Abstract: A control rod drive system (CRDS) for use in a nuclear reactor. In one embodiment, the system generally includes a drive rod mechanically coupled to a control rod drive mechanism (CRDM) operable to linearly raise and lower the drive rod along a vertical axis, a rod cluster control assembly (RCCA) comprising a plurality of control rods insertable into a nuclear fuel core, and a drive rod extension (DRE) releasably coupled at opposing ends to the drive rod and RCCA. The CRDM includes an electromagnet which operates to couple the CRDM to DRE. In the event of a power loss or SCRAM, the CRDM may be configured to remotely uncouple the RCCA from the DRE without releasing or dropping the drive rod which remains engaged with the CRDM and in position.

Abstract: A control rod drive system (CRDS) for use in a nuclear reactor. In one embodiment, the system generally includes a drive rod mechanically coupled to a control rod drive mechanism (CRDM) operable to linearly raise and lower the drive rod along a vertical axis, a rod cluster control assembly (RCCA) comprising a plurality of control rods insertable into a nuclear fuel core, and a drive rod extension (DRE) releasably coupled at opposing ends to the drive rod and RCCA. The CRDM includes an electromagnet which operates to couple the CRDM to DRE. In the event of a power loss or SCRAM, the CRDM may be configured to remotely uncouple the RCCA from the DRE without releasing or dropping the drive rod which remains engaged with the CRDM and in position.

Abstract: A control rod drive system (CRDS) for use in a nuclear reactor. In one embodiment, the system generally includes a drive rod mechanically coupled to a control rod drive mechanism (CRDM) operable to linearly raise and lower the drive rod along a vertical axis, a rod cluster control assembly (RCCA) comprising a plurality of control rods insertable into a nuclear fuel core, and a drive rod extension (DRE) releasably coupled at opposing ends to the drive rod and RCCA. The CRDM includes an electromagnet which operates to couple the CRDM to DRE. In the event of a power loss or SCRAM, the CRDM may be configured to remotely uncouple the RCCA from the DRE without releasing or dropping the drive rod which remains engaged with the CRDM and in position.

Abstract: Systems and methods of monitoring a rod control system of a nuclear power plant, including calculating impedance of at least one coil of a rod movement mechanism non-intrusively while the system is operating, comparing a measured impedance to a reference impedance, and determining if the measured impedance deviates from the reference impedance value by a predetermined amount to indicate degradation of the rod control system.

Abstract: A control rod drive mechanism (CRDM) configured to latch onto the lifting rod of a control rod assembly and including separate latch engagement and latch holding mechanisms. A CRDM configured to latch onto the lifting rod of a control rod assembly and including a four-bar linkage closing the latch, wherein the four-bar linkage biases the latch closed under force of gravity.

Abstract: Systems for controlling and protesting nuclear reactors. A drive of an emergency safety rod of a nuclear reactor includes an electric drive, a reduction gear, and a rack-and-pinion gear. The electric drive contains a contactless electric motor based on permanent magnets, which is installed in the housing of the electric drive with a motor rotor position sensor, and a reduction gear for changing the rate of rotation of the electric drive. A toothed rack is installed along the axis of the rack-and-pinion gear in order to provide for the reciprocating motion of a system absorber rod connected thereto. A toothed electromagnetic clutch having a contactless current supply is installed on an inner shaft of the rack-and-pinion gear, enabling the rigid and simultaneous mechanical coupling of half-couplings, and the drive contains a reverse-motion coupling, a rack-separation spring and toothed rack position sensors.

Abstract: A control rod drive mechanism (CRDM) configured to latch onto the lifting rod of a control rod assembly and including separate latch engagement and latch holding mechanisms. A CRDM configured to latch onto the lifting rod of a control rod assembly and including a four-bar linkage closing the latch, wherein the four-bar linkage biases the latch closed under force of gravity.

