Abstract: A nuclear reactor (1) includes a vessel (3) has a central axis (X); and a core (5) arranged in the vessel (3). The core (5) includes a plurality of nuclear fuel assemblies, a primary water layer (7) separating the core (5) from the vessel (3) radially from the central axis (X) and surrounding the core (5); and a system (9) for controlling and protecting the nuclear reactor. The control and protection system (9) includes a device (11) for continuously measuring the neutron flux emitted by the core (5). The measuring device (11) includes at least one neutron detector (12) arranged in the primary water layer (7) separating the core (5) from the vessel (3).

Abstract: A vessel electrical penetration assembly for a feed-through of nuclear reactor vessel, the assembly including: a docking tube to form an extension of the secondary containment barrier of the reactor, the docking tube including: a first end to be positioned in the interior of the vessel and to be mechanically and sealably connected to an actuator in the interior of the vessel, and a second end to be mechanically and sealably secured to the vessel; a seal-tight electrical bar that passes through the docking tube and having on either side seal-tight connectors ensuring an electrical link between the actuator and the exterior of the reactor; the seal-tight electrical bar including a system for limiting a leakage of primary liquid to the exterior of the vessel if the secondary containment barrier extension fails; and a mechanical maintaining system for securing, under the required pressure conditions, the electrical bar to the vessel.

Abstract: A nuclear reactor vessel includes a shell (5) having a wall (9) traversed by at least one passage (11) having a central axis (C) and a valve (21) mounted in the passage (11), the valve (21) having a determined outer cross-section. The passage (11) has an inner end segment (23) that opens into the inner volume (7) and an outer end segment (25) that opens into an outer piping (13), the valve (21) being housed in the inner end segment (23). The valve (21) is capable of being extracted from the passage (11) through the inside of the vessel (1). The outer end segment (25) has at least one portion having an inner cross-section, perpendicular to the central axis (C), that is smaller than the outer cross-section of the valve (21), such that the valve (21) cannot be ejected out of the vessel (1).

Abstract: A nuclear reactor (10) includes a vessel (12) containing a primary liquid, a core (14) comprising nuclear fuel and arranged in the internal volume of the vessel (12), at least one primary pump generating a main primary flow (56) of primary liquid in the vessel (12), at least one control member (16) for controlling the reactivity of the core (14), at least one movement mechanism (18) for moving the control member (16), arranged in the internal volume of the vessel (12) and linked to the control member (16), and a pressurizer (20) situated in a top portion of the vessel (12). The movement mechanism (18) comprises an electrical actuator and a transmission mechanism. The electrical actuator is completely immersed in the primary fluid and situated outside the main primary flow (56).

Abstract: A nuclear reactor includes a vessel incorporating at least one primary power heat exchanger for cooling the primary liquid of the nuclear reactor during the normal operation of the reactor and at least one primary passive safety heat exchanger for cooling the primary liquid of the nuclear reactor in the event of a malfunction in the normal cooling of the primary liquid of the reactor. The vessel includes a compartment arranged in the thickness thereof, wherein the primary passive safety heat exchanger is at least partially contained inside the compartment.

Abstract: A nuclear reactor has a pressurizer housed in a vessel. Heating elements are completely housed in the pressurizer. The nuclear reactor has electrical conductors that are the only feature leaving the vessel through electrical penetrations. The nuclear reactor can be operated to produce energy. The production of energy can be stopped, and the vessel of the reactor can be opened for performing maintenance operations on elements of the pressurizer and other components of the reactor, including fuel assembly replacement. After performing maintenance operations, the vessel of the reactor can be closed and energy production resumed.

Abstract: An electrical penetration assembly for a nuclear reactor vessel, mountable in an aperture of a nuclear reactor vessel, includes a penetration body including first and second ends to be positioned, respectively, inside and outside the vessel; a sealed electrical connector providing a first seal for the electrical penetration assembly, the sealed connector insulating the penetration body at the first end; a feed-through carrier flange having a plurality of unitary electrical feed-throughs, each unitary feed-through allowing a single electrical conductor to pass therethrough, thereby ensuring continuity of the electrical connections, each unitary feed-through being individually insulated by an individual insulator providing a second seal, the unitary feed-throughs insulating the penetration body at the second end; and an anti-ejection device formed by the engagement between a narrowed portion provided at each unitary feed-through and a shoulder that is larger than the narrowed portion and provided on each of the

Abstract: A vessel electrical penetration assembly for a feed-through of nuclear reactor vessel, the assembly including: a docking tube to form an extension of the secondary containment barrier of the reactor, the docking tube including: a first end to be positioned in the interior of the vessel and to be mechanically and sealably connected to an actuator in the interior of the vessel, and a second end to be mechanically and sealably secured to the vessel; a seal-tight electrical bar that passes through the docking tube and having on either side seal-tight connectors ensuring an electrical link between the actuator and the exterior of the reactor; the seal-tight electrical bar including a system for limiting a leakage of primary liquid to the exterior of the vessel if the secondary containment barrier extension fails; and a mechanical maintaining system for securing, under the required pressure conditions, the electrical bar to the vessel.

