Abstract: One or more pairs of vertically-spaced-apart sidewardly-aimable plasma arc cutting torches, the upper one angled upward and the bottom one downward, on the end of a horizontal boom movable longitudinally fore and aft and angularly sideward, are used to double-cut the tube bundle of a steam generator progressively in a manner clearing a path that accommodates torch assembly advancement.

Abstract: Nuclear reactor upper internal guide tube having a flow diffuser integral with its bottom end. The guide tube provides guidance for control rods during their ascent or descent from the reactor core. The flow diffuser serves to divert the upward flow of reactor coolant around the outside of the guide tube thereby limiting the amount of coolant flow and turbulence within the guide tube, thus enhancing the ease of movement of the control rods.

Abstract: A tube lock drill for remotely performing operations on equipment including a positioning mechanism disposed in the equipment for selectively positioning the tool with respect to the equipment with the tool comprising a locking mechanism associated with the positioning mechanism for securing the tool in proper relationship to the equipment, a cutting mechanism disposed on a locking mechanism for performing cutting operations on the equipment, and a lifting mechanism attached to the positioning mechanism and attached to the cutting mechanism for lifting the cutting mechanism into contact with the equipment. The tube lock drill tool is capable of being arranged in a plenum of a nuclear steam generator so that remote operations may be performed on the tube sheet and heat exchange tubes in the nuclear steam generator.

Abstract: A multi-function end effector for performing operations on equipment located in areas where human access is limited comprises a vertical support capable of being supported in the equipment on which the operations are to be performed, such as a nuclear steam generator, along with a table attached to the vertical support. The table is capable of positioning tools in relation to the equipment and is capable of driving the tools. The table comprises a centering device for positioning the tools in proper relation to the equipment.

Abstract: The internal diameter measuring apparatus comprises a flexible supporting member capable of being inserted into a heat transfer tube in a nuclear steam generator with flexible centering devices disposed on the flexible supporting member at various locations along the flexible supporting member for centering the measuring apparatus within the heat transfer tube. The measuring apparatus also comprises contacting apparatus disposed on the flexible supporting member for contacting the inside surface of the heat transfer tube that is capable of deflecting in response to variations on the inside surface of the heat transfer tube. The contacting apparatus is connected to a transforming mechanism disposed in the flexible supporting member for monitoring the deflection of the contacting apparatus and for transforming the so monitored deflections into readings indicating the internal diameter of the heat transfer tube.

Abstract: An apparatus for efficiently and safely recombining hydrogen and oxygen gas to form water vapor, the apparatus being particularly adapted for use with a nuclear reactor system in which potentially dangerous hydrogen gas, evolved within the containment vessel during certain postulated accident conditions, can be eliminated. Further, this apparatus also aids in the removal of certain radioactive contaminents from the gases in a containment vessel.

Abstract: Apparatus for vertically separating a motor drive shaft from a load shaft while maintaining alignment between the motor drive shaft and the load shaft so that the load shaft and associated apparatus may be accessed for repair or replacement.

Abstract: Apparatus for removing or inserting studs of a nuclear reactor vessel closure head so that the closure head may be removed for refueling the nuclear reactor. The apparatus comprises a carriage having an engagement mechanism for firmly contacting the studs and a rotation mechanism for rotating the engagement mechanism. A drive mechanism is also attached to the carriage for rotating the rotation mechanism. In addition, a support device is associated with the carriage that is capable of supporting the weight of the carriage during transit and of supporting the weight of the stud while the stud is being manipulated.

Abstract: A tool support arm 22 is mounted to a plate member 18 which in turn is mounted to a horizontal rotatable table 16. The plate 18 has, on its upper face, a plurality of horizontally extending tool support sleeves 20, each sleeve cooperating with one of the horizontally extending tool support arms for secure engagement and quick release therebetween. The sleeve includes means 40, 48 for indexing the tool arm therein. The tool support arms are intermediately hinged 28 for pivotal movement in a vertical plane to lower the vertical projecting tool supported thereon to a non-interfering inactive position while the active tool on another tool support arm extending horizontally from the plate is in the active, raised position.

Abstract: A segmented manipulator arm for a nuclear reactor vessel inspection device is disclosed. The several segments of the arm are linked in a manner which permits independent movement of each segment in a different plane of motion. The transducer array which is utilized to conduct the examination of any appropriate point in the reactor vessel is cooperably linked to the final or most forward segment of the manipulator arm.The first segment of the manipulator arm is appropriately coupled to the main column of the inspection device for independent movement in one of three planes relative to the main column. Additional segments are employed and cooperatively linked to the first segment to yield a total of nine planes of movement for one or more of the segments. In addition, brackets are used to constrain segment movement in parallel or predetermined planes as desired.

Abstract: A remote gaging apparatus for remotely measuring the pellet stack length and plenum length within a nuclear reactor fuel element comprises a housing capable of having a nuclear fuel element inserted therein with a drive mechanism disposed in the housing and attached to a rod having a stop mounted on the rod for selectively inserting the rod into an open end of the nuclear fuel element. The remote gaging apparatus further comprises a measuring device disposed in the housing and associated with the stop for contacting the stop when the rod is inserted into the fuel element thereby measuring the length of insertion of the rod in the fuel element. By determining the length of insertion of the rod in the fuel element, the stack length of nuclear fuel pellets in the fuel element can be determined along with the length of the unfilled plenum of the nuclear fuel element.

