Abstract: A nuclear fuel cladding is provided. The nuclear fuel cladding includes a base cladding; and at least one nanomaterial layer deposited on a surface of the base cladding, the nanomaterial layer having an average grain size of between 5 to 400 nanometers. A method of manufacturing nuclear fuel cladding is also provided. The method includes depositing nanoparticles on a base cladding to form at least one nanomaterial layer, the nanoparticles having an average grain size of between 5 to 400 nanometers.

Abstract: A method of operating a nuclear reactor is provided. The method includes defining a layer increment of a deposit layer modeling a deposit on a heat transfer surface of the nuclear reactor; periodically updating a thickness of the deposit layer by adding the layer increment to the deposit layer; recalculating properties of the deposit layer after each layer increment is added to the deposit layer; determining a temperature related variable of the heat transfer surface as a function of the recalculated properties of the deposit layer; and altering operation of the nuclear reactor when the temperature related variable of the heat transfer surface reaches a predetermined value. A method of modeling a deposit on a heat transfer surface of a nuclear reactor is also provided.

Abstract: A method of operating a power generator is provided. The method includes determining an amount of oxides on a heat transfer surface of the power generator as a function of a concentration of a noble metal substance in the oxides; and altering operation of the power generator when the amount of oxides on the heat transfer surface reaches a predetermined value. A method of operating a nuclear reactor is also provided.

Abstract: This invention applies optical tracking technology with an ultrasound inspection system to associate recorded position data with the inspection data. The reference targets of the optical tracking system can be attached to the inspection assembly to allow fully recorded position information to be associated with the ultrasonic, eddy current, or other nondestructive examination data without substantially impacting the overall envelope of the NDE inspection equipment. Moreover, the optical tracking system can be used to monitor skew or twist of the inspection equipment with respect to the normal rectilinear transducer orientation. The inspection equipment position information is then coupled to the inspection data to provide outputs equivalent to fully encoded multi-axis manipulator automated scans, but with less setup burden and equipment expense.

Abstract: This invention applies optical sensing technology with an ultrasound inspection system to associate encoded position data with the inspection data. The compact electronics of the optical system can be attached to the inspection assembly to allow fully encoded position information to be associated with the ultrasonic, eddy current, or other nondestructive examination data without substantially impacting the overall envelope of the NDE inspection equipment. Moreover, because of the small size, the optical system can be used in tandem to monitor skew or twist of the inspection equipment with respect to the normal rectilinear transducer orientation. The inspection equipment position information is then coupled to the inspection data to provide data outputs equivalent to fully encoded multi-axis manipulator automated scans, but with less setup burden and equipment expense.

Abstract: A jet pump stabilizer is disclosed and claimed. The stabilizer includes a clamp body that is affixed about the riser pipe. Two U-clamps are connected to the clamp body, each U-clamp positioned about a jet pump mixer section. A wedge assembly is positioned between the clamp body and each mixer pipe, cooperating with the clamp body and U-clamps to laterally restrain the mixer sections. A clamp ring is positioned about each mixer section and retained in place by the U-clamps, wedge assemblies, and clamp body. A sealing ring is moveably connected to the clamp ring such that it is biased toward engagement with the jet pump diffuser. Seals provided on the stabilizer engage the jet pump assembly above and below the slip joint, preventing vibration-inducing leakage through the slip joint.

Abstract: A resin removal tooling system for electric generator parallel rings including: a non-rotating sheath; a shaft mounted in the non-rotating sheath; a cleaning ball attached to the shaft, the non-rotating sheath positioning the cleaning ball; a high speed motor coupled to the shaft for rotating the shaft; a variable power supply connected to the high speed motor; and a tachometer for measuring a rotational speed of the high speed motor and the cleaning ball. A process of cleaning resin out of an electrical generator parallel ring including the following steps: inserting a cleaning ball mounted on a shaft into the parallel ring; verifying a location of the cleaning ball; rotating the shaft; measuring a rotational speed of the cleaning ball with a tachometer; and removing resin with the cleaning ball.

Abstract: A process of incorporating technetium into an electroless deposit, forming an alloy that is extremely resistant to corrosion and reduces the mobility of technetium on a geologic time scale is disclosed and claimed. The process includes providing a liquid containing technetium, such as an aqueous waste stream generated during the used nuclear fuel reprocessing activities. The technetium is collected and concentrated, and provided into an electroless deposition bath. A substrate, such as suitably prepared zero valent iron or stainless steel, is introduced into the bath to initiate autocatalytic electroless deposition of the technetium onto the substrate due to the difference in electrochemical potential between the plating bath and ti metals in solution. This causes a layer of technetium metal to form on the substrate.

Abstract: The inventive viscous damping tube stabilizer includes modules or capsules containing a viscous material. Adjacent capsules are linked end to end by a flexible cable, allowing the device o pass through curves such as the U-bend regions of steam generator tubes. The weight of the entire assembly will keep it essentially connected to the tube inner diameter such that any tube vibration is transmitted to the stabilizer. The viscous material may only partially fill the capsules such that even under small motion the material can slip and slide past each other, and/or bump into walls, each microscopically absorbing some of the tube energy. By creating multiple cells inside the capsule, the capsule then have good operating characteristics no matter to what angle the individual capsule is oriented as it rests on the full U-bend. The viscous material may completely fill the capsules, which also have a perforated member positioned therein.

