A method of generating power using a Thorium-containing molten salt fuel is disclosed. One example of the disclosed method includes the steps of providing a vessel containing a molten salt fuel, the molten salt fuel comprising Thorium and at least one salt containing a nucleus capable of interacting with a proton of sufficient energy to produce a (p, n) reaction resulting in the generation of a neutron at a first energy level and generating a proton beam externally to the vessel, where the externally generated proton beam being of an energy level sufficient to interact with the at least one salt in the vessel to produce a (p, n) reaction resulting in the generation of a neutron at the first energy level. In the example, the externally generated proton beam is directed into the vessel such that at least some protons forming the beam will interact with an atom forming a part of the at least one salt contained in the vessel to causing interaction between the externally generated proton beam and the at least one salt contained in the vessel to produce (p, n) reactions resulting in the generation of neutrons within the vessel and an absorption reaction involving the generated neutrons and Thorium within the vessel. Neutrons generated within the vessel through the (p, n) reactions caused by the externally generated proton's interaction with the at least one salt are utilized to produce a fission reaction where the fission reaction increases. the heat content of the molten salt within the vessel. In the example, a heat exchanger is used to extract heat from the molten salt within the vessel and power is generated from the extracted heat.

A method for providing a neutron source. The method including: providing a nuclear reactor neutron source, the nuclear reactor neutron source including: an enclosure delimiting a chamber, a nuclear reactor core arranged inside the chamber, the nuclear reactor core is configured to produce neutrons from a nuclear fuel element inside the nuclear reactor core; installing a beam generator arranged to generate a beam directed into the chamber; and installing, inside the chamber, a target arranged to eject neutrons upon impact of the beam such that neutrons are ejected from the target and emitted from the chamber.

A method for providing a neutron source. The method including: providing a nuclear reactor neutron source, the nuclear reactor neutron source including: an enclosure delimiting a chamber, a nuclear reactor core arranged inside the chamber, the nuclear reactor core is configured to produce neutrons from a nuclear fuel element inside the nuclear reactor core; installing a beam generator arranged to generate a beam directed into the chamber; and installing, inside the chamber, a target arranged to eject neutrons upon impact of the beam such that neutrons are ejected from the target and emitted from the chamber.

A method to determine a global core reactivity bias and the corresponding estimated critical conditions of a nuclear reactor core prior to achieving reactor criticality. The method first requires collection and evaluation of the inverse count rate ratio (ICRR) data; specifically, fitting measured ICRR vs. predicted ICRR data. The global core reactivity bias is then determined as the amount of uniform reactivity adjustment to the prediction that produces an ideal comparison between the measurement and the prediction.

A first system for producing a high flux of neutrons for non-destructive testing includes a dense plasma focus device neutronically coupled to a subcritical or sub-prompt critical fission assembly. The dense plasma focus device is a source of initiating neutrons for the fission assembly, and the fission assembly is configured to multiply a number of the initiating neutrons via inducing fission. A second system for producing a high flux of neutrons includes a gas-target neutron generator neutronically coupled to a subcritical or sub-prompt critical fission assembly. The gas-target neutron generator is a source of initiating neutrons for the fission assembly, and the fission assembly is configured to multiply a number of the initiating neutrons via inducing fission.

A first system for producing a high flux of neutrons for non-destructive testing includes a dense plasma focus device neutronically coupled to a subcritical or sub-prompt critical fission assembly. The dense plasma focus device is a source of initiating neutrons for the fission assembly, and the fission assembly is configured to multiply a number of the initiating neutrons via inducing fission. A second system for producing a high flux of neutrons includes a gas-target neutron generator neutronically coupled to a subcritical or sub-prompt critical fission assembly. The gas-target neutron generator is a source of initiating neutrons for the fission assembly, and the fission assembly is configured to multiply a number of the initiating neutrons via inducing fission.

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.

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.

A target well of a target delivery assembly for use in an irradiation system operative to allow irradiation of a radioisotope target via a vessel penetration of a fission reactor. The target well includes an outer tube and an inner tube disposed therein so that an annulus is formed therebetween. The target is positioned in the inner tube during irradiation. At least one flow channel extends between a bottom end of the outer tube and a bottom end of the inner tube. An elevation piston is slidably disposed within the inner tube to elevate the target, the elevation piston including a one-way check valve allowing flow in a downward direction and preventing flow in an upward direction.

An example of a system for producing and collecting one or more radioisotopes includes one or more fractional distillation columns that can receive a mixture and produce one or more radioisotopes using the mixture by fractional distillation. In various embodiments, a molten-salt nuclear reactor produces the mixture including one or more fission products. In various embodiments, the mixture includes helium gas carrying the one or more fission products, and the one or more radioisotopes include tritium.