Abstract: An in-line dissolved gas removal membrane-based apparatus for removing dissolved hydrogen and fission gases from the letdown stream from a reactor coolant system.

Abstract: The invention relates to compositions and methods for coating a zirconium alloy, e.g., ceramic-containing, cladding tube for use with fuel rods in a nuclear water reactor. The coating includes an intermediate oxidation resistant layer and a SiC containing layer at least partially deposited on the intermediate oxidation resistant layer. The SiC containing layer can include a plurality of fibers. The invention provides improved capability for the zirconium alloy cladding to withstand normal and accident conditions to which it is exposed in the nuclear water reactor.

Abstract: A zirconium alloy cladding tube for use in a water cooled nuclear reactor under normal operating conditions and under high temperature oxidation conditions is described. The cladding tube has a coating uniformly deposited thereon. The coating, which may be up to 300 microns thick, is selected from the group consisting of chromium, a chromium-based alloy, and combinations thereof.

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: A nuclear fuel assembly comprising a plurality of control rod guide assemblies. At least one of the control rod guide assemblies includes a guide tube having an axial dimension, the guide tube being supported by the plurality of grids and extending axially between the top nozzle and the bottom nozzle, the guide tube having an upper portion having a first radius and a lower portion having a second radius less than the first radius, and an external dashpot tube disposed around a portion of the lower portion in an area beginning at the bottom grid and extending toward the top nozzle.

Abstract: Described herein is a clamp for repairing a site of at least one damaged nozzle on a pipe for carrying liquid, such as a sparger nozzle in a header pipe in a boiling water reactor of a nuclear power plant. The clamp in general includes a housing configured for mounting over the site on a surface the pipe, wherein the housing has a front, sides, top, and back. The housing may include an opening, or the clamp may include an orifice plate having an opening and being positioned on the front side of the housing such that liquid exiting the pipe flows through one or both the opening in the housing and opening in the orifice plate. The clamp also includes a bottom surface which, together with the housing and orifice plate, when included, defines an interior chamber. The bottom plate has an opening for alignment, upon installation, with the site, and at least one member, for example, wedges for securing one of the damaged nozzle or support rings for stabilizing a replacement nozzle in position within the housing.

Abstract: The invention relates generally to uranium fuel in a nuclear reactor and, more particularly, the inclusion of a fuel additive component to the bulk fuel material. The fuel additive component is selected and provided in an amount such that it is effective to improve one or more properties of the bulk fuel material. The fuel additive component has a grain size that is less than the grain size of the bulk fuel material. The granular fuel additive component coats or covers the granular bulk fuel material.

Abstract: A detection apparatus includes a resonant electrical circuit supported within an interior of a nuclear fuel rod generates a response pulse in response to an excitation pulse and transmits the response pulse through a cladding of the fuel rod to another location within a reactor in which the fuel rod is housed and without any breach in the cladding. A characteristic of the response pulse is indicative of a condition of the fuel rod. The detection apparatus also includes a transmitter positioned outside the cladding, in the reactor, in the vicinity of the fuel rod and configured to generate the excitation pulse and transmit the excitation pulse through the cladding to the resonant electrical circuit. A receiver is supported within the reactor outside of the cladding and, in response to the response pulse, communicates a signal to an electronic processing apparatus outside of the reactor.

Abstract: A server-based nuclear containment operations system can be used to monitor structures, systems, components, and personnel within the containment building of a nuclear power facility. The disclosed and claimed concepts relate generally to a method for utilizing near field communication (NFC) on a mobile client device having the dynamic capabilities of a logic-based computerized procedures system (CPS). The client permits the execution of procedures remotely in the field while monitoring the real-time current state and operation of the systems, components, and sensors of a large facility such as a nuclear power plant. This system consists of a client and server application which provide real-time monitoring of procedure adherence and place keeping, facility clearance information, and work order administration (including tracking an operator's procedure adherence) and further provides a capability for operator input.

Abstract: A method for making an improved nuclear fuel cladding tube includes reinforcing a Zr alloy tube by first winding or braiding ceramic yarn directly around the tube to form a ceramic covering, then physically bonding the ceramic covering to the tube by applying a first coating selected from the group consisting of Nb, Nb alloy, Nb oxide, Cr, Cr oxide, Cr alloy, or combinations thereof, by one of a thermal deposition process or a physical deposition process to provide structural support member for the Zr tube, and optionally applying a second coating and optionally applying a third coating by one of a thermal deposition process or a physical deposition process. If the tube softens at 800° C.-1000° C., the structural support tube will reinforce the Zr alloy tube against ballooning and bursting, thereby preventing the release of fission products to the reactor coolant.

Abstract: An energy storage device includes a plurality of plates, each having a first and second surface, with at least one of the surfaces having a plurality of grooves formed therein. The device further includes inlet and outlet plenums for providing or receiving a heat transfer medium to or from the grooves. At least one of the first surface and the second surface having the plurality of grooves formed therein of a first plate is disposed in direct contact with the other one of the at least first surface and second surface of an adjacent second plate. Heat from the transfer medium is transferred to the plates in a charging mode of operation or transferred from the plates to the transfer medium in a discharging mode of operation when the heat transfer medium is passed along the grooves.

