relative to the support by a given angle about the longitudinal axis are supported by the internal surface of the passage and the external surface of the shaft, said mechanical displacement means being actuated in each cycle, each cycle comprising a relative separation or approach displacement along the longitudinal axis of the basket and the support.

Abstract: A nuclear fuel cladding is provided. The nuclear fuel cladding includes a base cladding; and at least one nanomaterial layer deposited on a surface of the base cladding, the nanomaterial layer having an average grain size of between 5 to 400 nanometers. A method of manufacturing nuclear fuel cladding is also provided. The method includes depositing nanoparticles on a base cladding to form at least one nanomaterial layer, the nanoparticles having an average grain size of between 5 to 400 nanometers.

Abstract: New compounds which meet general formula (I): where: m=0, 1 or 2; R1 and R2=a C6 to C12, straight-chain or branched, hydrocarbon group; R3=H, a C1 to C12, straight-chain or branched, hydrocarbon group, optionally comprising one or more heteroatoms; a C3 to C8 monocyclic hydrocarbon group, optionally comprising one or more heteroatoms, or a monocyclic (hetero)aryl group; or else R2 and R3 together form a —(CH2)n— group where n=1 to 4; R4=a C2 to C8, straight-chain or branched, hydrocarbon group, or a monocyclic aromatic group; R5=H, or a C1 to C12, straight-chain or branched, hydrocarbon group.

Abstract: An alumino-borosilicate glass for the confinement, isolation of a radioactive liquid effluent of medium activity, and a method for treating a radioactive liquid effluent of medium activity, wherein calcination of said effluent is carried out in order to obtain a calcinate, and a vitrification adjuvant is added to said calcinate.

Abstract: A radiation attenuation elastomeric material which includes an elastomer in which a powder of metal oxides is dispersed, wherein the powder of metal oxides includes from 70 to 90% by mass of bismuth trioxide, from 5 to 15% by mass of tungsten trioxide, and from 5 to 15% of lanthanum trioxide. Multilayer protective gloves incorporating this material are suitable for use in protecting a wearer from ionizing radiation when handling radioactive materials.

Abstract: Described herein are solar energy collector systems, components for solar energy collector systems, and methods for installing solar energy collector systems. The components for solar energy collector systems include but are not limited to solar radiation absorbers, receivers, drives, drive systems, reflectors, and various support structures. The solar energy collection systems, solar radiation absorbers, receivers, drives, drive systems, reflectors, support structures, and/or methods may be used, for example, in LFR solar arrays. Drives and drive systems are described herein that may provide improved rotational positioning, movement, and/or rotational positional sensing. For example, drives and drive systems are provided which allow operation through a variable frequency drive. The components and methods described herein may be used together in any combination in a solar collector system, or they may be used separately in different solar collector systems.