Abstract: A control rod drive mechanism (CRDM) configured to latch onto the lifting rod of a control rod assembly and including separate latch engagement and latch holding mechanisms. A CRDM configured to latch onto the lifting rod of a control rod assembly and including a four-bar linkage closing the latch, wherein the four-bar linkage biases the latch closed under force of gravity.

Abstract: A nuclear reactor control rod drive assembly includes a control rod drive mechanism coupled to a drive shaft and operable to bi-directionally urge the drive shaft through a portion of an inner volume of a reactor vessel at a first force; a control rod manifold coupled to the drive shaft; a plurality of control rods coupled to the control rod manifold, the plurality of control rods adjustable among a plurality of positions within the inner volume of the reactor vessel based on operation of the control rod drive mechanism; and at least one variable strength joint positioned between the control rod drive mechanism and the plurality of control rods.

Abstract: A control rod drive system for a nuclear reactor that employs hydraulic cylinders to operate a conventional plunger/gripper drive system to incrementally move control rods into and out of the core of a reactor. The pressure differential for driving hydraulic pistons within the cylinders is obtained from the difference in pressure between the outside and inside of the core barrel of the reactor and control of the pistons is obtained from external solenoids attached to the reactor control system. The external solenoids regulate a charging pump feed to Poppet valves that control the hydraulic feed to the cylinders. A hydraulic piston/cylinder drive is also provided for the shutdown rods which operate in either an all in or out of the core condition.

Abstract: A fine motion control rod drive mechanism handling apparatus attaches a fine motion control rod drive mechanism having a control rod drive mechanism body, a spool piece, a motor bracket and a motor unit to a reactor pressure vessel, and detaches it from the reactor pressure vessel. The fine motion control rod drive mechanism handling apparatus is provided with a bolt wrench assembly, a motor unit attachment mounted to the bolt wrench assembly, for meshing a first gear of a first gear coupling on a spool piece side with a second gear of a second gear coupling on a motor unit side, and a rotation mechanism mounted to the bolt wrench assembly, for rotating the motor unit attachment.

Abstract: A control rod drive mechanism (CRDM) comprises a lead screw, a motor threadedly coupled with the lead screw to linearly drive the lead screw in an insertion direction or an opposite withdrawal direction, a latch assembly secured with the lead screw and configured to (i) latch to a connecting rod and to (ii) unlatch from the connecting rod, the connecting rod being free to move in the insertion direction when unlatched, and a release mechanism configured to selectively unlatch the latch assembly from the connecting rod.

Abstract: An apparatus or system that may incorporate a single component to connect the control rod blade to the control rod drive system (CRD) of a Nordic-type of BWR. The apparatus or system may eliminate the need of using multiple components to connect the control rod blade with the CRD.

Abstract: An embodiment of the present invention takes the form of an apparatus or system that may incorporate a single component to connect the control rod blade to the control rod drive system (CRD) of a Nordic-type of BWR. An embodiment of the present invention may eliminate the need of using multiple components to connect the control rod blade with the CRD.

Abstract: There is provided a semiconductor storage device and portable electronic equipment including a nonvolatile memory element that can easily be miniaturized. The semiconductor storage device includes a memory cell array 21 in which a plurality of memory elements 1 are arranged and a write state machine 32. The memory element 1 includes a gate electrode 104 formed on a semiconductor layer 102 via a gate insulator 103, a channel region arranged below the gate electrode 104, diffusion regions 107a, 107b that are located on both sides of the channel region and have a conductive type opposite to that of the channel region and memory function bodies 109 that are located on both sides of the gate electrode 104 and have a function to retain electric charge. The write state machine 32 can selectively prevent program and erase of data in the memory elements within a predetermined range.

Abstract: A device for handling a guide tube assembly. The assembly has an upper tube and a lower tube in each of which there are fixed horizontal guide plates arranged such that they are spaced apart in an axial direction. The handling device itself includes a gripper having a tubular body and two opposing arms located at one end of the tubular body and moveable between a retracted position and a deployed position, the arms bearing against a lower surface of a contacted guide plate when in the deployed position. A control member is located at an opposite end of the tubular body for controlling the arms. The length of the tubular body of the gripper selected to be: a) greater than the distance between an upper end of the upper tube and a first guide plate of the lower tube; and b) less than the distance between the upper end of the upper tube and a third guide plate of the second tube.

