Abstract: A transducer for generating or detecting ultrasonic energy of very narrow bandwidth which closely approximates a monochromatic source or detector has a gas gap of uniform dimensional width. The transducer employs standing ultrasonic waves generated, by multiple reflections and constructive interference, within the gap, effectively acting as a filter to pass only ultrasonic waves having a predetermined resonant frequency in response to impingement of broadband ultrasonic energy. This filtering effect enables the transducer to act as a source or detector of monochromatic ultrasound.

Abstract: A double-cantilever beam crack growth sensor made from welded alloy, e.g., nickel-based alloy, and a method for fabricating such sensors. The method includes the steps of forming a strongback from a block of a first nickel-based alloy; depositing a suitable thickness of nickel-based weld alloy on top of the strongback to form a bi-metallic test block; welding a second block of the first nickel-based alloy on top of the weld alloy; and machining the final three-layer block to form a double-cantilever beam crack growth sensor consisting of cantilever beams made of the first nickel-based alloy, a crack growth section of weld alloy having a microstructure wherein the direction of dendritic growth is parallel to the direction of crack growth and a third section made of the first nickel-based alloy.

Abstract: A tool for remotely installing a plug in a steam line of a reactor vessel. The tool has a strongback assembly on which a plug is securely mounted, a collapsible structure (e.g., a scissors jack assembly) which supports the strongback assembly and is movable between an extended state and a collapsed state, a hanging bracket assembly for hanging the collapsible structure inside the reactor vessel, and a rotatable actuating screw coupled to the collapsible structure. The collapsible structure moves between the extended and collapsed states in response to rotation of the actuating screw. During this operation, the plug is carried from a retracted position outside and aligned with the steam line nozzle to an inserted position inside the nozzle.

Abstract: An improved tool for removing a highly contaminated outer filter from a control rod drive during a maintenance operation. The tool slides onto the control rod drive and surrounds the outer filter with a shield. The shield has a window for removing the screws used to mount the outer filter on the control rod drive. The tool has a support for the spud on the inside thereof. A U-shaped handle is slidably inserted into guideways so that it interlocks with circumferential slots in the shield. The arms of the inserted U-handle latch underneath the ring flange of the outer filter, whereby the outer filter is captured by the tool. The filter-mounting screws are then removed by unscrewing through the aligned window in the shield. Thereafter, the outer filter is removed from the CRD when the outer filter removal tool is lifted.

Abstract: A shield for restricting molten corium from flowing into a water sump disposed in a floor of a containment vessel includes upper and lower walls which extend vertically upwardly and downwardly from the floor for laterally bounding the sump. The upper wall includes a plurality of laterally spaced apart flow channels extending horizontally therethrough, with each channel having a bottom disposed coextensively with the floor for channeling water therefrom into the sump. Each channel has a height and a length predeterminedly selected for allowing heat from the molten corium to dissipate through the upper and lower walls as it flows therethrough for solidifying the molten corium therein to prevent accumulation thereof in the sump.

Abstract: An improved method for examining fuel bundle spacers using fiber-optic visual inspection apparatus. A distal end of a fiber-optic scope having image and light guides is inserted through an upper tie plate and between the fuel rods of a fuel bundle assembly at the top thereof. The distal end of the scope is then lowered into the space between a group of spacer ferrules until a side aperture of the scope is at the elevation of the spacer spring to be inspected. Light is supplied to the light guide and redirected out the side aperture to a spot proximal to the field of view of the image guide. The distal end of the scope is rotated until the spacer spring to be inspected is visible through an ocular lens coupled to the image guide. The spring is visually inspected for defects by moving the scope to scan the spacer spring.

Abstract: In a boiling water nuclear reactor fuel bundle, a debris catching arrangement is disclosed for incorporation within the flow plenum up stream or below the rod supporting grid of the lower tie plate assembly. The device is preferably placed within the lower tie plate flow plenum between the fuel bundle inlet orifice and the rod supporting grid structure supporting the fuel rods; alternate placement can include any inlet channel upstream of the fuel rods including the fuel support casting. Paired plates defining offset holes and bosses are utilized. The bosses are supported at plate webbing between the respective holes. The holes are preferably square in plan with appropriately relieved and rounded corners defining the edges of the webbing. The bosses may be cylindrical, square or rectangular in cross-section. In confrontation of plates to form the debris catching grid, each boss from one plate confronts a hole from the remaining plate.