Abstract: A pellet dimension checker for determining the weight, length, and density of a pellet such as a nuclear fuel pellet. The checker comprises a rotatable arm for transferring a pellet from a pellet conveyor, to several dimensional measuring stations, and back to the conveyor if the dimensions of the pellet are determined to be within predetermined limits. Should the pellet be nonconforming, the rotatable arm removes the pellet from the process stream.

Abstract: The neutron absorbing medium in a reactor is changed in dependence upon the loading of the reactor, or any other operating mode where the power distribution axially is to be maintained within acceptable limits, by varying the chemical shim in the coolant of the reactor. The error for effecting the change is derived by comparing the average temperature of the coolant and a reference temperature which is a programmed function of the power delivered by the turbine energized by the reactor. The reference temperature is derived by converting the turbine impulse chamber pressure into a temperature parameter. A compensated temperature error is derived from an electrical compensating network typically a PID controller. At the input of this network an electrical analog of the temperature error is impressed and its output, a compensated temperature error, is derived. The correcting command is derived from the output of a non-linear gain network.

Abstract: A closure head for a nuclear reactor includes a stationary outer ring integral with the reactor vessel with a first rotatable plug disposed within the stationary outer ring and supported from the stationary outer ring by a bearing assembly. A sealing system is associated with the bearing assembly to seal the annulus defined between the first rotatable plug and the stationary outer ring. The sealing system comprises tubular seal elements disposed in the annulus with load springs contacting the tubular seal elements so as to force the tubular seal elements against the annulus in a manner to seal the annulus. The sealing system also comprises a sealing fluid which is pumped through the annulus and over the tubular seal elements causing the load springs to compress thereby reducing the friction between the tubular seal elements and the rotatable components while maintaining a gas-tight seal therebetween.

Abstract: Nuclear reactor coolant pump having a tooling boom mounted on the periphery of the motor stand of the pump for transferring pump components through openings in the motor stand during performance of maintenance on the pump. The tooling boom comprises an articulated arm mounted on the periphery of the motor stand with a gripping mechanism attached to the arm at the end opposite the arm's attachment to the motor stand. The gripping mechanism is capable of having pump components firmly attached thereto so that when the articulated arm is swung in the horizontal plane, the pump components may be transferred between the inside and outside of the motor stand.

Abstract: A neutron activation probe comprises a pulsed neutron source in series with a plurality of delayed neutron detectors for measuring radioactivity in a well borehole together with a NaI (T1) counter for measuring the high energy 2.62 MeV gamma line from thorium. The neutron source emits neutrons which produce fission in uranium and thorium in the ore body and the delayed neutron detectors measure the delayed neutrons produced from such fission while the NaI (Tl) counter measures the 2.62 MeV gamma line from the undisturbed thorium in the ore body. The signal from the NaI (T1) counter is processed and subtracted from the signal from the delayed neutron detectors with the result being indicative of the amount of uranium present in the ore body.

Abstract: A method for leaching mineral values from an underground ore body in situ comprises introducing an oxygen-bearing gas into a pressurized saturation-disengagement chamber located above ground of the ore body where the oxygen-bearing gas becomes dissolved in a leach solution. The leach solution with dissolved oxygen therein is then pumped into the well and through the ore body where the leach solution oxidizes the mineral values in the ore body permitting their solubilization and transport by the leach solution to a recovery well where the pregnant leach solution is pumped above ground. The pregnant leach solution is then treated to remove the mineral values therefrom. Insuring that the oxygen-bearing gas is completely dissolved in the leach solution above ground in the saturation-disengagement chamber prevents gas bubbles from being pumped into the ore formation, thereby preventing loss of injectivity.

Abstract: Positioning means for locating inspection apparatus used to volumetrically examine a nuclear reactor vessel is disclosed. The positioning means is provided with a support ring having an annular key positioned longitudinally about its periphery. Three support legs are attached to the support ring by brackets adapted to fit the annular key. In addition, the support ring also carries three guide stud bushings which are movably mounted thereon by clamps adapted to engage the support ring key. Prior to lowering the inspection apparatus into the vessel, the guide stud bushings are each moved to a point of alignment with one of three guide studs extending upwardly from the vessel. After alignment has been verified, the guide stud bushings are clamped in position.The inspection apparatus is now lowered towards its fully seated position within the vessel and is coarsely circumferentially positioned with respect thereto by the engagement of the guide studs within the guide stud bushings.

Abstract: Calibration apparatus for verifying the position and orientation of transducers used in nuclear reactor vessel inspection apparatus is disclosed. A tank, filled with water, the operating inspection medium, is fitted with a movable mounting assembly adapted to securely accommodate a transducer and the mounting assembly in which it is normally secured during an inspection procedure. The tank is also provided with a slidably mounted target positioned therein at a predetermined distance from the target which is selected to avoid the distortion effects in the near field of the transducer response. The calibration apparatus can be used to check the normal transducer mounting for either perpendicularity or angular orientation by moving the tank's mounting assembly via a lead screw with which it is threadingly engaged.

Abstract: A remote access manipulator for performing operations on equipment located in areas where human access is limited. The manipulator comprises a slave carriage located in the equipment on which the operation is to be performed, such as a nuclear steam generator, for carrying tools and inspection devices for performing operations on the equipment together with a master carriage located in a scale model of the equipment and electrically connected to the slave carriage for controlling the movement of the slave carriage. The slave carriage is capable of advancing across a surface of the equipment to position the devices which it carries. The manipulator further comprises a slave manipulator arm used to move the slave carriage into and out of the equipment on which the operation is to be performed in conjunction with a master manipulator arm located in the scale model for controlling the movement of the slave manipulator arm.