Abstract: An apparatus for removing irradiated Co-60 capsules from a plurality of burnable absorber rodlets. The apparatus comprises a solenoid that induces an electromagnetic flux into a Co-60 capsule and locks the Co-60 capsule in parallel with the apparatus. The apparatus is slideable along a longitudinal axis of the burnable absorber rodlet and causes the Co-60 capsule to overcome a plurality of forces exerted on it.

Abstract: Disclosed herein is a method pertaining to a power distribution of a reactor core of a nuclear installation, the method being executed on a general purpose computer. The method comprises: measuring current values from a plurality of vanadium neutron detector assemblies which are disposed in the reactor core of the nuclear installation; determining a measured relative core power distribution based upon the measured current values; producing a measured core power distribution based upon the measured relative core power distribution; and verifying that the reactor is operating within the licensed core operating limits based at least in part upon the measured core power distribution. Also disclosed herein is a vanadium neutron detector assembly.

Abstract: A process for treating highly localized carcinoma cells that provides precise positioning of a therapeutic source of highly ionizing but weakly penetrating radiation, which can be shaped so that it irradiates essentially only the volume of the tumor. The intensity and duration of the radiation produced by the source can be activated and deactivated by controlling the neutron flux generated by an array of electrically controlled neutron generators positioned outside the body being treated. The energy of the neutrons that interact with the source element can be adjusted to optimize the reaction rate of the ionized radiation production by utilizing neutron moderating material between the neutron generator array and the body. The source device may be left in place and reactivated as needed to ensure the tumor is eradicated without exposing the patient to any additional radiation between treatments. The source device may be removed once treatment is completed.

Abstract: The present disclosure is generally related to methods, devices and systems for improving the performances of a Rod Cluster Control Assembly (RCCA) and/or a Control Element Assembly (CEA) to mitigate clad strain, especially in the high fluence region, during normal operation conditions and accident conditions. One method may include incorporating a device such as a powder collection and blockage device between the ceramic upper and ceramic lower absorber materials of the RCCA and/or CEA. Another method may include increasing the plenum volume by incorporating an axial hole into the top end plug extension. Another method may include increasing the plenum volume by incorporating an axial hole into the bottom end plug and optionally incorporating radial grooves in the bottom of the lower absorber material to provide a flow channel for gas expansion or generation to ensure that the lower absorber does not block the opening in the bottom end plug.

Abstract: A motor control center circuit breaker replacement kit includes a standoff having a first plurality of mounting holes corresponding to existing holes on a bucket of the motor control center and a second plurality of holes corresponding to existing holes on a circuit breaker, a door interface panel having a third plurality of holes corresponding to existing holes on a door of the motor control center, the door interface panel having an opening formed therein having a size and shape corresponding to a handle operator associated with the circuit breaker, and a safety latch having a slot structured to receive a tab of the handle operator.

Abstract: Disclosed herein is a cold spray system. The cold spray system comprises a nozzle unit comprising a coating nozzle member, configured to apply at least a portion of a metallic coating to a substrate. The cold spray system is configured to pre-heat the substrate before application of the at least a portion of the metallic coating to the substrate. Also disclosed herein is a method for applying a coating via a cold spray technique.

Abstract: An assembly configured to seal an end plug on a plugged end of a fuel tube is disclosed. The assembly includes a seal weld chamber assembly and a helium flow stop assembly (HFSA) removably coupled to the seal weld chamber assembly. The seal weld chamber assembly includes a welding chamber and a plunger fluidically coupled to the welding chamber. A helium source is configured to supply helium to the welding chamber. The end plug of the fuel tube is positionable within the welding chamber via the plunger. The HFSA is configured to prevent helium from escaping the welding chamber through the plunger.

Abstract: The present disclosure is generally related to methods, systems and devices for forming a randomized grain structure coating on a substrate of a component for use in a nuclear reactor to provide protection against corrosion and, more particularly, is directed to improved methods, systems and devices for forming a randomized grain structure coating on a zirconium alloy nuclear fuel cladding tube using a cathodic arc (CA) physical vapor deposition (PVD) process to provide protection against corrosion in both normal operation and in transient and accidents of the nuclear reactor.

Abstract: A nuclear fuel cladding tube is described herein that includes a zirconium alloy tube having an outer wear and oxidation resistant ceramic coating selected from the group consisting of CrN, Cr2N, CrWN, CrZrN, and combinations thereof. The cladding may have an intermediate layer formed between the tube and the outer ceramic coating. The intermediate layer may be selected from the group consisting of Ta, W, Mo, Nb, and combinations thereof. Both the intermediate layer and the outer ceramic coating may be deposited by physical vapor deposition.

Abstract: A variable diameter fuel rod of a nuclear reactor assembly is disclosed. The variable diameter fuel rod includes an elongated cladding tube configured to house a plurality of fuel pellets including a fissile material arranged in a fuel stack orientation. The elongated cladding tube includes first and second axial reflector regions and a middle axial region therebetween. The middle axial region comprises an outer diameter defined as d1. The first and second axial reflector regions include an outer cladding diameter defined as d2 and d3, respectively. The variable diameter fuel rod further includes a transitional region between the diameter d1 of the middle axial region and the diameter d2 of the axial reflector region. The diameter d2 of the axial reflector region is greater than the diameter d1 of the middle axial region.

