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: A system for removing thermal energy generated by radioactive materials is provided. The system comprises 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 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 air inlet at a lower elevation than the air outlet; a heat rejection closed-loop fluid circuit comprising the tube-side fluid path, 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; and the air-cooled shell-and-tube heat exchanger transferring thermal energy from the coolant fluid flowing through the tube-side fluid path to air flowing through the shell-side fluid path.

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: A nuclear reactor cooling system with passive cooling capabilities operable during a reactor shutdown event without available electric power. In one embodiment, the system includes a reactor vessel with nuclear fuel core and a steam generator fluidly coupled thereto. Primary coolant circulates in a flow loop between the reactor vessel and steam generator to heat secondary coolant in the steam generator producing steam. The steam flows to a heat exchanger containing an inventory of cooling water in which a submerged tube bundle is immersed. The steam is condensed in the heat exchanger and returned to the steam generator forming a closed flow loop in which the secondary coolant flow is driven by natural gravity via changes in density from the heating and cooling cycles. In other embodiments, the cooling system is configured to extract and cool the primary coolant directly using the submerged tube bundle heat exchanger.

Abstract: A nuclear reactor cooling system with passive cooling capabilities operable during a reactor shutdown event without available electric power. In one embodiment, the system includes a reactor vessel with nuclear fuel core and a steam generator fluidly coupled thereto. Primary coolant circulates in a flow loop between the reactor vessel and steam generator to heat secondary coolant in the steam generator producing steam. The steam flows to a heat exchanger containing an inventory of cooling water in which a submerged tube bundle is immersed. The steam is condensed in the heat exchanger and returned to the steam generator forming a closed flow loop in which the secondary coolant flow is driven by natural gravity via changes in density from the heating and cooling cycles. In other embodiments, the cooling system is configured to extract and cool the primary coolant directly using the submerged tube bundle heat exchanger.

Abstract: A nuclear steam supply system having a shutdown system for removing residual decay heat generated by a nuclear fuel core. The steam supply system may utilize gravity-driven primary coolant circulation through hydraulic-ally interconnected reactor and steam generating vessels forming the steam supply system. The shutdown system may comprise primary and secondary coolant systems. The primary coolant cooling system may include a jet pump comprising an injection nozzle disposed inside the steam generating vessel A portion of the circulating primary coolant is extracted, pressurized and returned to the steam generating vessel to induce coolant circulation under reactor shutdown conditions. The extracted primary coolant may further be cooled before return to the steam generating vessel in some operating modes. The secondary coolant cooling system includes a pumped and cooled flow circuit operating to circulate and cool the secondary coolant, which in tun extracts heat from and cools the primary coolant.

Abstract: A nuclear steam supply system utilizing gravity-driven natural circulation for primary coolant flow through a fluidly interconnected reactor vessel and a steam generating vessel. In one embodiment, the steam generating vessel includes a plurality of vertically stacked heat exchangers operable to convert a secondary coolant from a saturated liquid to superheated steam by utilizing heat gained by the primary coolant from a nuclear fuel core in the reactor vessel. The secondary coolant, may be working fluid associated with a Rankine power cycle turbine-generator set in some embodiments. The steam generating vessel and reactor vessel may each be comprised of vertically elongated shells, which in one embodiment are arranged in lateral adjacent relationship. In one embodiment, the reactor vessel and steam generating vessel are physically discrete self-supporting structures which may be physically located in the same containment vessel.

Abstract: An autonomous facility for storing spent nuclear fuel in one embodiment includes a building forming an enclosed interior space containing a water-filled spent fuel pool. The pool includes fuel racks containing spent fuel assemblies which heat the water via radioactive decay. A passive cooling system includes a submerged heat exchanger in the pool and an air cooled heat exchanger located in ambient air outside the building at a higher elevation than the pool heat exchanger. A heat transfer working fluid circulates in a closed flow loop between the heat exchangers via unpumped natural gravity driven flow to cool the fuel pool. The air cooled heat exchanger may be enclosed in a concrete reinforced silo adjoining the building for impact protection. The building may include a cask pit formed integrally with the pool to allow fuel assembles to be removed from a transport cask and loaded into the fuel rack underwater.

Abstract: A vehicle seat having a seat back pivotably coupled to a seat base by a seat recliner mechanism such that the seat back can be pivoted in a forward and rearward direction relative the seat base. The seat includes a track assembly coupled to the vehicle and the seat, such that the seat can be moved in the forward and rearward directions relative to the vehicle interior. The seat further includes an actuator mechanism having a first actuator that includes a push button located on the seat and an actuator in electrical communication with the push button, A force transmitting device has one end connected to the actuator and a second end connected to the seat recliner mechanism, such that energizing the actuator actuates the force transmitting device to release the seat recliner mechanism and move the seat between a use and a tipped and forward position.

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: A passively-cooled spent nuclear fuel pool system in one embodiment includes a containment vessel comprising a thermally conductive shell and an annular reservoir surrounding the shell that holds a liquid coolant forming a heat sink. A spent fuel pool is disposed inside the containment vessel and includes a body of water in contact with a first peripheral sidewall of the fuel pool. At least one spent nuclear fuel rod submerged in the body of water heats the water. The first peripheral sidewall of the spent fuel pool is formed by a portion of the shell of the containment vessel adjacent to the fuel pool, thereby defining a shared common heat transfer wall. The heat transfer wall operates to transfer heat from the body of water in the spent fuel pool to the heat sink to cool the body of water. The heat transfer wall comprises metal in one embodiment.

