Abstract: A method and apparatus is disclosed for very rapidly cleaning very small, colloidal particles from nuclear reactor water subjected to a high-energy waterjet cutting of metal using metal shot particles for cuffing such as garnet particles with the cutting causing fracturing of the metal shot as well as the cut metal fines into a negatively charged colloidal suspension having a large area. This colloidal suspension causes water turbidity and makes known filtration techniques impractical for rapid removal of such suspensions for recycling to the reactor.

Abstract: The present invention provides an apparatus and method for measuring nonferrous electrical resistance measurement. The method includes providing a nonferrous material, inducing a magnetic field on the nonferrous material, measuring the remote magnetic field of the nonferrous material, and comparing the measured remote magnetic field to a standard.

Abstract: The invention is directed to an apparatus and method for inspecting spring hold down bolts of an upper tie plate of a fuel rod assembly in a nuclear reactor and includes an inspection fixture adapted to be aligned with the upper tie plate of the nuclear reactor fuel rod assembly for placement into a position for rapid and easy insitu inspection of the hold down bolts of the upper tie plate. The fixture is provided with a plurality of ultrasonic transducers which are positioned on the fixture so that when the fixture is placed into the inspection position each transducer will be located proximate to one of the hold down bolts for conducting effective ultrasonic scanning of the bolt while the bolt is in place. A multi-channel ultrasonic flaw detector is connected to each of the transducers for indicating whether there are any flaws in each of the hold down bolts when the fixture is placed into the inspection position and the ultrasonic transducers are activated.

Abstract: A tube testing system consists of two subassemblies, the probe and the applicator. The probe uses a stack of Belleville style washers that when compressed allow the locking fingers to relax and the probe to be inserted into the tube. Once the probe is placed in the correct location using the applicator, the Belleville style washers are allowed to expand, locking in the fingers and engaging the urethane seals. As the water fills the tube, the air is pushed through a bleed hole in the mandrel of the probe. The bleed hole leads to a chamber in the top of the probe that contains a plastic ball. The ball floats on water and as the chamber fills, the ball seals off the leak path and the tube can then be pressurized and the test performed. Once the test is complete, the water is drained and using the applicator, the probe is removed from the tube.

Abstract: A fuel assembly mechanical flow restriction apparatus for detecting failure in situ of nuclear fuel rods in a fuel assembly during reactor shutdown.

Abstract: The liquid effluent from solvent extraction contains radioactive thorium Th-231 and Th-234. This invention uses an ion exchange process to remove and concentrate the thorium. The process is designed so that the thorium remains on the ion exchange column until it decays to uranium and protactinium. These decay products are subsequently replaced by additional thorium. Therefore, the thorium never reaches break-through and the column can be used continuously without regeneration.

Abstract: A CRUD collection system for removing deposits from a nuclear reactor fuel rod submerged in pool water. The system includes a sealable collection head for containing a portion of the fuel rod. The collection head includes at least one seal positioned to receive the fuel rod. Also provided is a liquid inlet communicating with an interior portion of the collection head, the inlet is configured to inject a liquid into the interior to displace the pool water therefrom. At least one blade is provided that is positionable in scraping engagement with the fuel rod. Also included is a liquid outlet for eliminating a CRUD sample and the liquid to a filter.

Abstract: A method of removing rib plugs from steam generator tubes in energy producing units such as nuclear reactors includes the removal of the expander element or mandrel from the expanded part of the rib plug, TIG welding a bead on the available internal surface of the plug in a spiral manner from the bottom to the top thereof to relax the rib plug from its forced contact with the tube and removal of the rib plug as a unit from the tube after it has cooled down from the welding process.

Abstract: An in-situ testing apparatus for testing the integrity of rib plugs used to seal faulty reactor boiler tubes consists of a cup-shaped member with a groove on the open end, a tapped hole for attaching a hydraulic hose of known pressure, and a hole through the top of the member. A seal is installed in the groove on the open end of the cup to seal to the primary face of a tubesheet around the tested rib plug. A threaded mandrel goes through the hole in the top of the cup-shaped member and engages the expander member of the rib plug. The threading action of the mandrel into the expander draws the seal against the tubesheet to seal the testing apparatus and allows the rib plug to be in-situ pressure tested.

Abstract: A method for measuring the thickness of an oxide layer formed on the cladding surface of nuclear fuel rods and underlying a crud layer containing ferromagnetic material using eddy current lift-off measurements by exciting a probe coil at a first frequency which penetrates only into the crud layer and by exciting a probe coil at a second frequency which penetrates the crud layer, the oxide layer and into the cladding of a nuclear fuel rod. By subtracting vectorally the complex impedance resulting from exciting the probe coil at the first frequency from the complex impedance resulting from exciting the probe coil at the second frequency, the thickness of the oxide layer formed on the cladding is measured.

Abstract: An enhanced visibility underwater waterjet cutting system is provided wherein the waterjet cutting assembly and the video camera for remotely viewing the operating system is enclosed within an enclosure spacedly set against the workpiece and a stream of clean water is injected into the enclosure to set up a flow of clean water past the camera and to the waterjet cutting tip to exhaust the cuttings away from the enclosure and camera to allow a continuous view of the cutting surface of the workpiece without clouding up the water in the enclosure.

Abstract: Extruded Borated Aluminum rodlets of extended length are formed to maximize neutron absorption surface area while minimizing weight. They are located in the empty cells of a new or spent fuel assembly previously used by control rods and instrumentation with a length equal to that of a fuel rod or guide tube and control the reactivity of the fuel assembly during storage and shipment of the spent fuel assembly.

Abstract: High strength zirconium alloys with improved strength and creep resistance having 1.5 to 6 weight percent bismuth and an element or mixtures of elements selected from the group of molybdenum, tin and niobium.