Abstract: A TIG welding system for controlling the weld shape for the seal welding of a small pressurization hole in the end plug of nuclear fuel rods. The controlled shape of the seal weld enables improved ultrasonic detection capabilities. The system achieves the desired weld shape by controlling the pressure differential between the interior and exterior volumes of the fuel rod. The weld box pressure is decreased in accordance with Boyle's law while the weld material for sealing the hole is molten. The system uses an output from the weld electronics as an input to a programmable logic controller ("PLC"). After a programmed time delay, the PLC outputs a signal to a solenoid valve to open a "ballast" volume. The expansion of gas from the weld box into the ballast volume causes a sudden drop in pressure to a level below the pressure inside the fuel rod. As a result of this pressure differential, the molten weld material forms a concave weld upon solidification.

Abstract: A nozzle includes a barrel being integral with a vessel and includes a first bore. A safe end is joined at one end to the barrel by a first weld and at an opposite end to an inlet pipe at a second weld. A first thermal sleeve is disposed inside the first bore and has one end disposed in an interference fit with a second bore of the safe end. In order to repair the nozzle for reducing leakage at the interference fit between the first and second bores, a method includes removing a portion of the inlet pipe and the weld at the safe end and installing a replacement extension therefor. The extension includes a tubular body having a first fork at one end joined to the safe end by a replacement weld, and having a distal end joined to the inlet pipe at a third weld. A second fork is disposed concentrically inside the body and is integrally joined at one end with an intermediate portion of the body, and includes a distal end extending toward the safe end.

Abstract: A boiling-water reactor plant employs a baffle that parallels the interior surface of a thermally-conductive containment wall, defining an intermediate condensate channel. When the plant turbine becomes isolated from the boiling-water reactor, the reactor is shut down and steam is released from the reactor pressure vessel to the containment. Steam rises through an opening at the top of the baffle, allowing some of the steam to condense on the interior surface of the containment. Condensate then flows into the channel, which is dimensioned so that noncondensable gases are dragged into the channel along with the condensate. This minimizes thermal insulation due to the noncondensables and enhances the transfer of heat from the containment. Furthermore, the noncondensable gases are dragged at a sufficient velocity to induce turbulence. The resulting mixing of condensate flow layers further improves heat transfer to the containment wall.

Abstract: A rectilinear sectioned water rod--preferably of square cross-section--is provided with horizontal grooves for keying to bands on the inner, water rod surrounding aperture of spacers. Each spacer is constructed preferably of Inconel and includes a specialized inner band for keying to the water rod. The inner spacer member includes an upper surrounding band, a lower surrounding band, and four connecting vertical members--one positioned at each corner of the water rod. Two adjacent vertical members are bent inward to contact one side of the water rod at spaced apart points on the corners of the water rod. The remaining two adjacent vertical members are bent inward to contact the remaining two corners at single points on each vertical member.

Abstract: In a fuel bundle having an array of fuel rods of 9-by-9 or greater, removal of the corner fuel rods from the array occurs. This removal enables the remainder of the array rod-to-rod pitch to be decreased. Further, and over this array with the corner fuel rod removed, a fuel bundle channel having rounded corners of increased radius of curvature or flattened corners imparting a broadly taped curvature is utilized. In both cases, the effective flat span of the fuel bundle sides is reduced with the result that the new fuel bundle incorporates improved resistance to channel bulge with improved critical power.

Abstract: To measure the spring constants of double-acting, fuel rod-centering springs assembled with different pairs of ferrules in a nuclear fuel bundle spacer, a gauge is provided to include an alignment rod and a probe carried by a handle for insertions into the ferrules of a ferrule pair. The alignment rod loads the side of the spring acting in its ferrule, while the other spring side exerts its fuel rod-centering force on a load cell carried by the probe. A micrometer acts against the load cell to produce measured deflections of the other spring side. Spring constants are calculated from electrical readouts of spring force and spring deflection from the load cell and micrometer.