Abstract: A lifting support for a boiling water reactor nuclear fuel assembly comprising a grappling head configured to allow attachment to a lifting device, a body with an upper end and a lower end, the upper end connected to the grappling head, the body configured to be inserted into a water channel of a boiling water reactor nuclear fuel assembly, and an end connected to the lower end, the end configured to be accepted by the nuclear fuel assembly.

Abstract: A control rod coupling assembly for coupling a nuclear reactor control rod to a control rod drive mechanism is disclosed. The control rod drive mechanism includes an index tube and a bayonet head. The control rod includes blades and a tube at the intersection of the blades. The control rod coupling assembly includes a bayonet socket configured to receive the bayonet head, a shaft extending from the bayonet socket through the control rod, and a handle extending from the shaft, the handle movable to rotate the bayonet socket without rotation of the control rod.

Abstract: To reduce the manufacturing processes of a control rod and shorten the time required for manufacturing a control rod, for the lower part support member 7, the thin parts 11A and 11B are formed in the neighborhood of each of the left and right sides of the window 8. In the left and right sides of the pull-up handle 9, the grooves 17A and 17B are formed respectively. The groove 17B is deeper than the groove 17A. The thin part 11A is fitted into the groove 17A and the thin part 11B is fitted into the groove 17B. The gap formed between the end of the thin part 11B and the bottom of the groove 17B is larger than the gap formed between the end of the thin part 11A and the bottom of the groove 17A. Therefore, the thin part 11A can be simply fitted into the groove 17A.

Abstract: A transfer device for moving a poison rod assembly between fuel cells in a nuclear fuel storage facility coupleable to an overhead crane. The poison rod assembly has a plurality of poison rods disposed in rows. The device includes an elongated outer member, an inner member, and a gripper assembly supported by the inner member. The inner member is slidably disposed within the elongated outer member. The overhead crane is coupled to the inner member for sliding said inner member between an upper position and a lower position. An interlock assembly selectively couples the inner member and elongated outer member. Thus, moving the crane, which is coupled to the inner member either moves the inner member relative to the elongated outer member when the interlock is not engaged, or, moves both the inner member and the elongated outer member when the interlock is engaged.

Abstract: A spring set within a control rod guide tube in a nuclear reactor biases a control rod for movement into the reactor core. The spring set includes at least three springs in series, two being under compression and one in tension. The control rod may be displaced downwardly in a direction away from the core by a cable connected at one end to the control rod support element and at its opposite end to a drum. By winding the cable on the drum, energy is stored in the spring set. During a SCRAM, the drum is released, enabling the spring set to rapidly displace the control rod fully into the core.

Abstract: This control rod drive limiter removes the need for piping for extraction drive, increases the reliability of linkage with respect to the control rod, and removes the need of a speed limiter for the control rod, since there is no need to assume that the linkage might be released, thus reducing the building costs.A stop piston 112 is disposed so as to cover a buffer piston 110 and a buffer spring 111 from above, rollers 113 are disposed above this stop piston 112, and the lower end of a piston tube 107 is fixed to a flange 103a in such a manner that the piston tube 107 does not move in the axial and peripheral directions. A collet piston 115, collet fingers 116, and a return spring 117 are disposed between an outer tube 104 and a cylinder tube 105. A guide cap 120 is disposed at the upper end of the outer tube 104. Guide grooves 106c that engage with the rollers 113 are provided in the index tube 106.

Abstract: The control rod (4) carrying absorbing elements (5) contains an operating rod (37) forced upwards by washers (38) and projecting by a push button end (52). When it is decided to uncouple the absorbing elements, the control rod (4) is raised, so that the teeth (62) of ratchets (56) opened out beforehand weigh on the push button (52), lower the operating rod (37) and enable coupling balls (33) to enter a groove (35) on the bottom of the rod, which detaches the pommel (18) carrying the absorbing elements (5). Application to pressurized water nuclear reactors.