Abstract: A method and apparatus for extending the period a nuclear steam supply system spent fuel pool can be safely passively cooled by storing the spent fuel offloaded from the reactor, in the containment for one reactor operating cycle. During a refueling the spent fuel that is not to be returned to the reactor and the spent fuel that will be returned to the reactor are stored separately in shielded locations within the containment. After one operating cycle, the spent fuel stored within the containment that was not returned to the reactor just prior to the last operating cycle, is offloaded to the spent fuel pool and replaced by the newly offloaded spent fuel that is being retired.

Abstract: A method and apparatus for extending the period a nuclear steam supply system spent fuel pool can be safely passively cooled by storing the spent fuel offloaded from the reactor, in the containment for one reactor operating cycle. During a refueling the spent fuel that is not to be returned to the reactor and the spent fuel that will be returned to the reactor are stored separately in shielded locations within the containment. After one operating cycle, the spent fuel stored within the containment that was not returned to the reactor just prior to the last operating cycle, is offloaded to the spent fuel pool and replaced by the newly offloaded spent fuel that is being retired.

Abstract: An improved, accident tolerant fuel for use in light water and lead fast reactors is described. The fuel includes a ceramic cladding, such as a multi-layered silicon carbide cladding, and fuel pellets formed from U15N and from 100 to 10000 ppm of a boron-containing integral fuel burnable absorber, such as UB2 or ZrB2.

Abstract: A panel that uses the gamma radiation emitted by fission to produce electrical power. The panel includes layers of a metal with a relatively high atomic number (Z), that form an emitter, a high temperature electrical resistor, and an electrical conductor with a relatively low Z value, that forms a collector. The gamma radiation emitted during the fission process produces Compton and photoelectrical electrons in the layer of the Emitter located between the reactor Baffle and the fuel assemblies. The electrons that have sufficient energy to penetrate the resistor layer between the emitter layer and the collector layer will be stopped in the collector. This creates a substantial voltage difference between the emitter and the collector. This voltage difference may be used to produce significant electric power both during reactor operations and with the reactor shutdown to meaningfully augment the electricity produced by the turbine generators.

Abstract: In a panel that uses the gamma radiation emitted by fission to produce electrical power, a source of an electrical current is connected to a layer of the panel made of a metal with a relatively high atomic number (Z) that forms an electron emitter. The emitter layer is surrounded by an insulation layer which in turn is surrounded by a relatively low Z value layer for collecting electrons from the emitter. Another layer of insulation and an outer sheath surround the collector. The improved panel may be used for reactor power level and power distribution measurements, and for initiating, maintaining or returning molten salt or metal coolants in the liquid state.

Abstract: A molten salt reactor includes a containment vessel, a reactor core, a neutron reflector spaced from the containment vessel, and liquid fuel enclosed within the core. The liquid fuel is comprised of a nuclear fission material dissolved in a molten salt. A heat exchanger is positioned external to the containment vessel. A plurality of heat transfer pipes are provided for transferring heat from the core to the heat exchanger. Each pipe has a first and a second end. The first end of each pipe is positioned within the reactor core for absorbing heat from the fuel. The heat exchanger receives the second end of each heat transfer pipe. At least two or more reactor shut down systems are provided. At least one shut down system may be a passive system and at least one or both shut down systems may be an active or a manually operated system.

Abstract: A mounting assembly that has no threaded connections. A rod with pins or machined features radially extending from a distal end is configured to rotate until the pins align with grooves in a hole through a base plate. The rod is inserted through the hole until the pins are through an opposite surface of the base plate, compressing spring components on the rod. Then the rod is rotated until the pins are aligned with slots that partially extend through the second side of the base plate and the pins become seated in the slots. To remove the rod a tool that engages an articulated feature on the distal end of the rod is installed. The tool rotates the rod until the pins are disengaged from the slots, aligned with the through grooves and passed through the base plate.

Abstract: A Gland Seal End Plug closure for a nuclear fuel rod cladding composed of silicon carbide or other materials that cannot be welded. The sealant is, preferably, made from one or more forms of pure graphite and the ram, seat and other components of the Gland Seal End Plug are formed from high temperature metallic or ceramic materials.

Abstract: The invention relates to UF6 transport and process containers to store UF6 enriched up to 20 percent by weight 235U in amounts up to 1,500 kg U. The containers include a shell, which has an integral heat exchanger positioned between the exterior and interior surfaces/substrates of the shell. The integral heat exchanger is composed of metal passage voids to pass heat transport fluid. The shell forms an inner chamber, and a partition configuration is positioned within the inner chamber, extending longitudinally along the length of the container, to form a plurality of individual compartments within the inner chamber to store the UF6. The containers may be produced by additive manufacturing methods.