Abstract: Systems and methods for storing spent nuclear fuel below grade that afford adequate ventilation of the spent fuel storage cavity. In one aspect, the invention is a system comprising: a shell forming a cavity for receiving a canister of spent nuclear fuel, at least a portion of the shell positioned below grade; and at least one inlet ventilation duct extending from an above grade inlet to a below grade outlet at or near a bottom of the cavity; the inlet ventilation duct connected to the shell so that the cavity is hermetically sealed to ingress of below grade fluids.

Abstract: Embodiments of the disclosure include methods and compositions for in situ cardiac cell regeneration, including transdifferentiation of cardiac cells to cardiomyocytes. In particular embodiments, in situ cardiac cell regeneration encompasses delivery of p63 shRNA and one or both of Hand2 and myocardin, and in specific embodiments further includes one or more of Gata4, Mef2c, and Tbx5. In specific aspects of the disclosure, adult cardiac fibroblasts are reprogrammed into cardiomyocytes using viral vectors that harbor p63 shRNA and one or both of the transcription factors Hand2 and myocardin.

Abstract: A nuclear reactor in one embodiment includes a cylindrical body having an internal cavity, a nuclear fuel core, and a shroud disposed in the cavity. The shroud comprises an inner shell, an outer shell, and a plurality of intermediate shells disposed between the inner and outer shells. Pluralities of annular cavities are formed between the inner and outer shells which are filled with primary coolant such as demineralized water. The coolant-filled annular cavities may be sealed at the top and bottom and provide an insulating effect to the shroud. In one embodiment, the shroud may comprise a plurality of vertically-stacked self-supported shroud segments which are coupled together.

Abstract: A module for storing high level radioactive waste includes an outer shell, having a hermetically closed bottom end, and an inner shell forming a cavity and being positioned inside the outer shell to form a space therebetween. At least one divider extends from the top to the bottom of the inner shell to create a plurality of inlet passageways through the space, each inlet passageway connecting to a bottom portion of the cavity. A plurality of inlet ducts each connect at least one of the inlet passageways and ambient atmosphere, and each includes an inlet duct cover affixed atop a surrounding inlet wall, the inlet wall being peripherally perforated. A removable lid is positioned atop the inner shell and has at least one outlet passageway connecting the cavity and the ambient atmosphere, the lid and the top of the inner shell being configured to form a hermetic seal therebetween.

Abstract: A system and method for drying cavities containing spent nuclear fuel is devised. The invention utilizes a non-intrusive procedure that is based on monitoring the dew point temperature of a non-reactive gas that is circulated through the cavity. In one aspect, the invention is a system for drying a cavity loaded with spent nuclear fuel comprising a canister forming the cavity, the cavity having an inlet and an outlet; a source of non-reactive gas; means for flowing the non-reactive gas from the source of non-reactive gas through the cavity; and means for repetitively measuring the dew point temperature of the non-reactive gas exiting the cavity.

Abstract: A system and method for storing multiple canisters containing high level waste below grade that afford adequate ventilation of the spent fuel storage cavity. In one aspect, the invention is a ventilated system for storing high level waste emitting heat, the system comprising: an air-intake shell forming an air-intake cavity; a plurality of storage shells, each storage shell forming a storage cavity; a lid positioned atop each of the storage shells; an outlet vent forming a passageway between an ambient environment and a top portion of each of the storage cavities; and a network of pipes forming her sealed passageways between a bottom portion of the air-intake cavity and at least two different openings at a bottom portion of each of the storage cavities such that blockage of a first one of the openings does not prohibit air from flowing from the air-intake cavity into the storage cavity via a second one of the openings.

Abstract: A component cooling water system for a nuclear power plant. In one embodiment, the system includes an inner containment vessel housing a nuclear reactor and an outer containment enclosure structure. An annular water reservoir is formed between the containment vessel and containment enclosure structure which provides a heat sink for dissipating thermal energy. A shell-less heat exchanger is provided having an exposed tube bundle immersed in water held within the annular water reservoir. Component cooling water from the plant flows through the tube bundle and is cooled by transferring heat to the annular water reservoir. In one non-limiting embodiment, the tube bundle may be U-shaped.

Abstract: An alloy with tailored hardenability includes carbon, silicon, manganese, nickel, molybdenum, chromium, vanadium, and cobalt. A time and temperature transformation diagram of the alloy has a bainite nose and a ferrite nose that occur at approximately the same time at approximately 4 seconds at temperatures of about 750 K and 950 K, respectively.

Abstract: According to aspects of the disclosure, a method and system are provided for managing cell selection in a wireless communication network. In accordance with this disclosure, each cell in a radio access network (RAN) broadcasts a respective carrier-aggregation policy of the cell on its air interface. A UE engaging in a cell selection process reads the respective carrier-aggregation policy of each cell under consideration and selects a cell on which to attach based at least in part on the respective carrier-aggregation policies of the cells. The UE can then attach to the selected cell so that the selected cell can then serve the UE.

Abstract: A FIR filter includes segment cells, each of which is configurable as an interpolation filter, a decimation filter, a symmetric filter, or an asymmetric filter. Two or more of the segment cells are configurable to be cascaded to form an interpolation filter, a decimation filter, a symmetric filter, an asymmetric filter, a complex symmetric filter, or a complex asymmetric filter. The FIR filter includes registers corresponding to the segment cells for storing coefficient values of the corresponding segment cells. The FIR filter further includes control circuits corresponding to the segment cells for generating control signals.

