Abstract: Provided is an apparatus for generating electricity comprising a gas propellant chamber, a containment vessel, and a rotor/stator assembly partially integrated within the containment vessel. The gas propellant chamber is disposed within the containment vessel and comprises a compressor, a nuclear fuel chamber, and a turbine assembly, wherein a drive shaft extending axially through the gas propellant chamber couples the compressor to the turbine assembly. The rotor of the rotor/stator assembly is disposed internally of the containment vessel and is in communication with the stator, the stator being disposed externally of the containment vessel. The apparatus thereby provides a simpler and safer design that is both scalable and adaptable. The apparatus is easily and safely transportable and can be designed to be highly nuclear-proliferation-resistant.

Abstract: An energy recapturing apparatus is disclosed. The energy recapturing apparatus is housed within a frame that is configured to fit within a preexisting fluid passageway. The frame is further attached to a sliding mechanism, which enables the frame to be easily removed from the preexisting fluid passageway. Further, the frame is configured to accept at least one turbine that contains a plurality of blades. The turbine is able to convert the energy of fluid movement into electricity.

Abstract: A compact metal containment vessel, for a boiling water nuclear reactor, includes in one exemplary embodiment, a bottom head, a removable top head, and a substantially cylindrical sidewall extending from the bottom head to the top head. The bottom head, top head and cylindrical sidewall define a containment cavity sized to receive and enclose a reactor pressure vessel. The containment vessel has a pressure rating of at least about 50 atmospheres atm.

Abstract: A jet pump assembly for recirculating coolant through a recirculation loop of a boiling water reactor vessel, the jet pump assembly comprises a jet pump in operative association with the recirculation loop for forcing the coolant through the recirculation loop. A beam is positioned adjacent and in operative association with the jet pump for assisting in maintaining the positional relationship of the jet pump. A bolt is inserted in the beam for resisting the hydraulic forces generated in the jet pump, and an insert is disposed in said beam for receiving and surrounding the bolt which, in turn, reduces stress on the beam.

Abstract: An apparatus and method are provided for suppressing the formation of vortices in circulating coolant fluid of a nuclear reactor. A vortex-suppressing plate having a plurality of openings therein is suspended within the lower plenum of a reactor vessel below and generally parallel to the main core support of the reactor. The plate is positioned so as to intersect vortices which may form in the circulating reactor coolant fluid. The intersection of the plate with such vortices disrupts the rotational flow pattern of the vortices, thereby disrupting the formation thereof.

Abstract: A liquid metal cooled nuclear fission reactor plant having a passive auxiliary safety cooling system for removing residual heat resulting from fuel decay during reactor shutdown, or heat produced during a mishap. This reactor plant is enhanced by a backup or secondary passive safety cooling system which augments the primary passive auxiliary cooling system when in operation, and replaces the primary system when rendered inoperable.

Abstract: A high temperature reactor has a downflow type nuclear reactor provided at the top portion thereof with a gas inlet and a plurality of steam generators provided around the nuclear reactor. The steam generator has a heat insulation tube provided vertically from the bottom portion of the nuclear reactor to a level higher than the top gas inlet of the reactor, a heat exchanger provided in a descending gas flow path formed around the heat insulation tube, and a gas circulator provided at the bottom portion thereof for feeding a gas coolant to the gas inlet of the nuclear reactor, whereby said gas coolant, after being used for cooling the reactor core, delivered from the bottom portion of the reactor, flows into the heat insulation tube, flows upward to the top portion of the tube, is reversed in direction at the top end of the tube, then flows downward through the descending gas flow where the heat exchanger is provided, and is then recycled to the gas inlet flow path of the reactor by the gas circulator.

Abstract: A high-temperature nuclear power plant, includes a reactor, an inner vessel enclosing the reactor, an outer reactor pressure vessel disposed outside the inner vessel, a stub integral with the outer vessel, and a hot gas pipeline disposed in the stub, the improvement comprises a screw connection being releasable from outside the outer vessel for fastening the hot gas pipeline to the inner vessel, and a device connected to the hot gas pipeline for applying a force to the hot gas pipeline in a direction tending to separate the hot gas pipeline from the inner vessel.

Abstract: A gas-cooled nuclear reactor includes a central core located in the lower portion of a prestressed concrete reactor vessel. Primary coolant gas flows upward through the core and into four overlying heat-exchangers wherein stream is generated. During normal operation, the return flow of coolant is between the core and the vessel sidewall to a pair of motor-driven circulators located at about the bottom of the concrete pressure vessel. The circulators repressurize the gas coolant and return it back to the core through passageways in the underlying core structure.If during emergency conditions the primary circulators are no longer functioning, the decay heat is effectively removed from the core by means of natural convection circulation. The hot gas rising through the core exits the top of the shroud of the heat-exchangers and flows radially outward to the sidewall of the concrete pressure vessel.

Abstract: Nuclear boiler comprising a vessel sealed in its upper part by a removable cover, a basket-shaped member carrying the reactor core and separating the vessel into a hot inner area and a cold outer area, at least one steam generator positioned within the vessel and comprising a tightly sealed enclosure and a tube plate separating the enclosure into a primary part or water box and a secondary part, the tube plate carrying U-tubes, whose ends issue into a cold area and a hot area of the water box, defined by an inner structure, two linear, coaxial tubes defining an inner pipe and an annular outer pipe respectively connecting the hot areas and cold areas of the vessel and the water box, wherein a removable safety sleeve, whose wall is designed to resist the pressure in the primary circuit, is arranged coaxially within the outer annular pipe and defines with the latter a calibrated clearance making it possible to limit to a given value the leakage flow if the outer tube fractures.

Abstract: An improved design for shielding the component parts of a gas turbine power plant from radiation in a gas transport conduit is disclosed. The radiation shield and shielded gas conduit utilize a shielding arrangement comprising a displacement body arranged centrally within the conduit and a shielding annulus surrounding the displacement body. A shielding device provides for a first annular flow path for reactor cooling gas between the displacement body and shielding annulus and a second annular flow path for reactor cooling gas between the shielding annulus and the conduit housing. The shielding device provides protection against radiation without significantly disrupting the flow of the cooling gas in the conduits.

Abstract: The present invention relates to a nuclear boiler comprising a vessel whose top is closed by a dismountable cover, a cage bearing the core of the reactor and separating the vessel into an inner hot zone and an outer cold zone, at least one steam generator disposed outside the vessel and comprising a tight enclosure, a tube plate, separating the enclosure into a primary part, or water box, and a secondary part, and bearing U-shaped tubes whose ends open into two concentric zones of the water box separated by an internal structure, at least one hot connecting pipe and one cold connecting pipe respectively connecting the hot zone and the cold zone of the vessel to each of the concentric zones of the water box, wherein the tube plate, the tubes and the secondary part of the enclosure of the steam generator define a sub-assembly dismountable from the primary part of the enclosure, the hot connecting pipe being dismountably mounted between the cage and the internal structure of the water box, this strucutre itself