Abstract: This photothermal examination camera (16) comprises: a system (22) for shaping a laser beam (4), which includes a device (40) for elongating the cross section of the beam in order to form, on a surface of a part (1) to be examined, an elongate heating zone along a direction; a matrix (8) of infrared detectors for detecting infrared radiation emitted by a detection zone on the surface (1a) of the part (1) relative to the heating zone; and a signal processing unit (46) for processing the signals delivered by the infrared detectors in order to construct a thermographic image of the surface (1a) of the part (1) by scanning the surface (1a) with the heating zone. The camera includes a system for mechanically adjusting an offset between the elongate heating zone and the detection zone. Application to the non-destructive inspection of parts.

Abstract: A method to determine deposits in a steam generator having the steps of creating a calibration standard having at least two rings of deposit material, subjecting the calibration standard to an eddy current signal, wherein an amplitude of the signal reflected from the calibration standard is used to obtain a polynomial equation fit of the reflected eddy current signals to actual thickness of the rings, obtaining a steam generator with tubes, initiating an eddy current signal into the tubes of the steam generator, detecting and recording reflections of the eddy current signal initiated into the tubes of the steam generator, and determining a thickness of the deposits in the steam generator from the recorded reflections of the eddy current signal and the polynomial equation.

Abstract: The invention relates to a method of repairing a vessel bottom head penetration of a nuclear reactor, said penetration comprising a tube (10) fastened to the internal wall of the vessel bottom head (1a) by an internal weld bead (11) and emerging outside the vessel bottom head, forming a groove (15). The method consists inter alia in preparing a mock-up representative of the vessel bottom head penetration to be repaired and in depositing this mock-up on site in an irradiation-free zone, in fastening two half-inserts (30a, 30b) to this mock-up in the groove, each half-insert having a profile corresponding to the half-profile of the groove, in forming, again on this mock-up, automatically and by remote control, a weld bead (35) in the groove (15), in carrying out a dimensional check and, after validation of this weld bead (35), in carrying out the steps of fastening the two half-inserts and forming a weld bead automatically, directly in the groove (15) of the vessel bottom head penetration to be repaired.

Abstract: An aligning device for fuel elements allows fuel elements of a pressurized water reactor to be aligned in a comparatively easy and quick manner. To this end, the aligning device for fuel elements includes an aligning body, which extends in a longitudinal direction and whose lateral faces formed from side metal sheets can be displaced out of a position of rest in a direction that is perpendicular to the longitudinal direction. The cross-sectional dimensions of the lateral faces of the aligning body in the position of rest are selected so that they are less than the corresponding cross-sectional dimension of a reference fuel element by a predetermined nominal value.

Abstract: A fuel assembly for a pressurized water nuclear reactor includes a multiplicity of fuel rods which extend in a longitudinal direction and are guided in a plurality of spacers that are spaced apart from one another axially. The spacers of an upper region have a lower flow resistance in a transverse direction perpendicular to the longitudinal direction, than the spacers of a lower region.

Abstract: A pump unit for a nuclear installation, for example a pressurized water reactor, contains a vertical shaft, which is guided through at least one journal bearing. The journal bearing or bearings is or are configured as a spiral groove bearing or bearings, to prevent shaft vibration caused by the bearings and to increase the service life of the pump unit. Preferred uses of the pump units include, for example, the coolant pump of a pressurized water reactor and the circulating pump of a boiling water reactor.

Abstract: A method and apparatus for removing uranium (IV) and uranium (VI) from sands and soils. The method and device assays a volume of soil and determines a presence and position of uranium enrichment. A concentration of uranium enrichment is determined, and compared to a threshold concentration. The volume of soil is processed and transported to a coarse screen, deck screen and classified in a classifier. In the classifier, the volume of soil is separated into a washed and fines fraction, assayed and transported to a uranium recovery facility, then transported to a silicon removal process and subsequent ammonia and metals removal processes.

Abstract: A method of purifying water in a nuclear installation includes an ion exchange mechanism in which the water is purified with an ion exchanger. Before being guided over the ion exchanger, the water is brought into contact with a catalyst in order to decompose hydrogen peroxide that is present in the water.

Abstract: A grid (13) for supporting nuclear fuel pencils (3) for a nuclear fuel assembly (1) comprising a peripheral belt (17), the peripheral belt (17) comprising on at least one of its edges (35, 37) guide fins (33) is disclosed. The edge (35, 37) of the peripheral belt (17) has between the adjacent guide fins (33) recesses (39) towards the inside of the grid (13). The invention is applicable, for example, to pressurized water reactors.

Abstract: A pipeline configuration for the transport of a liquid, especially petroleum, contains a pipeline laid above ground, beneath which is disposed a sensor line for detection of a leak, extending along the pipeline in its longitudinal direction. The sensor line is disposed in a catchment container, fixed to the pipeline and likewise extending along it, at its lowest point. The catchment container has side edges running in the longitudinal direction and have a spacing from the outer surface of the pipeline. Inside the catchment container a device is disposed to reduce an air flow moving between the catchment container and the outer surface of the pipeline transversely to its longitudinal direction.

