FRAMATOME

A subrack assembly ( 1 ) comprising a subrack ( 3 ) comprising two top rails ( 9 ), two bottom rails ( 7 ) and side elements ( 5 ), at least one rigidifying frame ( 21 ) comprising a front crossbeam, a rear crossbeam and two side beams; and at least one connector ( 70 ) for connecting the rigidifying frame ( 21 ) to the top and/or bottom of the subrack ( 3 ), comprising at least one movable block movable in translation relative to the rigidifying frame ( 21 ) between an insertion position, in which it is spaced away from the subrack ( 3 ) and a use position, in which it bears against the subrack ( 3 ). The connector ( 70 ) is configured for connecting the rigidifying frame ( 21 ) to the top and/or bottom of the subrack ( 3 ) such that the front and rear crossbeams each extend substantially parallel to a top or bottom rail ( 7, 9 ) of the subrack ( 3 ) and in alignment therewith along a vertical direction.

An anchoring device ( 1 ) for anchoring an equipment to a civil engineering structure includes a support plate ( 5 ) for the equipment, with at least two orifices ( 7 ); for each orifice ( 7 ), a longitudinal dowel ( 13 ) intended to be rigidly fastened in the civil engineering structure ( 3 ); for each orifice ( 7 ), a fastening member ( 25 ) mounted around the dowel ( 13 ); for each orifice ( 7 ), a connection ( 27 ) of the fastening member ( 25 ) to the plate ( 5 ), allowing the fastening member ( 25 ) to be placed at any given position in a defined region of the orifice ( 7 ) in a plane parallel to the plate ( 5 ); and for each orifice ( 7 ), a reversible lock ( 55 ) for blocking the fastening member ( 25 ) with respect to the plate in the given position and for blocking the fastening member in position along the dowel ( 13 ).

A reactor ( 1 ) for hydrolysis of uranium hexafluoride comprises a tubular injector ( 9 ) comprising first ( 11 ), second ( 13 ) and third ( 15 ) concentric fluid circulation ducts intended to be connected respectively with a source of UF 6 , a source of inert gas and a source of water vapor. The tubular injector ( 9 ) is obtained by additive manufacturing.

A nuclear fuel cladding element comprises a substrate made of a material containing zirconium and a protective coating covering the substrate on the outside. The protective coating is being made of a material containing chromium, and has a columnar microstructure composed of columnar grains and having on the outer surface thereof a microdroplet density of less than 100 per mm2.

A method regulates operating parameters comprising at least the mean temperature of the core (T m ), and the axial power (AO) imbalance. The method includes development of a vector (U S ) of control values of the nuclear reactor by a supervisor ( 31 ) implementing a predictive control algorithm; development of a vector (u K ) of corrective values of the nuclear reactor controls by a regulator ( 33 ) implementing a sequenced gain control algorithm; development of a vector (U) of corrected values of the commands of the nuclear reactor, by using the vector (U S ) of the values of the commands produced by the supervisor ( 31 ) and the vector (u K ) of the corrective values of the commands produced by the regulator ( 33 ); and regulation of the operating parameters of the nuclear reactor, by controlling actuators using the vector (U) of the corrected values of the controls.

A test method is for testing a spacer grid of a nuclear fuel assembly comprising a bundle of nuclear fuel rods and N spacer grids distributed along the bundle of nuclear fuel rods, where N is a positive integer equal to or greater than four. The method of testing includes providing a test assembly comprising a bundle of test rods shorter than the nuclear fuel rods and three spacer grids distributed along the test rods, generating an impact on the centrally located spacer grid, and measuring and recording at least one impact parameter and/or at least one displacement of said centrally located spacer grid.

A platform for a nuclear power plant is configured to span a pool ( 4 ) of a nuclear power plant by being movable along two parallel rails ( 6 ) arranged on either side of the pool ( 4 ). The platform comprises at least one platform module ( 16 ) having a module floor ( 18 ) defining at least part of a platform floor ( 14 ) and two guide assemblies ( 20 ) for mating with rails ( 6 ) to guide the platform along said rails ( 6 ). Each platform module is expandable to vary the spacing between the two guide assemblies ( 20 ) of the platform module ( 16 ), the two guide assemblies ( 20 ) being close together in a storage configuration and far apart in a service configuration.

A radioactive sodium destruction facility includes a tank for storing liquid metallic sodium, located at a first level; a reaction vessel containing an aqueous solution; a sodium feed circuit comprising a sodium circulation member located at a second level higher than the first level, the circulation member having a suction in fluid communication with the tank and a discharge in fluid communication with the reaction vessel; an inert gas supply unit configured to supply the tank; a controller driving the sodium circulation member; and an inert gas supply unit configured to supply the tank; and a controller driving the supply unit to control a gas pressure in the tank, such that a pressure at the suction of the sodium circulation member is maintained within a predetermined range.

A BWR fuel assembly is elongated along a fuel assembly axis and comprises a lower tie plate, an upper tie plate axially spaced from the lower tie plate, a bundle of fuel rods extending axially between the lower tie plate and the upper tie plate, and a tubular fuel channel extending from the lower tie plate to the upper tie plate with encasing the fuel rods. The fuel assembly comprises an interaction device mounted on the lower tie plate and configured to interact with the fuel channel. The interaction device has an inactive configuration and an active configuration.

An installation is for the destruction of radioactive metallic sodium and includes a reaction vessel containing an aqueous solution, the reaction vessel having an aqueous solution outlet; a sodium feed circuit configured for feeding liquid metallic sodium into the reaction vessel; a liquid effluent treatment unit, comprising a drain tank and a drain line fluidically connecting the aqueous solution outlet to the drain tank; a gas treatment unit configured for diluting the gases and releasing the diluted gases into the atmosphere, the drain tank having a gas outlet fluidically connected to the gas treatment unit; an inert gas feed unit configured for feeding the drain tank.