Abstract: A device for measuring and correcting a parallelism error of an upper plug end of a nuclear fuel rod comprising mechanisms for measuring a parallelism error and for correcting said error, and a mechanism for positioning said device on the fuel rod and cooperating with a rack on which the fuel rod is stored, said correction means being arranged opposite the measuring mechanism relative to the location of the fuel rod, in order to allow a measurement of the parallelism error during correction of said error.

Abstract: A collecting line for leakage monitoring in an installation is permeable to a substance to be monitored in at least one subarea extending along the longitudinal direction. The collecting line is formed of at least two subsections that are spaced from a first end of the collecting line. The distance between the second subsection and the first end is larger than the distance between the first subsection and the first end. The permeability to the substance to be monitored is higher in the first subsection than in the second subsection. A device having the collecting line is also provided.

Abstract: A wind turbine tower is provided. The wind turbine includes a tower wall, at least one inlet formed in a section of the tower wall for introducing air surrounding the wind turbine tower into the wind turbine tower, and a tower wall reinforcement, the tower wall reinforcement bracing the inner circumference of said tower wall section, and the tower wall reinforcement defining an air duct for guiding the air along the inner circumference of said tower wall section.

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 module including a casing extending in a longitudinal direction, a bundle of fuel rods encased in and supported by the casing and connector provided on the casing for connecting the casing side-by-side to the casing of at least one other module to obtain a nuclear fuel assembly having a channel box defined by the casings of the assembled modules and of larger cross-section than the casing of each of the assembled modules and a bundle of fuel rods of larger cross-section than that of each the assembled modules.

Abstract: A sealed stopper for an opening in a junction tubing between an enclosure and a pipe, including an attachment ring. The stopper includes a rigid lid and a sealing assembly borne by the lid including a passive annular gasket including at least one annular internal chamber, a first static annular gasket, a second static annular gasket and a flat gasket ensuring the seal of the opening of the tubing.

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: A method and a system for catalytic recombination of hydrogen, which is carried in a gas flow, with oxygen, has the gas flow passed through a reaction zone with a number of catalytic converter elements, with steam being added to the gas flow before it enters the reaction zone. The method and system ensure a particularly high operational reliability of the recombination device, even in varying operating conditions or with varying operating methods, in particular with regard to a hydrogen feed, which is provided as required, in the steam/feed water circuit of the installation. For this purpose, the feed rate of the steam to be added is adjusted in dependence on a measured value which is characteristic of a current actual temperature in the reaction zone.

Abstract: The heat exchange assembly (1) for exchanging heat between a first and a second fluid comprises: a plurality of heat exchange modules (12) for exchanging heat between the first and second fluids, these being distributed about a central axis (X) and having opposing respective lateral faces (47); feed manifolds (14, 16) for feeding the modules (12) with primary and secondary fluid and collection manifolds (18, 20) for removing these fluids. At least some of the said manifolds (14, 16) or parts of the said manifolds (18) run between the modules (12), the said manifolds (14, 16) or parts of manifolds (18) flanking one and the same module (12) being positioned substantially symmetrically with respect to the mid-plane situated between the two lateral faces (47) of the said module (12) in such a way that the said manifolds (14, 16) or parts of manifolds (18) create substantially identical thermal stresses in the lateral faces (47) of the module (12).

Abstract: A method for determining tube support plate blockage of a steam generator includes the following steps: measuring at least five different eddy current values per tube support intersection; calculating a nominal clean fit radius of flow hole; determining a center signal response; converting the center signal response to a deposit thickness; determine an edge reduction; converting the edge reduction to an edge thickness; calculating the resulting flow hole radius; verifying the reasonableness of the resulting flow hole radius; and determining a virtual calibration range.

Abstract: A method for measuring the neutron flux in the core of a nuclear reactor, the method including several steps recurrently performed at instants separated by a period, the method comprising at each given instant the following steps: acquiring a total signal by a cobalt neutron detector placed inside the core of the reactor; assessing a calibration factor representative of the delayed component of the total signal due to the presence of cobalt 60 in the neutron detector; assessing a corrected signal representative of the neutron flux at the detector from the total signal and from the calibration factor; assessing a slope representative of the time-dependent change of the calibration factor between the preceding instant and the given instant; the calibration factor at the given instant being assessed as a function of the calibration factor assessed at the preceding instant, of the slope, and of the time period separating the given instant from the preceding instant.

