Abstract: A method for cleaning an irradiated nuclear fuel assembly includes chemically enhancing a technique utilizing an apparatus including a housing adapted to engage a nuclear fuel assembly. A set of ultrasonic transducers is positioned on the housing to supply radially emanating omnidirectional ultrasonic energy to remove deposits from the nuclear fuel assembly. Any corrosion products remaining after ultrasonic fuel cleaning will have exposed surfaces that are susceptible to chemical dissolution.

Abstract: A method for cleaning an irradiated nuclear fuel assembly includes chemically enhancing a technique utilizing an apparatus including a housing adapted to engage a nuclear fuel assembly. A set of ultrasonic transducers is positioned on the housing to supply radially emanating omnidirectional ultrasonic energy to remove deposits from the nuclear fuel assembly. Any corrosion products remaining after ultrasonic fuel cleaning will have exposed surfaces that are susceptible to chemical dissolution.

Abstract: The present invention provides a method for measuring hydrogen concentration in an electrically conductive material, such as a nuclear fuel rod, comprising calibrating an eddy current probe at a plurality of hydrogen concentrations; measuring eddy currents at a plurality of positions along an electrically conductive material; and calculating a hydrogen concentration in the electrically conductive material at each of the positions along the electrically conductive material. The present invention also provides a system for measuring hydrogen concentration in a nuclear fuel rod, comprising an eddy current probe; a nuclear fuel rod calibration standard; a data handling system for collecting data generated by the eddy current probe and for performing calculations using the data. The system may be utilized in-situ and may comprise a movable probe mount configured to hold the eddy current probe and to traverse the calibration standard and the nuclear fuel rod to be measured.

Abstract: The present invention provides a method for measuring hydrogen concentration in an electrically conductive material, such as a nuclear fuel rod, comprising calibrating an eddy current probe at a plurality of hydrogen concentrations; measuring eddy currents at a plurality of positions along an electrically conductive material; and calculating a hydrogen concentration in the electrically conductive material at each of the positions along the electrically conductive material. The present invention also provides a system for measuring hydrogen concentration in a nuclear fuel rod, comprising an eddy current probe; a nuclear fuel rod calibration standard; a data handling system for collecting data generated by the eddy current probe and for performing calculations using the data. The system may be utilized in-situ and may comprise a movable probe mount configured to hold the eddy current probe and to traverse the calibration standard and the nuclear fuel rod to be measured.

Abstract: A new type of coated component for use in boiling water reactor (“BWR”) fuel assemblies, particularly Zircaloy spacers, having protective coatings applied to selected surfaces of the spacers in order to prevent the formation and propagation of “shadow corrosion” on adjacent zirconium alloy structures. In its broader aspects, the coating material is applied to those surfaces of the BWR components having electro-chemical characteristics that differ from zirconium alloys, such as Inconel spacers or springs. The new coatings impart an electro-chemical potential to the surfaces of the components that is substantially similar to the adjacent zirconium alloy, thereby preventing or significantly inhibiting shadow corrosion.