Abstract: A method for determining the thickness of ferromagnetic material deposited on a nuclear fuel rod. Calibration samples of known thickness and known permeability are placed between the probe of an eddy current sensor and a conductive surface. A plurality of calibration points are plotted to provide a characteristic complex impedance diagram for a probe excited at a predetermined frequency. Then the complex impedance of the probe excited at the selected frequency is measured when in proximity to a fuel rod having a corrosion layer of unknown thickness and unknown magnetic permeability. For each probe position, the two components of the complex impedance, i.e., the inductive reactance and the resistance, are determined and plotted on the characteristic complex impedance diagram. The position of the measured data point relative to the calibration points enables one to determine the lift-off error due to the presence of ferromagnetic material.

Abstract: The present invention provides a cladding having an outer circumferential substrate, a zirconium barrier layer metallurgically bonded to the inside surface of the substrate and an inner circumferential liner metallurgically bonded to the zirconium barrier. The inner circumferential liner is more ductile than conventional Zircaloy. The low ductility of the inner circumferential liner is obtained, for example, by using a zirconium alloy containing a low tin content (e.g. less than 1.2% by weight) and/or a low oxygen content (e.g. less than 1000 ppm). The inner circumferential liner is less than about 25 micrometers thick.

Abstract: A baffle is provided between a relatively hot containment vessel and a relatively cold silo for enhancing air cooling performance. The baffle includes a perforate inner wall positionable outside the containment vessel to define an inner flow riser therebetween, and an imperforate outer wall positionable outside the inner wall to define an outer flow riser therebetween. Apertures in the inner wall allow thermal radiation to pass laterally therethrough to the outer wall, with cooling air flowing upwardly through the inner and outer risers for removing heat.

Abstract: A method and apparatus decrease the release of volatile radioactive iodine from a nuclear reactor pressure vessel containing a reactor core having fuel rods submerged in water. The method includes monitoring the pressure vessel to determine an accident condition and then injecting into the pressure vessel a stable iodide in liquid solution to mix with the reactor water for decreasing vaporization of volatile radioactive iodine discharged from the fuel rods. A reservoir initially stores the stable iodide in the liquid solution and is operatively joined to the pressure vessel through a supply conduit and a normally closed valve which is selectively opened following the accident condition to inject the stored iodide liquid solution into the pressure vessel to mix with the water therein.

Abstract: A one-shot thermal fuse mounted directly on the casing of a centrifugal pump to prevent overheating and concentration of ammonium nitrate. The thermal fuse is screwed into a standard pipe coupling welded to a designated location on the pump casing. The thermal fuse has an electrical contact connected in the pump control circuit. A compressed spring is prevented from urging the electrical contact into an open position by a pellet of fusible material which is designed to melt at a desired threshold temperature below the temperature at which ammonium nitrate explodes. If the heat produced by the pump melts the pellet of fusible material, the spring is released, thereby opening the electrical contact and shutting off the pump. Alternatively, the temperature-sensitive element mounted on the pump casing can be a thermocouple or a temperature switch having a bimetallic element.

Abstract: An electrical stator of an electromagnetic pump includes first and second spaced apart coils each having input and output terminals for carrying electrical current. An elongate electrical connector extends between the first and second coils and has first and second opposite ends. The connector ends include respective slots receiving therein respective ones of the coil terminals to define respective first and second joints. Each of the joints includes a braze filler fixedly joining the connector ends to the respective coil terminals for carrying electrical current therethrough.

Abstract: A plenum spring and getter assembly for use in a nuclear fuel rod has a plenum spring design which retains the getter at a desired distance from the fuel column. The plenum spring is a wire having a first wound section of diameter greater than the diameter of the getter installed therein, a second wound section of diameter less than the getter diameter and a third wound section having a diameter which is preferably, but not necessarily, equal to the diameter of the first wound section. The wound sections are connected in series along an axis, with the "necked" second wound section being situated intermediate the first and third wound sections. When the fuel rod in accordance with the invention is installed upright in the reactor, the getter bears against and is supported by the first turn of the necked wound wire section.