Abstract: An assembly configured to seal an end plug on a plugged end of a fuel tube is disclosed. The assembly includes a seal weld chamber assembly and a helium flow stop assembly (HFSA) removably coupled to the seal weld chamber assembly. The seal weld chamber assembly includes a welding chamber and a plunger fluidically coupled to the welding chamber. A helium source is configured to supply helium to the welding chamber. The end plug of the fuel tube is positionable within the welding chamber via the plunger. The HFSA is configured to prevent helium from escaping the welding chamber through the plunger.

Abstract: An ultrasonic phased array transducer assembly having a single housing in which a plurality of phased array transducer subassemblies are mounted at a skewed angle relative to a leading face of the housing and to each other, with each transducer mounted on composite wedge(s) at different orientations within the housing.

Abstract: An ultrasonic testing probe operable to perform an ultrasonic inspection on a workpiece, the workpiece having an interior region. The testing probe comprises a support; an ultrasonic testing element that is structured to generate an ultrasonic output that is directed toward the workpiece and to receive an ultrasonic input from the workpiece that is responsive to the ultrasonic output, the ultrasonic testing element being movably situated on the support; a motor apparatus structured to be electrically connected with a control apparatus, the motor apparatus comprising a motor that is connected with the ultrasonic testing element and is structured to rotate the ultrasonic testing element with respect to the support; and a bladder that is structured to be movable between an initial state and an expanded state, the expanded bladder structured to be engaged with the workpiece within the interior region and to center the support in the interior region.

Abstract: A replacement thermal sleeve with a flange for a reactor vessel closure head penetration adapter housing. By altering a diameter of the flange, a replacement thermal sleeve can be installed through the narrow diameter of the penetration adapter housing opening from under the reactor vessel head. The flange can be compressible or expandable or the tubular wall of the thermal sleeve can be inserted in longitudinal sections, one at a time, into an opening in the underside of the penetration head adapter and reformed within the opening when fully inserted.

Abstract: A housing assembly configured to house a reactor is disclosed. The housing assembly includes a plurality of modular walls configured to surround the reactor and a passive temperature control system. The plurality of modular walls includes a first modular wall. The passive temperature control system is coupled to the first modular wall. The passive temperature control system is configured to transfer heat between the reactor and an area around the housing assembly.

Abstract: A testing arrangement and method of using in performing an in-situ adhesion test of a cold spray deposit on a surface of a structure. The testing arrangement includes a specimen member having a number of apertures defined therein and a loading arrangement coupled to the specimen member. The loading arrangement is configured to provide a mechanical force of a known magnitude to the specimen member. In performing an in-situ test of a cold spray deposit on a structure, the method includes positioning the testing arrangement with respect to a surface of the structure, depositing the cold spray deposit on the surface of the structure, and testing the adhesion of the cold spray deposit to the surface.

Abstract: Disclosed herein is a method comprising coating a fissile, uranium-containing ceramic material with a water-resistant layer, the layer being non-reactive with the fissile, uranium-containing ceramic material. The coating is applied to a surface of the fissile, uranium-containing ceramic material. Also disclosed is a fuel for use in a nuclear reactor.

Abstract: An in-core detector configured to measure a power distribution in a nuclear reactor is disclosed herein. The in-core detector includes a housing configured to be placed within a predetermined location of the nuclear reactor and a plurality of a gamma detectors. Each gamma detector of the plurality of gamma detectors includes a Schottky diode including an active semiconductor region and a Schottky contact, an Ohmic contact, a photoelectron source material configured to transfer electrons to the active region upon contact with gamma radiation, and a first and second lead. The plurality of gamma detectors are positioned within the housing such that each gamma detector of the plurality of gamma detectors is radially offset relative to an adjacent gamma detector of the plurality of gamma detectors, such that the first and second leads of each gamma detector are offset relative to the first and second leads of the adjacent gamma detector.

Abstract: A method is described herein that produces UN from UF6 in at most two steps comprising UF6?intermediate?UN. The principle of the reaction is that in a first step, UF6 would be reduced to UxNy, where x may be an integer selected from 1 and 3, and y is an integer selected from 1 and 2. Reduction occurs at or near the surface of a gaseous membrane electrode where it is also in contact with a nitrogen bearing salt. In a second step, UxNy decomposes to UN and N2 gas, either in the same reactor as the first step or after removal to a separate unit for further processing.

Abstract: A method of locating a remotely operated vehicle within a workspace includes the steps of: receiving a video feed of the workspace from a video camera; processing the video feed to identify landmarks and features of known physical structures in or near the workspace; determining a correlation between the features and landmarks and known physical structures; calibrating the video feed from the camera to the known physical structures using the correlation; determining the location in the calibrated video feed of a number of fiducial markers on the remotely operated vehicle; and determining the position of the remotely operated vehicle within the workspace using the location of the number of fiducial markers in the calibrated video feed.