Abstract: A method and apparatus for replacing a nozzle or heater sleeve in a nuclear reactor coolant system pressurizer. The tubular main body portion of the replacement nozzle is threadably received in the nozzle bore after the original heater and damaged heater sleeve have been removed and the nozzle bore partially tapped to provide a threaded area therein. The first or upper end of the main body portion is positioned substantially flush with the interior of the pressurizer. A seal weld is provided between the upper end of the main body portion and the interior of the pressurizer. A flange that extends radially from and adjacent the second or lower end of the main body portion bears against the exterior of the pressurizer when the main body portion is in its installed position inside the heater sleeve bore.

Abstract: A plug and method for plugging a penetration in a pressure vessel wall having a sleeve protruding through the penetration. The sleeve is cut at a point between the interior and exterior surfaces of the pressure vessel wall. The cut portion of the sleeve extending beyond the exterior surface of the pressure vessel wall is removed. A plug sized to fit within the penetration is inserted into the penetration so that one end of the plug is flush with the exterior surface of the pressure vessel wall. A weld pad is deposited on the end of the plug and the exterior surface of the pressure vessel wall.

Abstract: A fuel rod alignment template and method for loading fuel rods in a nuclear fuel assembly. Front and rear guide plates are provided with a plurality of holes corresponding to cells in the fuel assembly to be loaded. The guide plates are rigidly connected together by connecting rods that extend beyond the front guide plate and are sized to be received in the guide tubes of the fuel assembly. When attached to the fuel assembly with the front guide plate abutting the guide tubes the holes in the guide plates and cells in the grid assemblies of the fuel assembly are in coaxial alignment. This provides positive guidance to the fuel rods as they are inserted into the fuel assembly to prevent mis-tracking and damage to the fuel assembly.

Abstract: A rotating cross wound eddy current head for inspecting tubing. A main body portion has a coil mounting arm pivotally mounted in a bore on the main body portion that allows for radial movement of the arm. A cross wound eddy current coil is mounted adjacent the opposite end of the arm from the pivotal mounting point. Opposing magnets mounted in the main body portion and coil mounting arm bias the arm and coil radially outward so that the coil tracks the surface of the tube being inspected and only reads one point on the tube. A helical inspection path is provided by moving the head axially through the tube while simultaneously rotating the head.

Abstract: A grid key and method for keying exterior grid cells in a nuclear fuel assembly. The grid key has a main body portion having first and second ends and is bent at approximately a 45 degree angle near the first end. Two tabs extend outward from the first end at a right angle to the main body portion to define a T-shape. The T-shaped end is inserted into the window of the exterior grid strip such that the top of the T-shape is parallel to the longitudinal axis of the grid assembly. The main body portion is then rotated 90 degrees to position the top of the T-shaped end to be perpendicular to the longitudinal axis of the grid assembly and behind the exterior grid strip. The main body portion is then pulled away from the exterior grid strip in a vertical rotating motion, causing the top of the T-shaped end to pull the exterior grid strip away from the center of the cell defined by the grid assembly.

Abstract: A thimble tube for use in a guide the in a nuclear reactor. The thimble tube is an elongated hollow tube having one end closed. The portion of the tube that extends into the reactor is formed from a plurality of sections attached to each other to form the tube in an alternating fashion along the width and length of the tube. The sections are formed from materials having different coefficients of thermal expansion. This causes the thimble tube to warp into supporting contact with the interior of the guide tube at normal reactor operating temperature.

Abstract: An apparatus and method for loosening a mechanical plug in a tube. A cartridge having a nose portion, central portion formed from a material that produces an exothermic reaction when ignited, and a base is inserted into the plug to be loosened and removed. An insulated wire extends through the base into the central portion and is connected to a resistive noninsulated wire positioned in the central portion. Sending an electrical current through the wiring causes the noninsulated wire to heat up rapidly. The rapid heat buildup initiates an exothermic reaction in the central portion. The heat generated causes stress conditions in the plug that exceed plug yield and results in a stress relief condition in the plug where the diameter of the plug is reduced. This loosens the plug in the tube and reduces pulling forces needed to remove the plug from the tube.

Abstract: A replacement heater sleeve for a nuclear reactor coolant system pressurizer and method for replacing a damaged original heater nozzle. The original heater and heater nozzle are removed from the pressurizer and the original bore is enlarged. An outer sleeve is installed in the enlarged bore on the same center as the original heater nozzle and is substantially flush with the interior of the pressurizer. The outer sleeve is welded to the pressurizer on its interior and exterior surfaces. An inner sleeve is installed in the inner diameter of the outer sleeve and extends beyond the outer sleeve into the pressurizer. The inner sleeve is welded to the lower end of the outer sleeve and is provided with an inner diameter sized to receive a heater of the same size as that originally installed in the pressurizer. The inner sleeve also maintains the original heater alignment in the pressurizer.

Abstract: A nuclear fuel assembly with a debris filter. The lower end fitting of the fuel assembly has a stamped plate attached thereto that serves as a debris filter immediately upstream of the fuel rods. The stamped plate is provided with a plurality of flow holes in a size and pattern that provides filtration of debris damaging to the fuel rods while maintaining adequate coolant flow through the fuel assembly.

Abstract: A replacement heater sleeve for nuclear reactor coolant system pressurizer and method for replacing a damaged original heater nozzle. The original heater and heater nozzle are removed from the pressurizer and the original bore is enlarged. An outer sleeve is installed in the enlarged bore on the same center as the original heater nozzle and is substantially flush with the interior of the pressurizer. The outer sleeve is welded to the pressurizer on its interior and exterior surfaces. An inner sleeve is installed in the inner diameter of the outer sleeve and extends beyond the outer sleeve into the pressurizer. The inner sleeve is welded to the lower end of the outer sleeve and is provided with an inner diameter sized to receive a heater of the same size as that originally installed in the pressurizer. The inner sleeve also maintains the original heater alignment in the pressurizer.

