Abstract: A power production installation including a primary circuit containing gas passing via a nuclear reactor, via a first heat exchanger, and via a blower. A secondary circuit containing incondensable gas passes via the first heat exchanger, and via a turbine and a compressor fitted on the same shaft. The blower is driven by the shaft. The gases in the primary and secondary circuits are of the same nature, and the pressure in the secondary circuit is automatically regulated by the pressure in the primary circuit.

Abstract: Disclosed herein is a method comprising heating helium in a core of a nuclear reactor; extracting heat from the helium; superheating water to steam using the heat extracted from the helium, expanding the helium in a turbine; wherein the turbine is in operative communication with an electrical generator; and generating electricity in the electrical generator.

Abstract: An upper plenum structure of a cooled pressure vessel for a prismatic very high temperature reactor which secures a space for coolant to supply to a core and also supports an upper reflector located inside a graphite structure on top of the core. The upper plenum structure includes a cavity structure where the coolant goes down in the upper plenum structure, a plurality of upper reflector supports formed with the cavity and supporting the upper reflector located on top thereof, and a plurality of coolant distributing blocks. Each of the coolant distributing blocks is coupled with a bottom portion of a respective one of the upper reflector supports and is located on top of the core in order to distribute the coolant collected in a cavity, formed by the upper reflector support, to the core. The coolant distributing blocks cooperate with the upper reflector supports to define the cavity structure.

Abstract: Disclosed herein is a method comprising heating helium in a core of a nuclear reactor; extracting heat from the helium; superheating water to steam using the heat extracted from the helium; expanding the helium in a turbine; wherein the turbine is in operative communication with an electrical generator; and generating electricity in the electrical generator.

Abstract: A nuclear thermal rocket engine is provided with an integrated and compact construction that facilitates vehicle size and weight reduction. The engine includes a nuclear reactor core having multiple fuel assemblies and moderator rods disposed therebetween. A reactor vessel surrounds a reflector assembly which surrounds the core and includes multiple passages formed therein for circulating coolant therethrough. The reactor vessel is surrounded by a nozzle assembly which includes a nozzle block having a plenum fluidly coupled to the outlets of the fuel assemblies and a nozzle throat region. Multiple struts extend from the reactor vessel and through the nozzle throat region to divide that region into multiple nozzle throats. Each strut includes multiple channels for circulating coolant (e.g.

Abstract: A system for increasing the temperature of a fluid heated by a high temperature gas cooled nuclear reactor to a sufficient temperature to supply the heat of reaction for a high temperature chemical process. The system includes a secondary loop having a working fluid heated to a first temperature by the nuclear reactor, and has a heat pump connected in the secondary loop and adapted to increase and thereby augment the temperature of the working fluid in the secondary loop sufficiently to supply the heat of reaction for a high temperature chemical process such as in a reformer. The system also provides low temperature heat in the form of steam which may be used in a turbine to provide power to the compressor of the heat pump and for auxilliary apparatus.

Abstract: A system for producing process heat which employs a high temperature gas cooled nuclear reactor and is adapted to provide process heat at temperatures higher than the reactor core temperature. The system includes a closed secondary loop having a working fluid heated to a first temperature by the coolant of the reactor core in an intermediate heat exchanger, and has a heat pump connected in the secondary loop which increases the temperature of the working fluid to a temperature above the core coolant temperature. Steam in an independent closed nuclear steam supply circuit is heated directly by the core coolant in a steam generator and provides steam for make-up driving power to the heat pump in the secondary loop. The steam supply circuit also supplies additional steam to generate electric power and process steam. The size of the intermediate heat exchanger is minimized to enable maximum utilization of the steam supply circuit.