Abstract: A nuclear steam supply system includes an elongated reactor vessel having an internal cavity with a central axis, a reactor core having nuclear fuel disposed within the internal cavity, and a steam generating vessel having at least one heat exchanger section, the steam generating vessel being fluidicly coupled to the reactor vessel. The reactor vessel includes a shell having an upper flange portion and a head having a head flange portion. The upper flange portion is coupled to the head flange portion, wherein the upper flange portion extends into the internal cavity, and the head flange portion extends outward from the internal cavity. Primary coolant flow between the steam generating vessel and reactor vessel occurs via a fluid coupling comprising direct welding between forged outer nozzles of each vessel and welded inner nozzles between each vessel inside the outer nozzles.

Abstract: A system for removing thermal energy generated by radioactive materials comprising: an air-cooled shell-and-tube heat exchanger comprising a shell and plurality of heat exchange tubes arranged in a substantially vertical orientation within the shell, the plurality of heat exchange tubes comprising interior cavities that collectively form a tube-side fluid path, the shell forming a shell-side fluid path that extends from an air inlet of the shell to an air outlet of the shell, the first air inlet located at a lower elevation than the air outlet; a heat rejection closed-loop fluid circuit comprising the tube-side fluid path of the air-cooled heat exchanger, a coolant fluid flowing through the heat rejection closed-loop fluid circuit, the heat rejection closed-loop fluid circuit thermally coupled to the radioactive materials so that thermal energy generated by the radioactive materials is transferred to the coolant fluid; and the air-cooled shell-and-tube heat exchanger transferring thermal energy from the coola

Abstract: A portable device including a gesture recognizer module for automatically detecting a specific sequence of gestures is described. The portable device may be used to detect a health, safety, or security related event. The portable device may further include an emergency event module for automatically determining whether the sequence of gestures corresponds to an emergency event. The portable device may further include a proximity detection module for automatically determining whether a mobile device corresponding to a user listed as an emergency contact is in a state of proximity to the portable device. The portable device may further include a notification module for automatically transmitting a message, indicating the emergency event, to the user of the mobile device determined to be in the state of proximity.

Abstract: A vertical bundle air-cooled heat exchanger. In one embodiment, the invention can be a vertical bundle air-cooled condenser comprising: at least one tube bundle assembly comprising: a tube bundle comprising a plurality of finned tubes arranged in a substantially vertical and side-by-side orientation, each of the plurality of finned tubes comprising a cavity; a top header pipe comprising an inlet header cavity operably coupled to a source of steam; a bottom header pipe comprising an outlet header cavity for collecting condensate; top ends of the plurality of finned tubes coupled to the top header pipe and the bottom ends of the plurality of finned tubes coupled to the bottom header pipe; and a shell having an open top end and open bottom end, the at least one tube bundle assembly positioned within the shell.

Abstract: In one aspect, the invention relates to substituted urea depsipeptide analogs, derivatives thereof, and related compounds, which are useful as activators the ClpP endopeptidease; synthesis methods for making the compounds; pharmaceutical compositions comprising the compounds; and methods of treating infectious disease using the compounds and compositions. This abstract is intended as a scanning tool for purposes of searching in the particular art and is not intended to be limiting of the present invention.

Abstract: A container and system for handling damaged nuclear fuel, and a method of making the same. In one embodiment, the invention is a damaged fuel container having a specially designed top cap that can be detachably coupled to the elongated tubular wall by simply translating the top cap into proper position within the elongated tubular wall, wherein biased locking elements automatically lock the top cap to the elongated tubular wall. In another embodiment, the vent screens of the damaged fuel container are integrally formed rather than being separate components. In still other embodiments, the lower vent screens are arranged on an upstanding portion of the damaged fuel container. In an even further embodiment, the elongated tubular wall is formed by an extrusion process.

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 rack having adjustable height pedestals.

Abstract: An autonomous self-powered system for cooling radioactive materials comprising: a pool of liquid; a closed-loop fluid circuit comprising a working fluid having a boiling temperature that is less than a boiling temperature of the liquid of the pool, the closed-loop fluid circuit comprising, in operable fluid coupling, an evaporative heat exchanger at least partially immersed in the liquid of the pool, a turbogenerator, and a condenser; one or more forced flow units operably coupled to the closed-loop fluid circuit to induce flow of the working fluid through the closed-loop fluid circuit; and the closed-loop fluid circuit converting thermal energy extracted from the liquid of the pool into electrical energy in accordance with the Rankine Cycle, the electrical energy powering the one or more forced flow units.

Abstract: A reactivity control device for storing nuclear fuel includes a top tube sheet, plurality of neutron absorber rods fixedly attached to the sheet, and a floating guide plate slideably mounted on the absorber rods for upward and downward movement between a lower position and an upper position. The reactivity control device is insertable into a spent fuel assembly in either wet storage in a spent fuel pool or dry storage in a canister. The absorber rods are inserted into empty guide tubes when the fuel assembly is removed from the nuclear fuel core normally occupied by control rods when in the reactor vessel. During installation, the device is lowered to insert the absorber rods into the guide tubes. The guide plate first engages the fuel assembly as the rods continue to slide through the plate until the tube sheet then engages the plate signaling the device is fully installed.

Abstract: A portable device including a gesture recognizer module for automatically detecting a specific sequence of gestures is described. The portable device may be used to detect a health, safety, or security related event. The portable device may further include an emergency event module for automatically determining whether the sequence of gestures corresponds to an emergency event. The portable device may further include a proximity detection module for automatically determining whether a mobile device corresponding to a user listed as an emergency contact is in a state of proximity to the portable device. The portable device may further include a notification module for automatically transmitting a message, indicating the emergency event, to the user of the mobile device determined to be in the state of proximity.