This disclosure describes nuclear fuel salts usable in certain molten salt reactor designs and related systems and methods. Binary, ternary and quaternary chloride fuel salts of uranium, as well as other fissionable elements, are described. In addition, fuel salts of UCl.sub.xF.sub.y are disclosed as well as bromide fuel salts. This disclosure also presents methods and systems for manufacturing such fuel salts, for creating salts that reduce corrosion of the reactor components and for creating fuel salts that are not suitable for weapons applications.

This disclosure describes nuclear fuel salts usable in certain molten salt reactor designs and related systems and methods. Binary, ternary and quaternary chloride fuel salts of uranium, as well as other fissionable elements, are described. In addition, fuel salts of UCl.sub.xF.sub.y are disclosed as well as bromide fuel salts. This disclosure also presents methods and systems for manufacturing such fuel salts, for creating salts that reduce corrosion of the reactor components and for creating fuel salts that are not suitable for weapons applications.

A molten salt reactor comprising a reactor vessel and a molten salt contained within the reactor vessel. There is a corrosion reduction unit configured to process the molten salt to maintain an oxidation reduction ratio, (E(o)/E(r)), in the molten salt at a substantially constant level, wherein E(o) is an element (E) at a higher oxidation state (o) and E(r) is the element (E) at a lower oxidation state (r).

A molten salt reactor comprising a reactor vessel and a molten salt contained within the reactor vessel. There is a corrosion reduction unit configured to process the molten salt to maintain an oxidation reduction ratio, (E(o)/E(r)), in the molten salt at a substantially constant level, wherein E(o) is an element (E) at a higher oxidation state (o) and E(r) is the element (E) at a lower oxidation state (r).

A power system can connect to a nuclear reactor through a standardized connection. The standardized connection is configured so that the nuclear reactor may be designed independently of the power system. Systems include a reactor core in fluid communication with a heat exchanger. A fluid loop passes through the heat exchanger. The system includes an output and inlet manifolds at the ends of the fluid loop, terminating in ports that include a standardized connection mechanism. When the secondary system is coupled to the connection mechanism, the fluid loop and the secondary system define a distal loop. A working fluid can then flow through the distal loop and transfer heat from the reactor core to the secondary system.

A power system can connect to a nuclear reactor through a standardized connection. The standardized connection is configured so that the nuclear reactor may be designed independently of the power system. Systems include a reactor core in fluid communication with a heat exchanger. A fluid loop passes through the heat exchanger. The system includes an output and inlet manifolds at the ends of the fluid loop, terminating in ports that include a standardized connection mechanism. When the secondary system is coupled to the connection mechanism, the fluid loop and the secondary system define a distal loop. A working fluid can then flow through the distal loop and transfer heat from the reactor core to the secondary system.

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 molten salt nuclear reactor a neutron moderator core that has an inner region that defines channels of a first diameter separated by a first pitch and, an outer region that defines channels of a second diameter separated by a second pitch. The first diameter is larger than the second diameter and the first pitch is larger than the second pitch. This configuration allows for an increased capture of neutrons by fertile elements in the outer region. That is, less neutrons are lost to the outside of the core. The configuration is such that the neutron multiplication factor is larger than one in the inner portion and lower than one in the outer portion.

A molten salt nuclear reactor a neutron moderator core that has an inner region that defines channels of a first diameter separated by a first pitch and, an outer region that defines channels of a second diameter separated by a second pitch. The first diameter is larger than the second diameter and the first pitch is larger than the second pitch. This configuration allows for an increased capture of neutrons by fertile elements in the outer region. That is, less neutrons are lost to the outside of the core. The configuration is such that the neutron multiplication factor is larger than one in the inner portion and lower than one in the outer portion.

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.