Abstract: Disclosed herein are a method of generating a correlation function with no side-peak and a system for tracking a BOC signal in order to synchronize the BOC signal. The method of generating a correlation function includes step S1 of generating sub-correlation functions {Sl(?)}l=0N?1, step S2 of generating a first final correlation function R0(?) by combining some of the sub-correlation functions, and step S3 of generating a second final correlation function Rproposed(?) by combining R0(?) with each of the remaining sub-correlation functions that have not been used for the combination at step S2. The BOC signal is one or more of BOCsin(kn,n) and BOCcos(kn,n) signals.

Abstract: There is provided a dual-polarized N/2-column antenna arrangement. The antenna module arrangement comprises a coupler module. The coupler module is arranged to direct a first summation of energy from signals from a first distinct set of power amplifiers of an N-channel radio to a first single output port connected to a first polarization of a first column of the dual-polarized N/2-column antenna arrangement. The coupler module is arranged to direct a second summation of energy from signals from a second distinct set of power amplifiers of the N-channel radio to a second single output port connected to a second polarization of a second column of the dual-polarized N/2-column antenna arrangement.

Abstract: A pressurized water reactor (PWR) includes a cylindrical pressure vessel defining a sealed volume, a nuclear reactor core disposed in a lower portion of the cylindrical pressure vessel, one or more control rod drive mechanisms (CRDMs) disposed in the cylindrical pressure vessel above the nuclear reactor core, and an annular steam generator surrounding the nuclear reactor core and the CRDM. In some such PWR, a cylindrical riser is disposed coaxially inside the pressure vessel and inside the annular steam generator and surrounds the nuclear reactor core and the CRDM, and the steam generator is disposed coaxially inside the cylindrical pressure vessel in an annular volume defined by the cylindrical pressure vessel and the cylindrical riser. In other such PWR, the steam generator is disposed coaxially outside of and secured with the cylindrical pressure vessel.

Abstract: Fuel bundles for a nuclear reactor are disclosed, and in some embodiments include a first fuel element including thorium dioxide; a second fuel element including uranium having a first fissile content; and a third fuel element including uranium having a second fissile content different from the first fissile content. Nuclear reactors using such fuel bundles are also disclosed, including pressurized heavy water nuclear reactors. The uranium having the different fissile contents can include combinations of natural uranium, depleted uranium, recycled uranium, slightly enriched uranium, and low enriched uranium.

Abstract: Illustrative embodiments provide nuclear fission fuel elements, and systems, applications, apparatuses, and methods related thereto. Illustrative embodiments and aspects include, without limitation, nuclear fission fuel elements, heat pipe assemblies, heat pipes, methods of fabricating a nuclear fission fuel element, methods of fabricating a heat pipe assembly, and the like.

Abstract: There is provided an inspection device for inspecting an inner surface of a nozzle provided in a reactor vessel. The inspection device includes: a device frame, an inspection unit provided on the device frame, an inspection unit push-out moving mechanism for pushing out and moving the inspection unit to the inner surface of the nozzle, a rotation moving mechanism for rotating and moving the inspection unit, a calibration test unit arranged on the device frame for calibrating the inspection unit; and a calibration test unit forward/backward moving mechanism for moving the calibration test unit forward or backward in the direction along the central axis with regard to a track where the inspection unit makes push-out movement.

Abstract: A process for minimizing waste and maximizing utilization of uranium involves recovering uranium from an irradiated solid target after separating the medical isotope product, molybdenum-99, produced from the irradiated target. The process includes irradiating a solid target comprising uranium to produce fission products comprising molybdenum-99, and thereafter dissolving the target and conditioning the solution to prepare an aqueous nitric acid solution containing irradiated uranium. The acidic solution is then contacted with a solid sorbent whereby molybdenum-99 remains adsorbed to the sorbent for subsequent recovery. The uranium passes through the sorbent. The concentrations of acid and uranium are then adjusted to concentrations suitable for crystallization of uranyl nitrate hydrates. After inducing the crystallization, the uranyl nitrate hydrates are separated from a supernatant. The process results in the purification of uranyl nitrate hydrates from fission products and other contaminants.

Abstract: Systems, methods, and devices with improved electrode configuration for downhole nuclear radiation generators are provided. For example, one embodiment of a nuclear radiation generator capable of downhole operation may include a charged particle source, a target material, and an acceleration column between the charged particle source and the target material. The acceleration column may include an intermediate electrode that remains floating at a variable potential, being electrically isolated from the rest of the acceleration column.

Abstract: Example embodiments are directed to methods of producing desired isotopes in commercial nuclear reactors and associated apparatuses using instrumentation tubes conventionally found in nuclear reactor vessels to expose irradiation targets to neutron flux found in the operating nuclear reactor. Example embodiments include irradiation targets for producing radioisotopes in nuclear reactors and instrumentation tubes thereof. Example embodiments include one or more irradiation targets useable with example delivery systems that permit delivery into instrumentation tubes. Example embodiments may be sized, shaped, fabricated, and otherwise configured to successfully move through example delivery systems and conventional instrumentation tubes while producing desired isotopes.