Abstract: The device makes it possible to automatically disconnect an absorber fuel rod cluster (6) from its control rod (5) when the pressure and/or temperature within the vessel of the reactor have dropped below a certain value.Use is mainly made of a thermal module (35) located between the attachment head (37) and the locking member (32) in order to form a mobile assembly optionally completed by a barometric module placed beneath the locking member (32).Application to pressurized water nuclear reactors.

Abstract: A window in the control rod for a nuclear reactor has flanges along its opposite sides. A latch handle has slots along its opposite sides. The latch handle is sized and configured such that in a first angular orientation, the latch handle may be received within the plane and peripheral confines of the window and, upon rotation of the latch handle through 90.degree. into a second orientation, engages the slotted sides of the latch handle with the flanges of the window to capture the latch handle within the window while simultaneously enabling linear vertical movement of the latch handle relative to the window. The latch handle is then attached to a shaft for operating a coupling mechanism between the control rod and the control rod drive.

Abstract: A control rod drive having a magnetic coupling device which eliminates the need for packing-type seal assemblies for preventing leakage from the reactor pressure vessel adjacent the spindle. The magnetic coupling device includes a driving rotor and a driven rotor separated by a pressure barrier which forms part of the reactor pressure boundary. The driven rotor and the driving rotor are coupled magnetically so that the driven rotor rotates in response to rotation of said driving rotor, whereby the control rod displaces in response to operation of the drive motor. The driven and driving rotors are each constructed by stacking a plurality of circular magnetic rings concentric with a centerline axis. Each circular ring has multiple poles circumferentially distributed thereon. An anti-rotation device is incorporated to prevent free rotation of the spindle when the drive motor is removed during maintenance operations. The anti-rotation device includes a push rod actuator which penetrates the pressure barrier.

Abstract: A gauge for ensuring that the uncoupling rod of a control rod drive is properly inserted in the center hole of the spud and not in one of the outer lobes, i.e., spud flow holes, which communicate with the center hole. The uncoupling rod is inserted in the spud. Then the gauge is placed on top of the spud with a centering ring protruding into the spud. The uncoupling rod is correctly installed if it is free to slide inside the gauge and the spud. The gauge is also provided with a ring to protect the spud during transfer of the control rod drive.

Abstract: A control rod driving system for controlling a reactor core disposed in a reactor pressure vessel comprises a control rod and a control rod driving mechanism. The control rod has an inner hollow portion extending in a longitudinal direction thereof and the control rod driving mechanism is inserted into the inner hollow portion of the control rod for driving the control rod.

Abstract: A control rod handling apparatus and method for exchanging a control rod connected to a control rod drive mechanism by a bayonet coupling. The control rod handling apparatus comprises a member or connection to a fuel exchange apparatus, a fixing part having guides to be seated at the top face of an upper grid plate in a reactor vessel and to e supported by the upper rid plate, a body provided at the lower part of the fixing part, a control rod handling part having a control rod grasping instrument provided at the bottom part of the body, a fuel support piece handling part having a fuel support piece grasping instrument and means for positioning the fuel support piece grasping instrument, which is provided outside the control rod handling part, means for vertically moving the fuel support piece handling part along with the outside of the control rod handling part, and means for rotating the control rod handling part, the fuel support piece handling part, and the means for vertical motion.

Abstract: In a boiling-water nuclear reactor, a core-control assembly comprises a control rod, a fuel support, a control-rod guide tube, a control-rod drive, and a control-rod-drive housing. The fuel support is welded to the control-rod guide tube. To remove the control-rod drive, the reactor vessel can be opened and the adjacent fuel bundles removed from the fuel support. Then the control-rod can be rotated after clearing the fuel support. The control rod is then rotated to decouple its bayonet connection to the control-rod drive. The control rod can then be lifted out of the reactor. This arrangement allows a control rod to be replaced without handling of the fuel support. In addition, the fuel support can be more securely installed since it does not need to be removed.