Abstract: A system for removing the residual power of a pressurized water nuclear reactor, includes a reserve of water, a steam generator, wherein the primary water heated by the core either circulates in a forced manner during power operation, or circulates naturally when the primary pump is stopped, and a condenser housed in the containment vessel. The condenser includes a recovery unit for recovering the condensed water and a condenser link to ensure the circulation of water in a closed circuit between the reserve and the condenser. The system further includes a device for circulating the secondary water between the steam generator and the condenser, the device being activated without an external supply of electrical energy, when an operating parameter characteristic of excessive heating of the primary water reaches a certain threshold, such that the primary water heated by the core and circulating in the steam generator vaporizes the secondary water.

Abstract: A nuclear reactor includes a plurality of mechanisms (11) that drive the contact members (9) that control the reactivity, of the core. Each mechanism includes a driving member (21) including a driving part (23) forming one out of a screw or a nut, a member (27) for applying a rotary torque of the rotor (19) to the driving member (21), a driven member (29) translationally connected to one of the control members (9) and including the other out of screw and a nut; and a member (33) that is selectively mobile between a position of blocking the driving member (21) and a position of releasing the driving member (21).

Abstract: A nuclear reactor is provided that includes a vessel; a core provided in the vessel; at least one plate heat exchanger provided in the vessel, with at least one duct for supplying a secondary fluid to the heat exchanger and a duct for discharging the secondary fluid from the heat exchanger, the discharge duct extending through the vessel. The nuclear reactor comprises a device for attaching the heat exchanger to an area of the vessel through which the discharge duct extends.

Abstract: A plate heat exchanger for homogenous fluid flows between ducts includes primary passages and secondary passages. The secondary passages include a first group fluidly connecting a first secondary supply collector to a secondary discharge collector. The first group of secondary passages have a first total passage section at half-length between the first secondary supply collector and the secondary discharge collector. The first group of secondary passages have a second total passage section at the output of the first secondary supply collector of less than 10% of the first total passage section of the first group of secondary passages.

Abstract: A system for removing the residual power of a pressurised water nuclear reactor, includes a reserve of water, a steam generator, wherein the primary water heated by the core either circulates in a forced manner during power operation, or circulates naturally when the primary pump is stopped, and a condenser housed in the containment vessel. The condenser includes a recovery unit for recovering the condensed water and a condenser link to ensure the circulation of water in a closed circuit between the reserve and the condenser. The system further includes a device for circulating the secondary water between the steam generator and the condenser, the device being activated without an external supply of electrical energy, when an operating parameter characteristic of excessive heating of the primary water reaches a certain threshold, such that the primary water heated by the core and circulating in the steam generator vaporises the secondary water.

Abstract: A system for producing and distributing electrical energy over an electrical network of a geographic area, includes a first entity for generating electrical energy, which operates in a steady state and generates at least a portion of the electrical energy; a second entity for intermittently generating the electrical energy from renewable energy; a third entity, which is capable of operating in a load-following state, the system being sized such that the profile of the change in total energy potential of the geographic area over the span of one year, corresponding to the sum of the profile of the change in the amount of electrical energy distributed by the main entity and the profile of the change in the amount of electrical energy generated by the second entity over the span of one year, is less than the profile of the change in the demand for electrical energy of the network.

Abstract: The system according to the invention prevents the effect of turbulence due to exhaust of gases via chimney from propulsion machines on aircraft carriers (1). It consists of creating internal circulation of water by means of a scope (3) of a circulation pump (4), an inlet chamber (6) in which exhaust gases from the thermodynamic machines of the Ship empty. Water nozzles are placed in this inlet chamber (6). The resulting mixture is evacuated via a pipe (7) and a mixing tube (8) terminating outside the ship, to the stern thereof, just above the water line. Application to aircraft carriers.

Abstract: The balancing device makes it easy to balance low and medium tonnage ships without needing to use high power. It comprises mainly one or several trains of moving masses mounted on a U track of which the side branches are parallel to the side walls of the ship, the central segment being perpendicular to the center line of the ship. Two drive wheels placed inside the turning points of the U enable driving of the train of moving mass. Application to low and medium tonnage ships.

Abstract: The device makes it possible to stabilize high tonnage ship, when several of them are used. Mainly, it comprises a train of mobile lead masses (12), completed at each end by a pair of jaws (16) pressing against the lateral rails of a housing (3). A single cable (2) serves to pull the train and to control the release of the jaws (16). The control means for displacement and for cable tension are placed on one side of the ship. The winch (20) of one device can be coupled to the winch of an adjacent device, thus allowing compensation should a device fail. Application refers to the stabilization of high tonnage ships, such as aircraft carriers.

Abstract: The device makes it possible to stabilise high tonnage ships, when several of them are used.

Abstract: The asynchronous discoidal electric motor has stator (1A, 1B) windings (13) and radial rotor bars (2) embedded in notches (11, 22) opened by a very narrow slit (11, 21). These slits (11, 21) and notches (12, 22) may be machined electrochemically using a wire. Application to asynchronous discoidal electric motors with winding embedded in the stator and with a cartwheel structure on the rotor.

Abstract: The axial pump makes it possible to deliver a fluid having a double gaseous-liquid phase at high flow rates. It is constituted by a one-piece rotor comprising a hollow shaft (10) onto which are shrunk pulsating systems (12). This rotor is placed within a body (2) constituted by a stack of washers (3) within which are fixed straighteners (14). Each straightener is constituted by two half-straighteners, so as to permit the installation of each straightener around the rotor. Everything is sealed by end flanges on which the rotor is mounted in rotary manner. The pulsating systems (12) can also be machined on the outer surface of the body (10).