Abstract: An aircraft includes a fuselage and a fixed flying surface having two wings, and a cradle-shaped ventral fairing at the crossover of the latter with the flying surface and provided with two longitudinal flanges climbing laterally along the fuselage and being provided with an opening for the passage with play of the corresponding wing to form a first peripheral slot around the ventral fairing and a second peripheral slot around each wing. An elongate seal is fixed to the periphery of the ventral fairing and to the periphery of each opening, so at to shut off the first and second slots, respectively. The seal includes a longitudinal elastic end lip applied, via the inner face of its free end, respectively against the fuselage or the flying surface and a longitudinal leaktightness member, carried by the inner face of the seal set back with respect to the end lip and also able to be applied against the fuselage or flying surface, respectively.

Abstract: Aircraft landing gear assemblies having multiple deployed static positions. In one embodiment, a landing gear assembly usable with a wing includes a wheel truck and a strut having a first strut end and a second strut end. The first strut end is configured to be pivotally connected to the wing, and the second strut end is configured to be pivotally connected to the wheel truck. In one aspect of this embodiment, the strut is configured to be connected to a first brace extending between the strut and the wing for positioning the wheel truck in a first deployed static position. In another aspect of this embodiment, the strut is further configured to be connected to a second brace extending between the strut and the wing for positioning the wheel truck in a second deployed static position different than the first deployed static position.

Abstract: An experimental machine (1) for producing low-temperature nuclear fusion reactions, wherein an ion source (3) feeds a flux of positive deuterium ions to a reaction chamber (2) housing a target (5) defined by active elements (30, 31) and by an aggregate of metal sulfate hydrated with heavy water; a pumping assembly (4) being provided to maintain a vacuum in the reaction chamber (2); and the reaction chamber (2) having an accelerating device (10) for accelerating the positive deuterium ions, and which generates an electric field inside the reaction chamber (2) to convey and accelerate the deuterium ions against the active element of the target (5) in such a manner as to initiate nuclear fusion reactions between the incident deuterium ions and some of the atoms of the active element.

Abstract: A method for manufacturing a control rod of a nuclear reactor, the control rod having a blade including neutron absorbers and a sheath, a tie rod for fixing the blade, a handle and a lower-blade fixed to the tie rod and the blade. The method includes a first step for cutting weep holes for water to cool the neutron absorbers in the sheath and cutting a periphery of the sheath, a second step for bending the sheath cut in the first step to a C-shape, a third step for inserting the neutron absorbers in a bent portion of the sheath formed by bending in the second step, a fourth step for successively welding the blade to the tie rod, the blade to the handle and the blade to the lower-blade, and a fifth step for finishing portions welded in the fourth step.

Abstract: A pilot controlled relative analgesia system in which there would be located in the aircraft, possibly in the storage or luggage portion of the aircraft below the passenger deck, a pressurized source of gas capable of immobilizing individuals by placing them in a semi-conscious state, such gas including but not limited to nitrous oxide, and a control system positioned in the flight crew compartment either manual or electronic in nature for the deployment of the gas into the passenger portion of the airplane when a flight emergency in the form of a possible hijacking exists. The concentration level of nitrous oxide would be achieved and maintained until the flight crew with self-contained breathing apparatus could enter the passenger cabin and restrain and secure the appropriate individuals or alternatively maintain the level of nitrous oxide gas until the plane could be safely landed.

Abstract: A guide tube inspection camera fixture for inspecting internal surfaces of nuclear reactor control rod guide tubes is provided. In an exemplary embodiment, the guide tube camera fixture includes a base plate, a unit-body tower having a first end and a second end, and a support bracket coupled to the unit-body tower. The unit-body tower is coupled to the base plate, and the support bracket is configured to support an inspection camera.

Abstract: An opening portion 3 is produced by cutting a recirculating piping 72 connected to a recirculating nozzle 2 of a reactor pressure vessel 1. A repairing device is brought into an annulus 10 of the reactor pressure vessel 1 from the opening 3, thereby repairing the annulus 10.

Abstract: The invention comprises an apparatus to repair a fuel assembly to accomplish a load lift comprising a main body, an upper section, a connection configured between the main body and the upper section and a lower section connected to the main body. The invention also comprises an inner adjusting body with a top and a bottom wherein a mandrel is connected to the bottom, the mandrel configured to actuate a holding body upon actuation of the inner adjusting body, the inner adjusting body positioned inside the upper section, the main body and the lower section and an actuator connected to the upper section, the actuator configured to actuate the inner adjusting body.

Abstract: The invention concerns a remote-controlled flying machine, in particular for surveillance and inspection, capable of hovering and comprising a spherical open-worked resistant shroud integral with a cylindrical fairing wherein rotates a propeller powered by an engine housed in a fuselage secured to the fairing with radial arms and straightening vanes.

Abstract: A reactor power output measurement device measuring a neutron flux with a traversing incore probe (TIP) traversing in a vertical direction in a core of a reactor, and calibrating a detection sensitivity of a local power range monitor based on a measured neutron flux distribution in the axial direction inside the reactor, which is provided with an integrated control device 9 for transmitting control data to all of TIP drive control devices 13a through 13e and performing control/monitor of all of detector drive systems 17a through 17e.