Abstract: A nuclear power generation system and related power cycle are disclosed, in one embodiment, the system includes primary coolant circulation through a hydraulically interconnected reactor containing nuclear fuel and a steam generating vessel collectively defining a steam supply system. Liquid secondary coolant for the power cycle flows through the steam generating vessel and is converted to steam by the primary coolant to drive a low pressure turbine of a turbine-generator set. Steam exiting the turbine is condensed and heated prior to return to the steam supply system, thereby completing a secondary coolant flow loop. In one embodiment, a majority of the secondary coolant heating occurs within the steam generating vessel via heat exchange with the primary coolant rather than externally in the secondary coolant flow loop.

Abstract: A nuclear steam supply system having a start-up sub-system for heating a primary coolant. In one embodiment, the invention can be a nuclear steam supply system comprising: a reactor vessel having an internal cavity, a reactor core comprising nuclear fuel disposed within the internal cavity; a steam generating vessel fluidly coupled to the reactor vessel; a primary coolant loop formed within the reactor vessel and the steam generating vessel, a primary coolant in the primary coolant loop; and a start-up sub-system fluidly coupled to the primary coolant loop, the start-up sub-system configured to: (1) receive a portion of the primary coolant from the primary coolant loop; (2) heat the portion of the primary coolant to form a heated portion of the primary coolant; and (3) inject the heated portion of the primary coolant into the primary coolant loop.

Abstract: A passively-cooled spent nuclear fuel pool system and method therefor. In one embodiment, the invention can be a passively-cooled spent nuclear fuel pool system comprising: a spent nuclear fuel pool comprising a body of liquid water having a surface level, at least one spent nuclear fuel rod submerged in the body of liquid water that heats the body of liquid water; a lid covering the spent nuclear fuel pool to create a hermetically sealed vapor space between the surface level of the body of liquid water and the lid; and a passive heat exchange sub-system fluidly coupled to the vapor space, the passive heat exchange sub-system configured to: (1) receive water vapor from the vapor space; (2) remove thermal energy from the received water vapor, thereby condensing the water vapor to form a condensed water vapor; and (3) return the condensed water vapor to the body of liquid water.

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.

Abstract: A nuclear steam supply system utilizing gravity-driven natural circulation for primary coolant flow through a fluidly interconnected reactor vessel and a steam generating vessel. In one embodiment, the steam generating vessel includes a plurality of vertically stacked heat exchangers operable to convert a secondary coolant from a saturated liquid to superheated steam by utilizing heat gained by the primary coolant from a nuclear fuel core in the reactor vessel. The secondary coolant may be working fluid associated with a Rankine power cycle turbine-generator set in some embodiments. The steam generating vessel and reactor vessel may each be comprised of vertically elongated shells, which in one embodiment are arranged in lateral adjacent relationship. In one embodiment, the reactor vessel and steam generating vessel are physically discrete self-supporting structures which may be physically located in the same containment vessel.

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.

Abstract: A nuclear reactor cooling system with passive cooling capabilities operable during a loss-of-coolant accident (LOCA) without available electric power. The system includes a reactor vessel with nuclear fuel core located in a reactor well. An in-containment water storage tank is fluidly coupled to the reactor well and holds an inventory of cooling water. During a LOCA event, the tank floods the reactor well with water. Eventually, the water heated by decay heat from the reactor vaporizes producing steam. The steam flows to an in-containment heat exchanger and condenses. The condensate is returned to the reactor well in a closed flow loop system in which flow may circulate solely via gravity from changes in phase and density of the water. In one embodiment, the heat exchanger may be an array of heat dissipater ducts mounted on the wall of the inner containment vessel surrounded by a heat sink.

Abstract: A nuclear reactor cooling system with passive cooling capabilities operable during a reactor shutdown event without available electric power. In one embodiment, the system includes a reactor vessel with nuclear fuel core and a steam generator fluidly coupled thereto. Primary coolant circulates in a flow loop between the reactor vessel and steam generator to heat secondary coolant in the steam generator producing steam. The steam flows to a heat exchanger containing an inventory of cooling water in which a submerged tube bundle is immersed. The steam is condensed in the heat exchanger and returned to the steam generator forming a closed flow loop in which the secondary coolant flow is driven by natural gravity via changes in density from the heating and cooling cycles. In other embodiments, the cooling system is configured to extract and cool the primary coolant directly using the submerged tube bundle heat exchanger.

Abstract: A food tracing and tracking system, method, and computer-program product are provided. The present invention allows companies that operate within these supply-chains, to exchange information bi-directionally throughout the entire supply-chain while maintaining data integrity and appropriate levels of security at all times and in real-time. The present invention enables a continuous linkage across the supply-chain-entities and changing of supply-chain entities in near real-time and ensures data integrity and data security, performs language translation, maintains a continuous history over time without the need for data conversion, and provides each entity within the supply chain the option of publishing their identity and data to the other supply chain entities. New fields can be added as needed for processes and materials. The present invention supports distributed data hosted on various machines by various organizations over a public or private data network.