Embodiments of the present invention pertain to a power system utilizing a uranium-based reactor for space missions. For example, the power system may include a reactor configured to generate thermal energy using a uranium core. A plurality of heat pipes may be configured to transfer thermal energy from the reactor core to a plurality of Stirling engines to generate electricity for a spacecraft.

Embodiments of the present invention pertain to a power system utilizing a uranium-based reactor for space missions. For example, the power system may include a reactor configured to generate thermal energy using a uranium core. A plurality of heat pipes may be configured to transfer thermal energy from the reactor core to a plurality of Stirling engines to generate electricity for a spacecraft.

A transportable nuclear power system is provided. The system includes a nuclear power generator. The nuclear power generator includes one or more fuel cartridges configured to form a critical core during a power generation operation, each of the one or more fuel cartridges containing a nuclear fuel. The nuclear power generator also includes a reactivity controller and one or more working fluid conduits, each work fluid conduit containing a working fluid circulating within each of the one or more fuel cartridges to cool the nuclear fuel and execute a thermodynamic cycle. The system also includes an Intermodal transport container including a support structure mounted inside the transport container to support at least the one or more fuel cartridges of the nuclear power generator. The one or more fuel cartridges of the nuclear power generator are contained in the transport container during the power generation operation.

The present invention relates generally to electric power and process heat generation using a modular, compact, transportable, hardened nuclear generator rapidly deployable and retrievable, comprising power conversion and electric generation equipment fully integrated within a single pressure vessel housing a nuclear core. The resulting transportable nuclear generator does not require costly site-preparation, and can be transported fully operational. The transportable nuclear generator requires an emergency evacuation area substantially reduced with respect to other nuclear generators as it may be configured for operation with a melt-proof conductive ceramic core which allows decay heat removal even under total loss of coolant scenarios.

A flow control device configured to be positioned in a reactor core. The flow control device including a central shaft and at least one blade extending helically from the central shaft. A nuclear reactor and related systems and methods are also disclosed.

A power conversion system for converting thermal energy from a heat source to electricity is provided. The system includes a chamber including an inner shroud having an inlet and an outlet and defining an internal passageway between the inlet and the outlet through which a working fluid passes. The chamber also includes an outer shroud substantially surrounding the inner shroud. The chamber includes a source heat exchanger disposed in the internal passageway, the source heat exchanger being configured to receive a heat transmitting element associated with the heat source external to the chamber, and to transfer heat energy from the heat transmitting element to the working fluid. The system also includes a compressor disposed adjacent the inlet of the inner shroud and configured to transfer energy from the compressor to the working fluid, and an expander disposed adjacent the outlet of the inner shroud.

A closed-vessel molten salt reactor (cvMSR) is described herein. A cvMSR may comprise a suspended container, such as a metallic container, within a trench surrounded by a concrete enclosure and a concrete cover having a number of channels. The container is rotatable between different orientations. The container may be hollow and a solution of fissile materials and salt materials may be provided within the container. The solution may be capable of undergoing a chain reaction nuclear fission process once a threshold temperature is reached. Heat generated by the solution may heat a fluid surrounding the container. The heated fluid may be transported, through the number of channels of the concrete cover, to an external location where the heated fluid may be used in distributing heat and/or electricity generation.

The invention relates to the field of nuclear energy, more particularly to low-power and particularly low-power reactors. A nuclear reactor contains a housing with a reflector which forms a reactor core. The core has arranged therein primary process tubes, which are intended for circulating a coolant, and secondary process tubes, which are intended for accommodating elements of a control and protection system. The reactor also contains an intake chamber for coolant of a primary loop, and a discharge chamber for coolant of the primary loop, which are separated by a partition. The primary process tubes are designed in the form of Field tubes, the outer tubes of which are secured on the bottom of the intake chamber for the coolant of the primary loop, and the inner tubes are secured on the partition. Fuel assemblies are mounted in the inner tubes of the Field tubes on suspensions, which are secured on an upper portion of the discharge chamber for the coolant of the primary loop. The secondary process tubes are sealed off from the intake and discharge chambers for the coolant of the primary loop, and the inter-tube space of the core is filled with a medium or material which is transparent to neutrons.

The invention relates to the field of nuclear energy, more particularly to low-power and particularly low-power reactors. A nuclear reactor contains a housing with a reflector which forms a reactor core. The core has arranged therein primary process tubes, which are intended for circulating a coolant, and secondary process tubes, which are intended for accommodating elements of a control and protection system. The reactor also contains an intake chamber for coolant of a primary loop, and a discharge chamber for coolant of the primary loop, which are separated by a partition. The primary process tubes are designed in the form of Field tubes, the outer tubes of which are secured on the bottom of the intake chamber for the coolant of the primary loop, and the inner tubes are secured on the partition. Fuel assemblies are mounted in the inner tubes of the Field tubes on suspensions, which are secured on an upper portion of the discharge chamber for the coolant of the primary loop. The secondary process tubes are sealed off from the intake and discharge chambers for the coolant of the primary loop, and the inter-tube space of the core is filled with a medium or material which is transparent to neutrons.

Various embodiments of a transportable nuclear power generator having a plurality of subcritical power modules are disclosed. Each of the plurality of subcritical power modules includes a fuel cartridge, a power conversion unit, and a housing substantially enclosing the fuel cartridge and the power conversion unit. The fuel cartridge contains a nuclear fuel and has a proximal end and a distal end. The power conversion unit includes a compressor turbine disposed at the proximal end of the fuel cartridge and a power turbine disposed at the distal end of the fuel cartridge. At least one of the plurality of subcritical power modules is movable with respect to the other of the plurality of subcritical power modules between a first position and a second position to control criticality of the nuclear fuel contained in the fuel cartridges of the plurality of subcritical power modules.