Abstract: A method for determining tube support plate blockage of a steam generator includes the following steps: measuring at least five different eddy current values per tube support intersection; calculating a nominal clean fit radius of flow hole; determining a center signal response; converting the center signal response to a deposit thickness; determine an edge reduction; converting the edge reduction to an edge thickness; calculating the resulting flow hole radius; verifying the reasonableness of the resulting flow hole radius; and determining a virtual calibration range.

Abstract: The present invention provides a method of operating a Boiling Water Reactor, having the steps of analyzing LPRM signals for oscilliatory behavior indicative of neutron-flux-coupled density wave oscillations, determining if oscilliatory behavior is present in the signals; initiating a reactor protective corrective action if the oscilliatory behavior is determined, and in addition, initiating corrective actions if neutron uncoupled oscillations are possible. Detecting the later is performed through analytically determined exclusion zone on the power flow map or by on-line stability calculations for several high power channels.

Abstract: A process of collecting and manipulating data to measure the gap between structural components of a piece of equipment or a system is disclosed and claimed. The technique uses ultrasonic zero degree longitudinal waveforms to measure the gap. The technique subtracts the average of two adjacent waveforms from the waveform being processed to remove data from reflections from the components to reveal the reflections generated by the gap.

Abstract: A method for recycling AgInCd control rod absorber bar material from a used control rod from a nuclear power plant includes sectioning AgInCd absorber bar from a used control rod into a first section and a second section, the first section having a higher radioactivity than the second section; and recycling the material of the second section of the AgInCd absorber bar.

Abstract: The present invention provides a method and an apparatus for calibrating a first self-powered neutron detector for long term use in a nuclear reactor core with a second self-powered neutron detector, where the emitter material of the second self-powered neutron detector has a neutron absorption cross-section that is greater than the neutron absorption cross-section of the first emitter material for the first self-powered neutron detector.

Abstract: The invention provides at least two electrochemical sensors positioned in a nuclear reactor or in a system adjacent to the nuclear reactor, wherein at least one of the at least two electrochemical sensors has a heated zirconium electrode, and the at least two electrochemical sensors produce voltages proportional to an electrochemical corrosion potential for a surface that each of the at least two electrochemical sensors are installed upon. The invention also provides an arrangement configured to accept the voltages produced by the at least two electrochemical sensors, wherein the arrangement is configured to determine an electrochemical corrosion potential of a zirconium fuel rod in the nuclear reactor based upon the voltages of the at least two electrochemical sensors.

Abstract: A method for retrofitting a boiling water reactor is provided. The method includes removing a mixing chamber from a slip joint defined by a diffuser and the mixing chamber, the mixing chamber having an inner surface and a bottom edge directing flow to the diffuser such that a recirculation zone at an entrance to the slip joint creates a diverging effective path for the leakage flow entering the slip joint. The method also includes providing a new inner surface and new bottom edge, the new inner surface and the new bottom edge being reshaped to decrease the size of the recirculation zone. A jet pump is also provided.

Abstract: A nuclear power plant is provided including a BWR, a reactor cooling system cooling the BWR, an HWC hydrogen injection system connected to the reactor cooling system and an alcohol injection system connected to the reactor cooling system. Methods for providing methanol and hydrogen are also provided.

Abstract: A nickel, chromium, iron alloy and method for use in producing weld deposits and weldments formed therefrom. The alloy comprises, in weight percent, about 28.5 to 31.0% chromium; about 0 to 16% iron; less than about 1.0% manganese; about 2.1 to 4.0% niobium plus tantalum; 1.0 to 6.5% molybdenum; less than 0.50% silicon; 0.01 to 0.35% titanium; 0 to 0.25% aluminum; less than 1.0% copper; less than 1.0% tungsten; less than 0.5% cobalt; less than about 0.10% zirconium; less than about 0.01% sulfur; less than 0.01% boron; less than 0.03% carbon; less than about 0.02% phosphorous; 0.002 to 0.015% magnesium plus calcium; and balance nickel and incidental impurities. The method includes the steps of forming a welding electrode from the above alloy composition and melting the electrode to form a weld deposit. A preferred weldment may be in the form of a tubesheet of a nuclear reactor.

Abstract: The present invention provides a method of operating a Boiling Water Reactor, having the steps of analyzing LPRM signals for oscilliatory behavior indicative of neutron-flux-coupled density wave oscillations, determining if oscilliatory behavior is present in the signals; initiating a reactor protective corrective action if the oscilliatory behavior is determined, and in addition, initiating corrective actions if neutron uncoupled oscillations are possible. Detecting the later is performed through analytically determined exclusion zone on the power flow map or by on-line stability calculations for several high power channels.

Abstract: Methods for removing nuclear waste from a component are provided. In one embodiment, the method includes the steps of supplying oxalic acid to the nuclear waste on the component to form an oxalic acid/waste solution, feeding the oxalic acid/waste solution from the component, feeding an oxidant to the oxalic acid/waste solution to form carbon-dioxide, water and a precipitate, and separating the precipitate from the water. A system for removing nuclear waste is also provided.