Abstract: The present invention is mainly directed to a disconnector for an electrical substation for very high voltage in excess of 1100 kV, of the horizontal displacement type comprising a first moving part (2) and a second moving part (4), the said first moving part (2) and second moving part (4) each comprising at least two articulated arms (14, 16, 114, 116) which are arranged to make contact with each other through a free end. In the closed position, which is the closed position of the disconnector, the first arms (14, 114) and the second arms (16, 116) of each of the moving parts together define a non-flat angle (?) so that they form an arch, the two second arms (16, 116) being aligned with each other in a substantially horizontal position.

Abstract: A disconnection device is designed to separate a first portion of an electrical circuit electrically from a second portion of said circuit, the disconnection device including: at least one pair of contacts, one of which contacts is a moving contact, the pair of contacts having an open state and a closed state and a flexible conductor fixed at one end to the moving contact and serving to be fixed at the other end to one of the portions of the electrical circuit. The conductor comprises a flexible tube that is electrically conductive, at least at a surface portion thereof, and that has bending stiffness that is low enough to enable it to bend without kinking, and torsion stiffness that is high enough to enable it to take up a shape and a position that are substantially reproducible at least in the closed state. The device is used in particular in gas-insulated high-voltage electricity substations.

Abstract: In order to reduce the breaking energy of a high-voltage or medium-voltage circuit-breaker, the interrupting chamber (10) contains two contacts (12, 14) mounted to move in opposite directions, and actuated via a single device (20). The two contacts (12, 14) are surrounded by an insulating casing (18) of tubular shape, coupled in fixed manner to the main contact (12). The contacts (12, 14) are actuated by a device having a lever (24) in which each lever arm is coupled to a link, one of the links (32) being secured to the insulating casing (18) and the other link (34) being secured to the second contact (14). The guiding of the drive tube (18) on the main contacts (12b, 14b) makes it possible to improve breaking by keeping clean gas between said main contacts.

Abstract: An on-load transformer tap changing system, for example for a power transformer, wherein the secondary or primary of a transformer includes at least one first tap and one second tap. A main connection circuit is used for permanent connection of the first tap or the second tap to an output terminal of the secondary or primary of the transformer. Secondary connection circuits are each used to connect a tap temporarily and directly to the output terminal of the secondary or primary of the transformer. Each of the connection circuits includes one or more insulated gate bipolar transistors. The system can be controlled without zero current value transition detection in the secondary winding.

Abstract: In order to reduce the breaking energy of a high-voltage or medium-voltage circuit-breaker, the interrupting chamber (10) contains two contacts (12, 14) mounted to move in opposite directions, actuated via a single device (20, 30). The two contacts (12, 14) are driven in opposite directions by a cylindrical cam (22) having slots (26, 28) that co-operate with fixed rods (32, 42), each of which is connected to a respective one of the contacts (12, 14): the profiles of the slots (26, 28) make it possible to manage the speed and the amplitude of the movement of the second contact (14) relative to the main contact (12) without requiring any complex design.

Abstract: A pressure vessel of a reactor has a flow space between the reactor core and a separation device for separating water from water steam. The cross-section area of the flow section of the space expands upstream of the separation device. This makes it possible to pre-separate a water-water steam mixture coming from the reactor core. Due to the pre-separation, only the central area is provided with a cyclone device, and only drying equipment is disposed near the cyclone device. The novel approach makes it possible to reduce the height of the pressure vessel of a reactor.

Abstract: The invention relates to a method for regulation of operational parameters of the core of a pressurised water nuclear reactor comprising: a step of acquisition of values (FH, FB, TBC, TBF, Q) which are representative of the conditions of operating of the core of the reactor; a step of evaluation of the actual values (Tmoye, AOe, {circumflex over (P)} maxe) of the operational parameters at least according to the values acquired (FH, FB, TBC, TBF, Q); a step of selection of a control law for the concentration of a neutron-absorbent component ([B]) and for the positions of insertion (Z1 to Z5) of the groups (P1 to P5) of rods selected from at least the first and second control laws which are different from one another; and a step of regulation of the operational parameters by means of the control law selected, according to set points (Tmoyc, AOc, {circumflex over (P)} maxc) relative to the said parameters and to the actual values (Tmoye, AOe, {circumflex over (P)} maxe) evaluated.

Abstract: A device and technique for placing and moving a ferromagnetic element in an annulus between coaxially arranged cylindrical tubes. The device includes an electromagnetic ram moved along the interior of a cylindrical tube. The movable ferromagnetic element is magnetically coupled to the electromagnetic ram and moved by magnetic force to a location in the annulus defined by the tubes and magnetically coupled to the electromagnetic ram for movement in and removal from the annulus.

Abstract: A collector line for leakage monitoring and leakage location at a plant includes a carrier tube having a wall with openings formed therein, which are sealed with silicone rubber. This makes it possible to use the collector line during low ambient temperatures. A device and a method for leakage monitoring and leakage location and a pipeline having a collector line, are also provided.

Abstract: Metal-clad electrical equipment comprises a metal vessel (4) and an exhaust constituted by an arcing contact support tube (9) and a casing (16) surrounding the support tube (9) and co-operating therewith to define an annular volume (20). At one end, the support tube has an inlet for passing arc gas. Exhaust holes (17) are provided through the casing to allow arc gas to escape into the vessel. The equipment includes a particle trap (22) situated in the exhaust between the arcing contact support tube (9) and the exhaust casing (16).