Abstract: An inspection apparatus for inspecting jet pump beams of nuclear reactors is provided. The inspection apparatus includes a base straddlingly mountable on a jet pump beam. The base includes a beam bolt opening sized to receive a jet pump beam bolt. A first transducer holder is coupled to a first side portion of the base, and a second transducer holder coupled to a second side portion of the base. The first side portion is opposed to the second side portion. Each holder includes an adjustment cylinder configured to contact the jet pump beam when activated.

Abstract: An apparatus, transfer cask, system, and method for defueling a nuclear reactor and transferring spent nuclear fuel from a spent nuclear fuel pool to a storage cask for long terms storage. In one aspect, the invention is an apparatus for use in transferring a canister of spent nuclear fuel from a transfer cask to a storage cask, the apparatus comprising a radiation absorbing shield surrounding a portion of a hole through which the canister can pass; means for securing the apparatus to the top surface of the storage cask; means for securing the bottom surface of the transfer cask to the apparatus; wherein the transfer cask securing means and the storage cask securing means are positioned on the apparatus so that when the apparatus is secured to both the transfer cask and the storage cask.

Abstract: A method of carrying out a reactor vessel according to the present invention includes removing an overhead traveling crane in a reactor containment vessel of a pressurized water reactor. Alternatively, in an area where an overhead traveling crane is installed, operating the overhead traveling crane to move aside for creating a space, through which the reactor vessel is able to pass. Then the reactor vessel is carried out through an opening provided in a top portion of the reactor containment vessel. With the present method, the reactor vessel of the pressurized water reactor can be carried out in a short period of time with high efficiency.

Abstract: The assembly apparatus comprises a frame for supporting the straps of the first set of straps in mutually parallel positions, clamping and engagement for clamping on each of the straps of a second set of straps in succession and for engaging them with the straps of the first set in position in the support frame, and at least one comb that is movable between a disengaged position and a position in which it engages each of the straps of the first set.

Abstract: When carrying the large structure out through an aperture portion provided at a roof of a reactor building, a chamber for covering the aperture is provided at the roof so that work of providing the chamber for covering the aperture portion can be performed independent of other work performed in the reactor building, before at least a part of work of using a roof crane and at least a part work of handling fuel assemblies in the reactor building.

Abstract: A reduced pressure drop debris filter bottom nozzle for use in a fuel assembly of a nuclear reactor includes a plate member formed with a plurality of first flow holes and a plurality of second flow holes. The first flow holes are oblong in cross section and may be of an oval configuration. The first flow holes each have in cross section a major axis and a minor axis, the major axis being longer than the minor axis. The second flow holes are circular in cross section and may have a diameter substantially equal to the minor axis of the first flow holes. The bottom nozzle also features support ligaments that extend between the first flow holes and that are axially aligned with fuel rods within the fuel assembly.

Abstract: The measurement device comprises a real-time measurement-signal acquisition module (25) and means (23, 24) for connecting the cables for picking up the voltage from electrical windings for measuring the movement of the control rods to the acquisition module (25), in order to deliver, to the acquisition module (25), voltage signals corresponding to the voltage induced in the windings while the control rods are being dropped. The signal acquisition module (25) is thus permanently connected to the voltage-signal pickup cables (29) and the signals relating to the set of nuclear reactor control rods may be recorded simultaneously. Means (26, 27) for using the voltage signals delivered by the acquisition system (25) allow the drop times of the control rods to be determined.

Abstract: There is provided a nuclear power plant having a steam turbine controller. The nuclear power plant includes a main steam supply system and a turbine by-pass system. The main steam supply system guides steam from heat generated by the nuclear reactor to a steam turbine. The turbine by-pass system is branched from the main steam supply system at a main steam header. A main steam control valve is equipped with the main steam supply system and adjusts steam pressure in the main steam supply system supplied to the steam turbine. A turbine by-pass valve is used to by-pass steam to the turbine by-pass system. A regulating controller generates first and second opening/closing signals for the main steam control valve and the turbine by-pass valve, and an ON-OFF controller generates a third opening/closing signal for the turbine by-pass valve. The third opening/closing signal has priority over the second opening/closing signal.

Abstract: An air vehicle, such as an aircraft, an unmanned air vehicle, a missile, or an aero bomb that has a fuselage and two main wings each of which has a left side wing and a right side wing. Both of the main wings are rotatably mounted on the fuselage via one or two pivots or hollow turrets so that both of them can be yawed during flight to optimize flying efficiency under various flying conditions.

Abstract: For the redistribution of a coolant flow from a first region into a second region, in particular in boiling-water-reactor fuel elements having an eccentrically disposed water passage, a fuel-rod bundle is constructed in a mirror symmetry manner relative to a diagonal. A distance between adjacent fuel rods increases monotonically in particular along a diagonal. In addition, a fuel-rod bundle as an entity may be offset eccentrically along the diagonal. To compensate for asymmetry in the reactor core, a redistribution of coolant is provided which is advantageous in pressurized-water-reactor fuel elements.