Abstract: A control rod drive assembly includes a translatable drive tube joined to a control rod by a coupling having complementary screw threads. A purge flow is channeled between the screw threads to flush away debris therebetween for preventing galling of the threads during operation.

Abstract: A control rod is selectively positioned in a nuclear reactor core inside a reactor pressure vessel by a drive assembly. The assembly includes a flexible cable releasably joined to the control rod by a coupling. A drive is joined to the cable for selectively advancing and retracting in opposite directions the cable for selectively positioning the control rod in the reactor core. In exemplary embodiments, the drive and cable may be disposed above or below the reactor core. In another embodiment, a pressurized driving fluid may be used to additionally position the control rod within the reactor core.

Abstract: For each of the demountable fuel rods (23), the end part of the protective tube (27), which end part is open towards the exterior, has a reduced diameter over a certain length and comprises at least one seating which does or does not pass through its wall. The end part of the fuel rod (23) is integral with a ferrule (34) which is coaxial with the fuel rod and which surrounds the assembly rod (31) of the fuel rod over part of its length. The ferrule (34) is engaged on the reduced-diameter part of the protective tube (27) when the rod (31) is screwed into the bore (28) of the protective tube. Locking against rotation of the fuel rod in the protective tube (27) is ensured by deformation of the ferrule (34) within the openings of the end part of the protective tube (27). The fuel rod is demounted by exerting a torque on it by way of an engagement surface (37), for example of prismatic form, located near the end of the fuel rod.

Abstract: A reconstitutable control assembly has a spider structure which supports control rods by detachable attachment joints. Each attachment joint includes a hollow connecting finger on the spider structure and an elongated detachable split upper end plug on each control rod. The split upper end plug includes a pair of separate upper and lower plug portions. The upper plug portion has upper, middle and lower sections, whereas the lower plug portion has upper, middle and lower segments. The upper section of the upper plug portion is rigidly attached to the connecting finger on the spider structure, whereas the lower segment of the lower plug portion is rigidly connected to the control rod. Also, the lower section of the upper plug portion and the middle segment of the lower plug portion have complementary threads defined thereon for rigidly threadably attaching the upper and lower plug portions to one another.

Abstract: An electromagnet for a nuclear reactor shutdown system, which comprises upper and lower cores disposed in an axially symmetrical arrangement and capable of latching with and delatching from each other. When an ambient temperature increases, the upper and lower iron cores are delatched from each other and a control rod connected to the lower iron core falls down into a reactor core. The lower iron core is provided with a plurality of slits to form a plurality of fins therebetween. A temperature sensitive magnetic material (TSMM) is disposed in the outer circumferential lower corner portion of the lower iron core. An interface between the TSMM and an iron core material takes the form of a side surface of a cone whose central axis is coincident with the symmetry axis and whose apex angle lies in the range of 60.degree. to 120.degree..

Abstract: A drive for positioning a control rod in a nuclear reactor core is disclosed. The drive includes a turbine rotor joined to a hollow spindle in a housing. The spindle has a piston disposed therein and a piston rod extending therefrom and through a bottom end of the spindle for being joined to the control rod. A pressurized fluid is provided into the spindle for exerting a pressure force against the piston for moving the piston for selectively gripping the control rod. Interruption of the pressurized fluid to the spindle causes ungripping of the control rod.

Abstract: A device for the centering and fixation of a cluster guide flange and of a core plate of a nuclear reactor, extending parallel to one another in horizontal planes with a predetermined spacing. The device includes at least two axial guiding spindles of flange with respect to the core plate, diametrically opposite and rigidly connected to the plate or to the flange in order to engage into a housing in register formed in the flange or in the plate, respectively, and an assembly of self-locking shoes, adapted for sliding with a clearance within bores formed in the flange in order to be pressed on the plate surface, these shoes being each associated with a position control mechanism, carried by the flange and exerting on the shoes a force having a transverse component so as to cause, by reaction, immobilization of the flange with respect to the plate.

