Abstract: The aim of the method is to characterize an element (21) comprising a plurality of superposed layers separated from one another by interfaces. It comprises at least the following steps: The element (21) is illuminated with radiation (15) emitted by a source (13); radiation (23) transmitted through the element (21) is collected on a detector (17), this transmitted radiation forming an experimental image of the element (21) on the detector (17), the detector (17) being placed at such a distance from the element (21) that interference fringes appear on the experimental image at the interfaces between the layers; and an approximate value of at least one physical characteristic of at least one given layer is determined by calculation from the experimental image, the determination step being implemented by minimizing the difference between the experimental image and a simulated image of at least part of the experimental image of the element (21).

Abstract: A glove box with a sealed containment area delimited at least partially by a wall having a an inner partition facing the sealed containment area, an outer partition spaced from the inner partition and located outside of the containment area, and a lighting means with a light source housed between the inner partition and the outer partition.

Abstract: Production device including a press, a conveyor (4) intended to transport pellets from the press to a sintering area, means (26) for transferring pellets from the press to the conveyor (4), and means for inspecting at least one nuclear fuel pellet at the exit of a press, said inspection means including means (20) for identifying each pellet according to its die of origin.

Abstract: The present invention provides a method of operating a Boiling Water Reactor, having the steps of analyzing LPRM signals for oscilliatory behavior indicative of neutron-flux-coupled density wave oscillations, determining if oscilliatory behavior is present in the signals; initiating a reactor protective corrective action if the oscilliatory behavior is determined, and in addition, initiating corrective actions if neutron uncoupled oscillations are possible. Detecting the later is performed through analytically determined exclusion zone on the power flow map or by on-line stability calculations for several high power channels.

Abstract: The invention relates to a nuclear power station comprising: at least one high temperature reactor; a storage installation (14) for fuel elements (5); means (32) for transferring the fuel elements (5) between the core (4) and the storage installation (14). According to the invention, the transfer means (32) comprise a tunnel (34) for transferring the fuel elements between the reactor core (4) and the storage installation (14).

Abstract: A plurality of capsules are made available, each for receiving a fuel rod, and each comprising a tubular sheath that is closed at its ends by plugs. A loading structure is placed in a pool to receive at least one capsule with its axis vertical. A device for loading fuel rods into the capsule is secured onto an open top end of the structure. Defective rods are taken one by one and inserted one by one into empty capsules in the loading structure. For each capsule that is to receive a defective rod, a top plug of the capsule is unscrewed, a defective rod is inserted into the capsule through a guide device of the loading device, the top plug is screwed back onto the capsule, and the capsule containing the rod is put into a location in the support structure.

Abstract: A method and a corresponding device for the pressure relief of a nuclear power plant having an outlet for a relief flow. The relief flow is guided out of a containment into the atmosphere via a relief line provided with a filter system. The filter system has a filter chamber with a filter-chamber inlet and outlet and a sorbent filter arranged therebetween. The relief flow is guided in a high-pressure section of the relief line past the filter chamber, with the latter being heated, and the relief flow is expanded at the end of the high-pressure section and dried. In order for efficient retention of iodine-containing organic compounds, the relief flow is guided through a bed filter, guided in a superheating section past the high-pressure section of the relief line and in the process is heated, guided in this state directly thereafter through the filter chamber having the sorbent filter.

Abstract: An electrical insulator disk has central recesses and peripheral recesses to enable the disk to be mounted floatingly relative to flanges between which the disk is held and to a linear conductor that extends through the disk.

Abstract: A nuclear engineering plant has a containment, whose interior chamber is subdivided by a wall into a systems chamber and an operating chamber which is accessible during normal operation. The containment ensures a particularly high operational reliability, in particular also in incident situations, in which hydrogen is released in the systems chamber. For this purpose, a number of overflow openings are provided in the partition wall, the respective overflow opening is closed by a closure element of a closure apparatus which opens automatically when a trigger condition associated with the respective overflow opening is reached. Closure apparatuses are provided which open both as a function of pressure and independently of pressure. The closure apparatus furthermore has a closure element containing a bursting film or a bursting diaphragm. The closure apparatus is configured such that it frees the overflow opening automatically when a predetermined environment-side trigger temperature is reached.

Abstract: The electricity transmission device comprises prolonged rigid conductors made of copper, and also a connector comprising a network of flexible elements, such as brazed tubes with cooling channels for the conductors, that enables angular displacements between the successive segments and therefore gives a flexibility absorbing small displacements of the device. A lifting manoeuvre system is associated with the segments. The segments may be joined to other elements of the device through connections with jaws enabling slipping.

