Nuclear reactor systems and associated devices and methods are described herein. A representative nuclear reactor system includes a reactor vessel having a barrier separating a core region from a shield region. A plurality of fuel rods containing a liquid nuclear fuel are positioned in the core region. A liquid moderator material is also positioned in the core region at least partially around the fuel rods. A plurality of heat exchangers can be positioned in the shield region, and a plurality of heat pipes can extend through the barrier. The moderator material is positioned to transfer heat received from the liquid nuclear fuel to the heat pipes, and the heat pipes are positioned to transfer heat received from the moderator material to the heat exchangers. The heat exchangers can transport the heat out of the system for use in one or more processes, such as generating electricity.

Nuclear reactor systems and associated devices and methods are described herein. A representative nuclear reactor system includes a reactor vessel having a barrier separating a core region from a shield region. A plurality of fuel rods containing a liquid nuclear fuel are positioned in the core region. A liquid moderator material is also positioned in the core region at least partially around the fuel rods. A plurality of heat exchangers can be positioned in the shield region, and a plurality of heat pipes can extend through the barrier. The moderator material is positioned to transfer heat received from the liquid nuclear fuel to the heat pipes, and the heat pipes are positioned to transfer heat received from the moderator material to the heat exchangers. The heat exchangers can transport the heat out of the system for use in one or more processes, such as generating electricity.

The present invention relates to a device adapted for producing energy by nuclear fission, the device comprising a core container of a core container material, which core container encloses an inner tubing of an inner tubing material, the inner tubing and/or the core container having an inlet and an outlet, the device further comprising a molten halide salt located in the core container or in the inner tubing, wherein the inner tubing comprises one or more sections consisting of single crystal corundum. The invention further relates to methods of controlling nuclear fission processes using the device and to the use of a corundum tube as a structural material in a nuclear fission device. The invention provides improved economy in molten salt nuclear fission processes.

The present invention relates to a device adapted for producing energy by nuclear fission, the device comprising a core container of a core container material, which core container encloses an inner tubing of an inner tubing material, the inner tubing and/or the core container having an inlet and an outlet, the device further comprising a molten halide salt located in the core container or in the inner tubing, wherein the inner tubing comprises one or more sections consisting of single crystal corundum. The invention further relates to methods of controlling nuclear fission processes using the device and to the use of a corundum tube as a structural material in a nuclear fission device. The invention provides improved economy in molten salt nuclear fission processes.

A system for a carbon neutral cycle of gas production may include a molten salt reactor configured to generate zero carbon dioxide (CO.sub.2) emissions electricity. The system may include a desalination unit configured to receive the zero-CO.sub.2 emissions electricity from the molten salt reactor and produce a desalinated water. The system may include an electrolysis unit configured to be powered by the zero-CO2 emissions electricity generated by the molten salt reactor and generate hydrogen (H.sub.2) and oxygen (O.sub.2) from the desalinated water. The system may include an oxy-combustion unit configured to receive and combust a hydrocarbon fuel with the O.sub.2 from the electrolysis unit to produce electricity and CO.sub.2. The system may include a CO.sub.2 capture system adapted to capture the CO.sub.2 produced by the oxy-combustion unit and a catalytic hydrogenation unit configured to receive and convert H.sub.2 from the electrolysis unit and CO.sub.2 from the CO.sub.2 capture system to produce the hydrocarbon fuel.

A system for a carbon neutral cycle of gas production may include a molten salt reactor configured to generate zero carbon dioxide (CO.sub.2) emissions electricity. The system may include a desalination unit configured to receive the zero-CO.sub.2 emissions electricity from the molten salt reactor and produce a desalinated water. The system may include an electrolysis unit configured to be powered by the zero-CO2 emissions electricity generated by the molten salt reactor and generate hydrogen (H.sub.2) and oxygen (O.sub.2) from the desalinated water. The system may include an oxy-combustion unit configured to receive and combust a hydrocarbon fuel with the O.sub.2 from the electrolysis unit to produce electricity and CO.sub.2. The system may include a CO.sub.2 capture system adapted to capture the CO.sub.2 produced by the oxy-combustion unit and a catalytic hydrogenation unit configured to receive and convert H.sub.2 from the electrolysis unit and CO.sub.2 from the CO.sub.2 capture system to produce the hydrocarbon fuel.

Configurations of molten fuel salt reactors are described that allow for active cooling of the containment vessel of the reactor by the primary coolant. Furthermore, naturally circulating reactor configurations are described in which the reactor cores are substantially frustum-shaped so that the thermal center of the reactor core is below the outlet of the primary heat exchangers. Heat exchanger configurations are described in which welded components are distanced from the reactor core to reduce the damage caused by neutron flux from the reactor. Radial loop reactor configurations are also described.

Configurations of molten fuel salt reactors are described that allow for active cooling of the containment vessel of the reactor by the primary coolant. Furthermore, naturally circulating reactor configurations are described in which the reactor cores are substantially frustum-shaped so that the thermal center of the reactor core is below the outlet of the primary heat exchangers. Heat exchanger configurations are described in which welded components are distanced from the reactor core to reduce the damage caused by neutron flux from the reactor. Radial loop reactor configurations are also described.

The invention relates to a nuclear reactor circuit that is capable of containing nuclear fuel-containing molten salt in a channel which is substantially vertically arranged and provides an up-down passage. The circuits can be used to build a modular reactor from removable, individual molten salt nuclear circuits one part of which (‘the channel’) has been placed in a critical configuration, wherein the channel contains a non-critical amount of nuclear material, but the channels together create the critical zone of the reactor core. The invention further relates to methods of operating a modular nuclear reactor circuit and a nuclear reactor.

The invention relates to a nuclear reactor circuit that is capable of containing nuclear fuel-containing molten salt in a channel which is substantially vertically arranged and provides an up-down passage. The circuits can be used to build a modular reactor from removable, individual molten salt nuclear circuits one part of which (‘the channel’) has been placed in a critical configuration, wherein the channel contains a non-critical amount of nuclear material, but the channels together create the critical zone of the reactor core. The invention further relates to methods of operating a modular nuclear reactor circuit and a nuclear reactor.