Abstract: A mechanism for automatically releasing the control bars in a nuclear reactor following an increase of the temperature in the nuclear boiler includes a thermal sensor suitable for producing a mechanical force or a torque as a function of the temperature and such as to operate a mechanical actuator which provides to unlock the device that holds said control bars causing in this way their fall under the force of gravity.

Abstract: A spent fuel rack for storing fresh fuel assemblies, or spent fuel assemblies removed from a nuclear reactor, which includes a base plate having multiple cells of modular construction welded at their bottom ends to the plate. The cells are formed of L-shaped sections having walls which support neutron absorbing material, and the walls of one cell are common to the adjacent cells. The base plate includes openings primarily for receiving the bottom nozzle of a fuel assembly, but they further serve as access openings for apparatus used for leveling the base plate and for lifting and transferring the base plate with or without cells thereon, to a different area.

Abstract: The control rod drive is removed from the top of the reactor. The control rod drive is attached at its upper end to the bottom end of the control rod drive guide tube. The control rod guide tube in turn couples at a rotationally locked bayonet fitting to the top of the control rod drive housing. Locking of the bayonet fitting occurs thru the orificed fuel support casting. The orificed fuel support casting, is locked from rotation at a pin located on the reactor core plate. The control rod guide tube in turn locks rotationally to the orificed fuel support casting. During refueling, the fuel bundles and the orificed fuel support casting are removed, freeing the control rod guide tube and its depending drive for rotation. Thereafter, a fitting captures the control rod guide tubes at coolant inflow apertures and rotates the guide tubes and the depending drives.

Abstract: A thermally responsive trigger device comprises a closed bellows (14) having a filling a liquid metal and acting on a trigger (19) responsive to the free end of the bellows. The bellows and trigger are located at a temperature measuring location which is the coolant flow outlet (15) from a demountable sub-assembly vehicle (10) having a fuel unit (11) and a triggerable absorber unit (12). The outlet flowing coolant sweeps over the bellows (14) and once the expansion of the bellows exceeds a threshold a pin (26) and cam (28) at the free end of the bellows causes a plate (21) to move to a release the absorber unit (12).

Abstract: The present invention provides an apparatus for handling core constituent elements of a reactor that comprises a core having as core constituent elements control rod assemblies each containing a control rod and fuel assemblies each containing nuclear fuel, a small rotating plug rotatably provided on the core, and a control rod drive mechanism provided on the small rotating plug, the control rod drive mechanism being characterized by comprising a plurality of grippers each having a hook projecting inwards so as to be able to engage with a handling head of the control rod and a hook projecting outwards so as to be able to engage with a handling head of each of the core constituent elements as a distance in the longitudinal direction; an operational head for opening and closing the grippers; and a third elevating drive mechanism for vertically driving the operational head; a second elevating frame for supporting the third elevating drive mechanism and the grippers; a second elevating drive mechanism for vertical

Abstract: An absorber rod for nuclear reactors with a pile of spherical fuel elements, which is inserted directly into the pile, in order to affect the prevailing neutron flux by absorber material located in an annular gap between two concentric cylindrical rod elements. The absorber rod has concentric rod elements arranged in pairs, a common rod tip and common connecting pieces. The rod elements are cooled by flow of gas and the inner cylindrical rod element performs the support function, i.e., it absorbs and transmits forces and moments originating in the movements of the rod during insertion and extraction.

Abstract: A pressurized water nuclear reactor comprises a normally vertical main vessel externally duplicated by a confinement enclosure. The main vessel contains a simplified primary circuit essentially incorporationg the reactor core and an annular steam generator arranged in such a way that the circulation of water, pressurized once and for all during the sealing of the vessel, takes place by natural convection. All the auxiliary circuits, conventionally ensuring cooling on shut down of such a reactor are eliminated, said cooling being ensured by a special arrangement of the space formed between the vessel and the enclosure and by the fact that the latter is immersed in an external cooling liquid, no matter what the slope of the reactor. The shut down of fission reaction in the core is ensured by systems of absorbing elements and by the automatic displacement of part of the reflector in the case of a slope of the reactor.

