Abstract: The water flowing in a nuclear reactor is analyzed, while the reactor is in operation, by conducting water from the reactor vessel substantially without reduction in pressure or temperature past test surfaces (e.g. tubes) with different electrochemical potentials relative to the reactor water. Deposits formed on the test surfaces, which are substantially caused by colloidal particles in the water, are examined, preferably with regard to radioactive content.

Abstract: A method and an apparatus for feed-water control in a steam generating plant such as a boiling water nuclear reactor having motor-driven feed-water pumps and turbine-driven feed-water pumps for supplying feed-water to a steam generator, in which the feed-water flow through the turbine-driven feed-water pumps is controlled to be maintained constant, while reducing the recirculation flow discharged from the turbine-driven feed-water pumps and fed back to the inlet thereof, so as to reduce the amount of feed-water supplied to the steam generator by the motor-driven feed-water pumps, whereby variation of water level in the steam generator during switching between the two kinds of feed-water pumps is suppressed.

Abstract: An elongated canister (86) into which the fuel rods (42) from, preferably, two nuclear fuel assemblies (32) are inserted from above, and then passively consolidated within the canister such that at the lower end (88) the effective density of the rods is approximately double that of each fuel assembly. The canister includes a straight vertical back panel (308), side panels (312) having straight upper (310) and inwardly oriented, tapered lower portions (314), and a front panel (300) having straight upper (302) and tapered lower (304) portions. Spaced apart plates (90) extending between the front and back panels, and a temporary base (320), preferably titled from front to back, in conjunction with the generally funnel-shaped canister, operate to urge the rods close together while the rod pattern is transformed from square to triangular pitch.

Abstract: A nuclear reactor fuel rod includes a fuel tube and an improved end plug assembly having a pair of hollow end plugs which seal opposite ends of the fuel tube. Each end plug has an outer body portion with an outside diameter substantially the same as the outside diameter of the fuel tube and an inner body portion of reduced diameter inserted into an end of the tube. Each plug has a cavity defined therein which increases the space within the rod for fission gas expansion. An outer region of the cavity within the outer body portion of the end plug is undercut relative to an inner region of the cavity within the inner body portion of the plug. One of the end plugs also has an insert fitted into its inner body portion which prevents fuel chips from falling into the cavity of the end plug. A slot is formed axially in a side wall of the insert which allows communication of gas from the tube into the cavity of the end plug.

Abstract: An isolation and protection device is suitable for being inserted and deployed inside tubing, in order, in particular, to collect swarf and foreign bodies during work on tubing which must be kept under a controlled gas atmosphere, or to act as a flow plug or as a heat shield.

Abstract: Device for fixing a fuel assembly to the lower core plate of a nuclear reactor, comprising a fastening element (23) fixed to the lower core plate (18), in the central part of the opening (19) in this plate (18) corresponding to the assembly, an expandable sleeve fixed to the lower end (3) of the assembly in its central part, a guide tube (10) passing through the assembly in its central part in the axial direction, a rod (25) mounted for sliding movement in the tube (10) and fixed to an oval locking knob (38), and a socket (26) fixed to the upper end of the bar (25) and having a gripping surface for a lifting tool. The fastening element has an axial opening (31) for engagement of the expandable sleeve. The bar (25) and the socket (26) allow displacement of the oval knob (38) between service and out-of-service positions in which the latter spreads the expandable sleeve inside the opening (31) in order to fix the assembly.

Abstract: A cylinder driving apparatus, wherein a head chamber and a rod chamber of a cylinder for driving a load upwardly and downwardly are communicated with a pressure accumulation tank by way of a balance pipeway equipped with an electromagnetic proportional flow control valve and a recycling pipeway equipped with a pressure control valve mechanism, respectively, and the load is driven by feeding air at reduced pressure to the rod chamber or discharging it to the external atmosphere by way of the pressure control valve mechanism while applying air pressure into the head chamber of the cylinder against the load by way of the electromagnetic proportional flow control valve for adjusting the driving speed.

Abstract: A mechanical drive system (10) for moving alternate nuclear reactor fuel rods (14) within the nuclear reactor core (12) and relative to the remaining stationary nuclear reactor fuel rods (16) so as to axially displace the movable fuel rods (14), and enriched and natural uranium fuel zones defined therein, relative to similarly defined enriched and natural uranium fuel zones within the stationary fuel rods (16) in order to optimize utilization of excess or free neutrons produced within the nuclear reactor core within a fuel cycle. The nuclear reactor fuel rods (14, 16) all have a length which is less than that of standard-sized nuclear reactor fuel rods, and therefore, a plenum chamber (20) is able to be defined between an upper core plate (22) and an auxiliary upper core plate (24).

Abstract: Control cluster guide devices, for light water cooled nuclear reactors, including housings. The reactor includes means outside the core for guiding control clusters (7) during their movements.The housings (12) are associated respectively with the several control clusters (7) and comprise plates which ensure discontinuous guidance at intermediate levels for the individual pencils and an associated spider, each housing including for continuous of the individual pencils, tubes which connect two tube plates for the pencils to pass through, which are proper to the housing, the one terminating it and the other forming a positioning flange on the core plate.

Abstract: A multi-function magnetic jack control drive mechanism for controlling a nuclear reactor is provided. The mechanism includes an elongate pressure housing in which a plurality of closely spaced drive rods are located. Each drive rod is connected to a rod which is insertable in the reactor core. An electromechanical stationary latch device is provided which is actuatable to hold each drive rod stationary with respect to the pressure housing. An electromechanical movable latch device is also provided for each one of the drive rods. Each movable latch device is provided with a base and is actuatable to hold a respective drive rod stationary with respect to the base. An electromechanical lift device is further provided for each base which is actuatable for moving a respective base longitudinally along the pressure housing. In this manner, one or more drive rods can be moved in the pressure housing by sequentially and repetitively operating the electromechanical devices.