Abstract: Systems join with a control rod drive and expand or contract to displace elements necessary for decoupling. Joining structures affix to on sides of the control rod drive allow discriminatory jacking by a powered drive also in contact with the control rod drive. A moveable piston tube can be displaced by this jacking with hundreds or thousands of pounds of force with respect to the control rod drive. Probes and other instrumentation and sensors are useable in the systems to accurately measure any of piston tube displacement, temperature, malfunction; drive power status, displacement or speed; and communications status. Manual interaction with the systems are not required during the jacking, and installation and removal of the systems requires no tools or great amount of time or effort. Through remote operation and brief installation, human exposure to radiation about control rod drives is minimized.

Abstract: A modular, nuclear waste conversion reactor that continuously produces usable energy while converting U-238 and/or other fertile waste materials to fissionable nuclides. The reactor has a highly uniform, self-controlled, core (2) with a decades-long life and does not require reactivity control mechanisms within the boundary of the active core during operation to retain adequate safety. The exemplary embodiment employs high-temperature helium coolant, a dual-segment (22) initial annular critical core, carbide fuel, a fission product gas collection system, ceramic cladding and structural internals to create a modular reactor design that economically produces energy over multiple generations of reactor cores with only minimum addition of fertile material from one generation to the next.

Abstract: A particulate removal apparatus and method are used to capture and remove particulates from nuclear reactor core coolant during normal operation. Bottom nozzle, particulate removal apparatus and top nozzle structures form an assembly sized to be installed in place of a nuclear fuel assembly. The particulate removal achieved reduces the inventory of corrosion product deposits, foreign objects and other particulates in the reactor coolant system. This in turn reduces activation or deposition of particulates on fuel cladding, with a corresponding improvement in fuel reliability and reduction in ex-core radiation fields.

Abstract: A plasma confinement system is provided that includes a confinement chamber that includes one or more enclosures of respective helicity injectors. The one or more enclosures are coupled to ports at an outer radius of the confinement chamber. The system further includes one or more conductive coils aligned substantially parallel to the one or more enclosures and a further set of one or more conductive coils respectively surrounding portions of the one or more enclosures. Currents may be provided to the sets of conductive coils to energize a gas within the confinement chamber into a plasma. Further, a heat-exchange system is provided that includes an inner wall, an intermediate wall, an outer wall, and pipe sections configured to carry coolant through cavities formed by the walls.

Abstract: An antenna cell for a wide-scan low-profile phased array system includes an antenna layer including one or more stacked conductive radiators configured to receive electromagnetic waves. The antenna cell also includes a feed layer that includes multiple rectangular slots and one or more feed structures. Each rectangular slot may excite an orthogonal polarization. The feed structures are positioned perpendicular to one another, and each of the feed structures includes a feed fork that includes a set of open-circuit stubs and is configured to tune antenna performance.

Abstract: Devices and methods are directed to estimating a position of the device/user using a delta range measurement (DRM) module to measure a range difference between first and second range values for first and second time instants based on, e.g., carrier phase measurements. The time period between the first and second time instants may be greater than a periodic interval at which a new phase value is sampled. This architecture of the DRM module provides extended delta ranges values which also overlap in time, enabling a combination of improved dilution of precision and keeping fast generation of delta range values suitable for use in continuous filtering. A filter, e.g., a Kalman filter, may be used compute current estimates of two positions, or a combination of a position and a position difference, of the device based at least on the range difference and a priori estimate(s) of the position(s) of the device.

Abstract: A hybrid nuclear reactor for producing a medical isotope includes an ion source for producing an ion beam from a gas, a target chamber including a target that interacts with the ion beam to produce neutrons, and an activation cell positioned proximate the target chamber and including a parent material that interacts with the neutrons to produce the medical isotope via a fission reaction.

Abstract: An apparatus for supporting radioactive fuel assemblies, such as spent nuclear fuel. In one aspect, the invention is an apparatus, which can be in the form of a fuel basket, fuel rack, or the like, in which polygonal storage tubes are used not only for their internal cells but are also strategically patterned to create resultant cells with their outside surfaces.

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: Methods and systems for detecting an individual leaking fuel channel included in a reactor. One system includes a plurality of inlet lines and a plurality of outlet lines. Each of the plurality of inlet lines feeding annulus fluid in parallel to an annulus space of each of a first plurality of fuel channels included in the reactor, and each of the plurality of outlet lines collecting in parallel annulus fluid exiting an annulus space of each of a second plurality of fuel channels included in the reactor. In some embodiments, the system also includes a detector positioned at an outlet of each of the plurality of outlet lines configured to detect moisture in annulus fluid and identify a first position of an individual leaking fuel channel, and an isolation valve positioned at an inlet of each of the plurality of inlet lines operable to stop annulus fluid from circulating through one of the plurality of inlet lines and to identify a second position of the individual leaking fuel channel.

Abstract: A voloxidizer with a double reactor for spent fuel rods decladding of the present invention includes a reactor module into which spent fuel rods are loaded, the reactor module including a reactor having a dual structure; a heater module for heating the reactor module; and a drive module for providing a driving force to the reactor module. A double reactor utilized in a voloxidizer for spent fuel rods decladding includes an internal reactor into which spent fuel rods are loaded; and an external reactor formed on an outer circumferential surface of the internal reactor. Here, a first transport part and a second transport part are formed on inside surfaces of the internal reactor and the external reactor, respectively, and the spent fuel rods are moved by the first transport part and the second transport part and oxidized when the internal reactor and the external reactor are rotated.