Abstract: Selectively and remotely disconnectable two-piece drive rod assemblies comprising elongated hub and drive rod portions interconnected by a selectively disconnectable coupling, connect rod clusters within the pressure vessel of a pressurized water reactor system to respectively corresponding drive means. The drive means are selectively operable, through the drive rod assemblies, to move the corresponding rod clusters between fully inserted positions within the lower barrel assembly of the pressure vessel, in telescoping relationship with fuel rod assemblies therein, and to a fully withdrawn position within an inner barrel assembly of the pressure vessel.

Abstract: In order to automatically initiate without any intermediate instrumentation chain the drop of absorbing members into the core of a nuclear reactor, in the of a drop in the cooling liquid level to below a given threshold and, optionally, a rise in the pressure to beyond a maximum permitted value, between each absorbing member and the bar supporting said member is provided an apparatus, which comprises tongs formed by at least two fingers, said tongs normally being locked in a gripping position by locking members, such as balls. A float mounted in the bar controls the unlocking of the tongs in either of the two conditions requiring the dropping of the absorbing members.

Abstract: The device comprises a vertical shaft (36) movable along its axis under the action of a fluid pressure difference and having means for supporting at least one head (28) of the cluster and a first resilient finger (42) for securing and retaining the head on the support means. It comprises a high position securing mechanism carried by a fixed tube (20) for guiding the cluster and having at least one resilient finger for securing the head and retaining the head against the action of gravity and a vertically movable bolt urged resiliently to a position in which it prevents disengagement of a second resilient finger and cooperating with a mechanism controlling a second cluster so as to be brought into a position in which it releases the second resilient finger when the second cluster passes beyond the highest position assumed during normal operation.

Abstract: Device and method for retaining a linearly movable element in a nuclear reactor. The device comprises, for each shaft, a base fixed to the top part of the reactor internals and coaxial with a shaft guide tube; several grippers or catches spaced apart about the axis of the base and mounted for pivotal movement about a horizontal axis towards a position into and out of engagement with a portion, having circumferential grooves, of the shaft contained in the tube; a slide movable axially on the base towards a top position where it causes engagement of the catches in a groove of the rod, and out of such position; and springs bearing on the base and tending to engage the catches on the shaft. The slide is dimensioned so as to be held by the corresponding sleeve projecting through the reactor vessel cover in a position sufficiently distant from the low position for the catches to be released, whatever the temperature in the reactor.

Abstract: A coupling device between a nuclear reactor control rod and an actuating mechanism has a gripper body having resilient gripping fingers, belonging to the mechanism and, on the bar, a terminal pommel for engagement by the fingers and a shoulder directed towards the pommel. The coupling device comprises an additional member, such as a sleeve, movable with respect to the gripper body between a position in which it allows resilient fingers to be released from the pommel and another position in which it locks the resilient fingers onto the pommel. The sleeve has an end face bearing on the shoulder of the pommel. A prestressed spring exerts a force tending to move the sleeve away from the fingers so as to hold the end face of the sleeve firmly applied against the shoulder when the fingers are locked on the pommel.

Abstract: A temperature responsive, self-actuated nuclear reactor shutdown control rod assembly 10. The upper end 18 of a lower drive line 17 fits within the lower end of an upper drive line 12. The lower end (not shown) of the lower drive line 17 is connected to a neutron absorber. During normal temperature conditions the lower drive line 17 is supported by detent means 22,26. When an overtemperature condition occurs thermal actuation means 34 urges ring 26 upwardly sufficiently to allow balls 22 to move radially outwardly thereby allowing lower drive line 17 to move downwardly toward the core of the nuclear reactor resulting in automatic reduction of the reactor powder.