An electromagnetic pump (EMP) for a liquid metal-cooled nuclear reactor includes a pump casing, concentric inner and outer flow ducts collectively defining a flow annulus extending coaxially with a longitudinal axis of the EMP, and induction coils configured to control the flow of liquid metal coolant through the flow annulus based on electrical power received from the power supply. At least one of the inner flow duct or the outer flow duct includes a gamma shielding material configured to block gamma rays from entering an interior of the EMP from the flow annulus. The pump casing may include a neutron absorber material configured to absorb neutrons entering the pump casing from an exterior of the EMP. The EMP may include a neutron moderator material on an outer surface of the pump casing and configured to moderate neutrons entering the pump casing to be absorbed by the neutron absorber material.

Molten salt nuclear fission reactor including a core through which a fuel salt flows, a unit for circulating the fuel salt, a primary heat exchanger through which a heat-transfer salt flows, a primary enclosure which is impermeable to liquid salts and contains the reactor core, and a shelter. The reactor includes a parallelepiped matrix including alternating layers of fuel salt channels, and layers of heat-transfer salt channels. The matrix forms both the reactor core, in which the fission occurs, and the primary heat exchanger of the reactor. The circulating unit is entirely located within the primary enclosure and are configured to extract the fuel salt from one portion of the fuel salt channels on one side of the matrix and to propel the fuel salt into the other portion of the channels on the same side of the matrix.

Molten salt nuclear fission reactor including a core through which a fuel salt flows, a unit for circulating the fuel salt, a primary heat exchanger through which a heat-transfer salt flows, a primary enclosure which is impermeable to liquid salts and contains the reactor core, and a shelter. The reactor includes a parallelepiped matrix including alternating layers of fuel salt channels, and layers of heat-transfer salt channels. The matrix forms both the reactor core, in which the fission occurs, and the primary heat exchanger of the reactor. The circulating unit is entirely located within the primary enclosure and are configured to extract the fuel salt from one portion of the fuel salt channels on one side of the matrix and to propel the fuel salt into the other portion of the channels on the same side of the matrix.

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 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.

An apparatus and method for shielding against radiation and providing thermal insulation is disclosed. The apparatus includes multiple layers including an inner layer, an outer layer, and a radiation shielding layer composed of materials such a tungsten sheet, multiple tungsten sheets, staggered rows of tungsten rods, and/or a polymer radiation shield composed of a polymer and radiation attenuating material. Insulation layers may also be incorporated into the apparatus. The method for protecting against radiation includes the steps of providing a radiation shielding apparatus and securing such apparatus to a radiation emitting structure.

Collimators and other components for use in neutron scattering experiments or to provide neutron shielding in nuclear reactors or accelerator based neutron sources are produced by additive manufacturing from neutron absorbing material, such as boron carbide (B.sub.4C) or isotopically enriched boron carbide (.sup.10B).

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 intermodal 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 intermodal transport container during the power generation operation.

A method of refueling a nuclear reactor that includes the steps of removing the reactor vessel head and upper internals to a storage location and installing a cylindrical tank having open upper and lower ends, on the reactor vessel flange. The cylindrical tank is sealed to the reactor vessel and a penetration on the side of the cylindrical tank is sealed to a refueling canal that is connected to a spent fuel pool. The level of reactor coolant within the reactor vessel is then raised to at least partially fill the cylindrical tank to a level equal to that of the spent fuel pool. The refueling canal is then opened and a refueling machine supported on the reactor vessel is employed to transfer fuel assemblies between the core and the spent fuel pool.

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.