Abstract: A method for producing a wear-resistant and corrosion-resistant stainless steel part for a nuclear reactor is provided. This method comprises steps of providing a blank in stainless steel; shaping the blank; finishing the blank to form the part in stainless steel, the finishing step allowing the prevented onset or the removal of work hardness on the outer surface of the part; hardening the outer surface of the part via diffusion of one or more atomic species.

Abstract: A filter including a plurality of flow ducts extending in a longitudinal direction and each delimited between one pair of walls is provided. The filter includes deflectors protruding into each duct alternately from the pair of walls with overlapping in the longitudinal direction to define a zigzag shaped flow channel and provided with at least one set of holes aligned in the longitudinal direction to define through the overlapping deflectors a passage for accommodating a lower end pin of a fuel rod.

Abstract: A filter is provided which includes channels for circulation of coolant fluid through the filter, at least one channel extending along a channel centerline and includes an upstream section, a downstream section and an intermediate section extending between the upstream section and the downstream section and being enlarged relative to the upstream section and the downstream section. The filter also includes at least one separating member defining inside the intermediate section of the at least one channel an annular passage whose axis is substantially coaxial to the channel centerline in the intermediate section.

Abstract: A collector system (12) is disclosed that comprises a row of linearly conjoined collector structures (13). The collector system is arranged to be located at a level above a field of reflectors (10) and to receive solar radiation reflected from the reflectors within the field. The collector structure (13) comprises an inverted trough (16) and, located within the trough, a plurality of longitudinally extending absorber tubes (30) that, in use, are arranged to carry a heat exchange fluid. The absorber tubes (30) are supported side-by-side within the trough and each absorber tube has a diameter that is small relative to the aperture of the trough. The ratio of the diameter of each absorber tube to the trough aperture dimension is of the order of 0.01:1.00 to 0.10:1:00 and, thus, a plurality of absorber tube functions, in the limit, effectively to simulate a flat plate absorber.

Abstract: A sealing device for a device for measuring a fill level in a fluid container, particularly in a pressure container of a nuclear facility, includes at least one thermocouple which is connected by a pressure pipe to the pressure container and a pipeline connected to the pressure pipe to an evaluation unit. The pressure pipe and the pipeline are connected to each other by a pipe screw connection including a central part having two threaded pieces. One threaded piece is connected by a screw connection to a pipe sleeve and the other threaded piece is connected by a further screw connection to the pressure pipe.

Abstract: Disclosed herein are examples and variations of solar energy collector system comprising an elevated linear receiver (5) and first and second reflector fields (10P, 10E) located on opposite sides of, and arranged and driven to reflect solar radiation to, the receiver (5). Also disclosed herein are examples and variations of receivers (5) and reflectors (12a) that may, in some variations, be utilized in the disclosed solar energy collector systems.

Abstract: An integrated reactor missile shield and crane assembly (IRMSCA) is disclosed and claimed. The IRMSCA replaces the existing concrete missile shields and reactor services crane. The IRMSCA is moveable such that the missile shield can be moved away from the reactor head, allowing the integral crane to lift the control rod drive mechanism components and other routine loads at the refueling cavity.

Abstract: The present invention relates to a proton-conductive electrochemical cell (10), comprising an electrolytic membrane (13) made of a ceramic and an electrode (11, 12) made of a cermet, said electrochemical cell (10) being obtained directly by a method of co-sintering a ceramic layer, capable of forming the electrolytic membrane (13), and a cermet layer, capable of forming the electrode (11, 12), in a sintering tool at a sintering temperature of the ceramic that makes it possible to render said ceramic layer, capable of forming the electrolyte (13), gas-tight, wherein said cell (10) is characterised in that said cermet consists of the mixture of a ceramic and an electronically conductive passivatable alloy including at least 40 mol % chromium capable of forming a passive layer, the nature and the chromium content of said passivatable alloy enabling said electrochemical cell to be co-sintered with a membrane densification of more than 90% without melting said alloy.

Abstract: A method to analyze crystals in a deposit on a surface of a nuclear generating station heating surface, wherein the method extracts a sample of material from the surface of the nuclear generating station heating surface and also includes conducting at least one of a high resolution scanning electron microscope/energy dispersive X-ray spectrometry of the sample and a scanning transmission electron microscope/selected area electron diffraction/spot and elemental mapping analysis of the sample.