Abstract: A method is provided for the non-destructive and contactless characterization of a multilayered structure having a substantially spherical shape and including at least two layers, separated by interfaces. The method includes using a laser for locally heating the structure in a thermoelastic state so that the structure is vibrated in a non-destructive manner, measuring the resonance frequencies of the vibration modes of the structure and deriving at least one characteristic concerning the integrity or the shape or the mechanical behavior of the structure from the resonance frequencies of the structure.

Abstract: Methods for removing nuclear waste from a component are provided. In one embodiment, the method includes the steps of supplying oxalic acid to the nuclear waste on the component to form an oxalic acid/waste solution, feeding the oxalic acid/waste solution from the component, feeding an oxidant to the oxalic acid/waste solution to form carbon-dioxide, water and a precipitate, and separating the precipitate from the water. A system for removing nuclear waste is also provided.

Abstract: A piping assembly for directing fluid and mitigating acoustic and vortex coupled resonance is provided that includes a main pipe delivering fluid in a first direction; a standpipe coupled to the main pipe at an intersection; and a scoop positioned at the intersection directing the fluid towards the standpipe. A scooping insert and a method for disrupting vortex shedding in a piping assembly are also provided.

Abstract: An energy management system has a control center at a utility company, and logic resources coupled to the power system that provide a real time notice of conditions which effect energy management of the utility company. At least one user interface is provided at the control center that is coupled to the logic resources. The user interface provides a real time situation awareness of a potential energy management failure.

Abstract: A device for phase separating a multi-phase fluid flow has a housing configured substantially rotationally symmetrically about a center axis and encloses a hollow space, at least one in-feed line for the fluid flow configured for inflow of the fluid flow directed substantially tangentially to an interior of the housing, and at least one outlet line for the separated gaseous portion of the fluid flow. The device heats the gaseous portion of the fluid flow, such as steam, and requires little material and space. To this end, heating elements configured for heating the gaseous portion are disposed in the hollow space in an annular chamber placed concentrically about the center axis.

Abstract: Sealing means comprising a seal carrier and a seal connected thereto, wherein the seal carrier is removably fixable between two areas insulated from each other, and a transfer device between two chambers, which are separated by a wall, wherein said transfer device comprises a transfer mechanism and at least one sealing means according to the invention which is positioned between the wall and the transfer mechanism.

Abstract: The nuclear reactor comprises a lower stopper sealingly fixed to a lower end of a tubular casing of the pencil that comprises a part which is internal to the casing successively comprising a first cylindrical section having a diameter which is substantially equal to the inner diameter of the tubular casing; a second cylindrical section whose diameter is smaller than the inner diameter of the tubular casing and a third cylindrical section whose inner diameter is smaller than the inner diameter of the tubular casing and greater than the diameter of the second cylindrical section such that 1-2 tenths of a millimetre radial play is created in the gas passable between the outer surface of the third section and the inner surface of the casing.

Abstract: A method for treating a nitric aqueous liquid effluent containing nitrates of metals or metalloids, comprising a step for calcination of the effluent in order to convert the nitrates of metals or metalloids into oxides of said metals or metalloids, at least one compound selected from the nitrates of metals or metalloids and the other compounds of the effluent leading upon calcination to a tacky oxide, and a dilution adjuvant comprising at least one nitrate of metal or metalloid leading upon calcination to a non-tacky oxide being added to the effluent prior to the calcination step in order to give a mixture of effluent and of dilution adjuvant.

Abstract: The invention relates to a device (10) for operating in a water chamber (7) of a heat exchanger (1) comprising a wall (6) of substantially hemispherical shape and, at its upper portion, a tube plate (5) traversed by a plurality of vertical holes (4). The device comprises at least one rail (11) furnished with members for attachment on the bottom face of the tube plate (5) and supporting at least one trolley (15) that can be moved along the said rail (11) and fitted with a pendular lifting means (19) and a robotic arm (20) comprising an attachment base (30) furnished with members for coupling on the bottom face of the tube plate (5) and a drive means interacting with the lifting means (19) to draw the attachment base (30) against the tube plate (5). The invention applies more particularly to the steam generator of a pressurized water nuclear reactor.

Abstract: A zirconium alloy tube for forming the whole or the outer portion of a nuclear fuel pencil housing or a nuclear fuel assembly guide tube. The zirconium alloy contains 0.8-1.8 wt. % of niobium, 0.2-0.6 wt. % of tin and 0.02-0.4 wt. % of iron, and has a carbon content of 30-180 ppm, a silicon content of 10-120 ppm and an oxygen content of 600-1800 ppm. The tube may be used when recrystallized or stress relieved.