Abstract: A gas cooled nuclear fuel element. A cylindrical tube having an open lower end contains nuclear fuel disks stacked one upon the other to define an annular space between the tube and disks. An upper and a lower end fitting in the tube support the stack of fuel disks. Each disk has an axial bore or channel for coolant flow. The disks may also be provided with grooves extending radially on the upper or lower face from the axial channel to the outer edge of each disk. The lower end fitting has a central bore that is coaxial with the axial channel in the disks. Coolant flows into the annular space, radially between disks, and then axially out the disks and lower end fitting.

Abstract: A nuclear reactor using gas as a primary coolant and a liquid as a moderator and/or reflector. Gas coolant flows through inlet passages around the outlet plenum to a distributor plate. The gas is directed between fuel element housing thimbles and fuel elements therein, through the fuel elements, and into the reactor outlet plenum. Fins on the thimble housings conduct heat to the gas from a liquid moderator circulating in the core. The use of a liquid moderator enhances safety, allows the fissile material and reactor mass to be reduced and eliminates problems associated with cooling of a solid moderator.

Abstract: A tool positioning assembly for receiving tooling for repairing heater penetrations at the lower end of a pressurizer supported on its end by a support skirt between the pressurizer and a base with the pressurizer having a surge line extending vertically into the apex of the lower spherical end of the pressurizer. A pair of circular tracks are mounted so as to be concentric with the pressurizer. The inner track is mounted to the surge line and the outer track is mounted so as to be below the outer periphery of the pressurizer. A carriage is movably mounted between the tracks so as to be movable therebetween and around the pressurizer. Cross slides mounted on the carriage provide horizontal movement. A vertical slide mounted on the upper cross slide provides vertical movement and is also rotatable around its own vertical axis for clearance purposes when maneuvering around the heater penetration nozzles.

Abstract: A gas cooled nuclear fuel element having a particle fuel retention device which acts as a passive restraint in the event of failure of hot frit. A particle fuel retention device is positioned either in the annular space within the inner frit, in the end cap through which coolant gas flows, or attached to the end cap and extending axially beyond the fuel element.

Abstract: A grid key and method for keying exterior grid cells in a nuclear fuel assembly. The grid key has a main body portion having first and second ends and is bent at approximately a 45 degree angle near the first end. Two tabs extend outward from the first end at a right angle to the main body portion to define a T-shape. The T-shape end is inserted into the window of the exterior grid strip such that the top of the T-shape is parallel to the longitudinal axis of the grid assembly. The main body portion is then rotated 90 degrees to position the top of the T-shaped end to be perpendicular to the longitudinal axis of the grid assembly and behind the exterior grid strip. The main body portion is then pulled away from the exterior grid strip in a vertical rotating motion, causing the top of the T-shaped end to pull the exterior grid strip away from the center of the cell defined by the grid assembly.

Abstract: An ultrasonic transducer socket assembly for simultaneously tightening a bolt and measuring bolt load. A pole adaptor rigidly attached to a driving socket for engaging and driving a bolt has a stationary cylinder mounted therein. A second cylinder rotatably and slidably received in the stationary cylinder has an ultrasonic transducer pivotally mounted at one end that contacts the bolt to be tightened when the socket is engaged with the bolt. The rotating cylinder and transducer are rotated approximately 180 degrees during engagement of the socket and bolt to smear an even couplant layer between the bolt and transducer to assure consistent measurements of bolt load during tightening.

Abstract: A nuclear fuel element for a particle bed reactor. Concentric inner and outer porous cylinders attached at either end define an annulus therebetween that contains a fuel particle bed of nuclear fuel material. The outer porous cylinder is provided with fins that extend radially outward along its entire length. A nonporous cylinder is attached to the outer porous cylinder at either end and is positioned around the outer porous cylinder so as to be concentric therewith. Flexible fins extend radially inward form the nonporous cylinder along its entire length and contact the fins on the outer porous cylinder for conduction of heat to heat removal tubes on the outer surface of the nonporous cylinder. The heat removal tubes allow bimodal cooling of the particle bed reactor.

Abstract: A nuclear fuel assembly with a debris filter. The lower end fitting of the fuel assembly has a stamped plate attached thereto that serves as a debris filter immediately upstream of the fuel rods. The stamped plate is provided with a plurality of flow holes in a size and pattern that provides filtration of debris damaging to the fuel rods while maintaining adequate coolant flow through the fuel assembly.

Abstract: A drive unit for gripping and rotating a fuel rod during inspection of the fuel rod. A housing has a drive motor mounted at its first end with a spindle rotatably mounted in the housing and directly coupled to the drive motor. A recess at one end of the spindle adjacent the second end of the housing receives a substantially donut shaped rubber bladder. A flanged port that extends radially from the bladder and is in fluid communication with the interior of the bladder provides a means for pressurizing the bladder. This causes radial inward expansion of the bladder for gripping a fuel rod to be inspected.

Abstract: An assembly for controlling the release of neutrons in a nuclear reactor having the core split into two halves. A disk assembly formed from at least two circular disks is positioned substantially at the center of and coaxially with the core halves. Each disk is machined with an identical surface hole pattern such that rotation of one disk relative to the other causes the hole pattern to open or close. The disks may be formed from neutron absorbing material or moderator material. The holes may be provided with fissile material inserts to enhance reactivity when in the open position. A drive motor mounted adjacent the reactor and drive shaft operatively engaged between the drive motor and disks is used to rotate the disks.