Abstract: A device which controls coolant flow through a nuclear reactor assembly comprises a baffle means at the exit end of said assembly having a plurality of orifices, and a bimetallic member in operative relation to the baffle means such that at increased temperatures said bimetallic member deforms to unblock some of said orifices and allow increased coolant flow therethrough.

Abstract: Sealing device for the drive shaft (27) of a high pressure fluid pump comprising a system of seals (33, 34, 35) at least one of which (33) is a hydrostatic seal. Between this hydrostatic seal (33) and the interior of the volute (21) is disposed an auxiliary seal (45) of the mechanical type. The auxiliary seal (45) separates two chambers (46a) and (46b) which can be brought into communication or isolated by a system of pipes (47) on which a valve (48) is disposed. The invention is particularly applicable to the primary pumps of a pressurized water nuclear reactor.

Abstract: A microprocessor (158) based control for a hydraulic pump motor (26) used to control the operation of a mast assembly (12) on a work vehicle (10). The speed of each function performed by the mast assembly (12) is programmable to one of a plurality of possible speeds. An additional function for performing lifting of the mast (12) produces incremental speed variations relative to incremental movement of a corresponding control lever (14). Each of the functions have a predetermined priority such that attempted operation of multiple functions results in a pump motor speed requested by the function of highest priority.

Abstract: A control rod drive uses gravitational forces to insert one or more control rods upwardly into a reactor core from beneath the reactor core under emergency conditions. The preferred control rod drive includes a vertically movable weight and a mechanism operatively associating the weight with the control rod so that downward movement of the weight is translated into upward movement of the control rod. The preferred control rod drive further includes an electric motor for driving the control rods under normal conditions, an electrically actuated clutch which automatically disengages the motor during a power failure and a decelerator for bringing the control rod to a controlled stop when it is inserted under emergency conditions into a reactor core.

Abstract: A control system for a hydraulic circuit including at least first and second variable displacement volume type hydraulic pumps, at least first and second hydraulic actuators driven by the pumps, and valves for controlling hydraulic connections between the pumps and the actuators. The control system includes a device for deciding the order of priority of hydraulic connections between the first actuator and the first and second hydraulic pumps and the order of priority of hydraulic connections between the second pump and the first and second actuators. A first sensor is provided for sensing maximization of the displacement volume of the first pump, sensing that the displacement volume of the second pump has become substantially zero. A device decides target displacement volumes of the first and second pumps based on information supplied at least by the priority order deciding device and first and second sensor.

Abstract: A device for positioning a member so as to face each of a plurality of perforations arranged in a given grid in a plate, especially for the inspection of the tubes of a steam generator in a nuclear power station. It comprises a body having at least two attachment members for fastening the device in the perforations. The device is rotatable around one or the other of these attachment members so as to displace it on the plate, and has a support carrying the member and pivotable with respect to the body in order to bring the member into a position facing several perforations without displacing the device.

Abstract: A hydrostatic drive arrangement for a vehicle providing synchronized rotation of a pair of output drive shafts including a pair of transmissions each having a closed loop hydraulic circuit hydraulically interconnecting a variable displacement pump and a hydraulic motor, and a pressure responsive hydraulic synchronizing valve disposed between the hydraulic circuits and normally open to permit interflow of fluid between the hydraulic circuits with the valve being responsive to fluid pressure in one of the hydraulic circuits to restrict flow therethrough when the fluid pressure in the one hydraulic circuit exceeds a predetermined value.

Abstract: A hydrostatic seal for sealing an annular gap between two flat substantially horizontal coplanar surfaces, and particularly a gap in a nuclear reactor cavity which comprises a generally flat annular plate of a width sufficient to span the gap between the two surfaces, compressible annular sealing rings or gaskets disposed on the bottom surface of the flat annular plate for sealingly engaging the two flat surfaces when a downward force is exerted on the plate, and a plurality of fastening arrangements, distributed along the center line of the plate, for releasably fastening the plate in a position to span the gap and exert a downward force on the plate.

Abstract: A control system for overpressure protection of the reactor coolant boundary (14) in a nuclear power plant, comprising a pressure relief line (18a) having a power operated relief valve (24a) controlled by a circuit responsive to the condition of the reactor coolant and a control logic. The circuit includes a mode selector switch (80) having a NORMAL position (82) for establishing a full power overpressure relief valve setpoint (62) and a LTOP position (84) for establishing a low temperature overpressure relief setpoint (58). The control system logic opens the relief valve (24a) when (a) the mode switch is in the NORMAL position and the coolant pressure exceeds the full power setpoint (62), or (b) when the mode switch is in the LTOP position, the coolant temperature is less than a preselected value (52) and the coolant pressure exceeds the LTOP setpoint (58).

Abstract: A hydraulic apparatus for converting hydraulic pressure into mechanical movement for operating a tool or other device, operated by a pump block having a bore therein and a moveable plunger disposed within said bore. A cylinder is disposed over the pump block. The cylinder is captively held over the pump block and is moveable with respect thereto along the common axis. A fluid reservoir is defined between the cylinder and the pump block, and contains the hydraulic fluid. The plunger is operated by a pair of moveable arms secured to the apparatus and causes pressure to build in the fluid in an inlet chamber which communicates between the pump block and the cylinder. A pressure control valve is mounted adjacent the pump block and limits the hydraulic pressure which may be applied in the system. A release valve and apparatus is provided for releasing the hydraulic pressure and returning it to the reservoir.