Abstract: A canned rotodynamic flow machine (1) configured for operating with a working fluid such as molten salt of a molten salt nuclear reactor. The stator windings are formed by one or more electrically conductive solid bars (12).

Abstract: A power generation system for a nuclear reactor includes an externally-heated turbine engine, a reactor heat exchanger, and a heat recuperating system. The externally-heated turbine engine produces compressed air that is heated by the reactor heat exchanger. The heat recuperating system includes a heat exchanger thermally connected to the externally-heated turbine engine to transfer heat to the compressed air to supplement the reactor heat exchanger.

Abstract: Asteroid redirection systems are provided that use cosmic ray and muon-catalyzed micro-fusion. These systems include a micro-fusion propulsion system providing thrust for redirecting an asteroid, as well as micro-fusion electrical generation powering an ion drive. The systems deploy deuterium-containing fuel material as a localized cloud interacting with incoming ambient cosmic rays to generate energetic fusion products. Dust or other particulate matter in the fuel material converts some cosmic rays into muons that also catalyze fusion. The fusion products provide thrusting upon the asteroid, or when produced near turbines facilitates electrical generation, which can then power an ion drive.

Abstract: A method and arrangement for utilizing waste heat that includes a waste heat exchanger, at least two turbines, at least two recuperators, at least two cooler units, and at least two pumps and/or compressors as components, wherein all components are arranged in a single fluid cycle, where the waste heat exchanger heats up a fluid with heat from a waste heat source, the heated fluid flows through a first set of the at least one turbine, the at least one recuperator, the at least one cooler unit, and the at least one pump and/or compressor, and then flows through at least a second set the at least one turbine, the at least one recuperator, the at least one cooler unit, and the at least one pump and/or compressor with the same components arranged in series downstream of the first set.

Abstract: An improved gas circulator for a gas-cooled nuclear reactor system is disclosed which includes a stator, a rotor having a rotor shaft, and an impeller attached to one end thereof. A radial active magnetic bearing and a radial backup bearing are positioned proximate each end of the rotor shaft. An axial active magnetic bearing is also located between the ends of the rotor shaft, as is an axial backup bearing, with two of the backup bearings enclosed within a sealed chamber that may contain a lubricant, for example, a solid lubricant or a liquid lubricant. Preferably, the gas circulator is installed in a nuclear reactor system with the rotor shaft in a substantially vertical orientation and the sealed chamber near the bottom of the rotor shaft. The lower radical backup bearing and the axial backup bearing are advantageously located within the sealed chamber.

Abstract: A closure hold-down system for a prestressed concrete reactor vessel is disclosed which employs a concrete plug having an annular liner thereon and adapted to be received within the upper open end of a cavity in the reactor vessel. A prestressed concrete retaining ring is mounted on the reactor vessel concentric to the plug through a plurality of circumferentially spaced prestressed tendons anchored directly to the reactor vessel, and engages the concrete plug so that pressure forces acting on the plug from within the cavity are transmitted directly from the plug to the prestressed retaining ring through a contact surface therebetween. An omega seal is disposed between the closure plug and a cavity liner to prevent escape of fluid pressure from the cavity.

Abstract: A cooling system for a gas-cooled nuclear reactor is disclosed which includes at least one primary cooling loop adapted to pass coolant gas from the reactor core and an associated steam generator through a duct system having a main circulator therein, and at least one auxiliary cooling loop having communication with the reactor core and adapted to selectively pass coolant gas through an auxiliary heat exchanger and circulator. The main and auxiliary circulators are installed in a common vertical cavity in the reactor vessel, and a common return duct communicates with the reactor core and intersects the common cavity at a junction at which is located a flow diverter valve operative to effect coolant flow through either the primary or auxiliary cooling loops.

Abstract: A nuclear reactor system is described wherein a prestressed concrete reactor vessel is provided with a main cavity for the reactor core and at least one subsidiary cavity for a steam generator. At least two feedwater penetrations are provided in the reactor vessel communicating between the exterior of the reactor vessel and the subsidiary cylindrical cavity. A superheater penetration is provided aligned with the axis of the cavity with the feedwater penetrations and the superheater penetration having mutually parallel axes. Superheater outlet means are positioned in the superheater penetration and include a tubesheet positioned a substantial distance from both the subsidiary cylindrical cavity and the exterior of the reactor vessel.