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.

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.

A system for nuclear power generation includes an accelerator-driven subcritical reactor that operates using molten-salt fuel. The operation of the reactor can be continuously monitored to ensure subcriticality. The system also includes means for removing volatile radioactive fission products from the molten-salt fuel continuously during the operation of the reactor to maintain an amount of the volatile radioactive fission products in the reactor below a threshold corresponding to a safety limit for accidental release of radioactive materials. The system can be used for highly efficient nuclear power generation while preventing criticality accidents and accidental releases of radioactive isotopes.

A system for producing a high flux of neutrons includes a gas-target neutron generator and a fission assembly neutronically coupled to the gas-target neutron generator. The gas-target neutron generator includes an ion source configured to produce an ion beam, an accelerator configured to accelerate the ion beam to produce an accelerated ion beam, a plurality of focus elements configured to focus the accelerated ion beam in an x-direction and a y-direction, and a pumping/gas-target section including a gas target chamber filled with a target gas. The fission assembly is a subcritical or a sub-prompt critical fission assembly. The fission assembly surrounds the gas target chamber. 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 system for producing a high flux of neutrons includes a gas-target neutron generator and a fission assembly neutronically coupled to the gas-target neutron generator. The gas-target neutron generator includes an ion source configured to produce an ion beam, an accelerator configured to accelerate the ion beam to produce an accelerated ion beam, a plurality of focus elements configured to focus the accelerated ion beam in an x-direction and a y-direction, and a pumping/gas-target section including a gas target chamber filled with a target gas. The fission assembly is a subcritical or a sub-prompt critical fission assembly. The fission assembly surrounds the gas target chamber. 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.

The present invention discloses a heat exchange system and a nuclear reactor system. The heat exchange system includes: a heating device; a heat consuming device connected with the heating device through a pipe to form a loop; and a steam, which is in a wet steam state before being supplied to a heat source, and is supplied to the heat consuming device after becoming dry steam or superheated steam by exchanging heat with the heating device. Heat exchange efficiency and security of the nuclear reactor system are improved by adopting steam as a heat exchange medium.

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 generator unit is provided. The transportable nuclear power generator unit includes a container configured to be transportable by a vehicle, and nuclear power module disposed inside the container. The nuclear power module includes a sealed pressure vessel and a nuclear core disposed inside the sealed pressure vessel. The transportable nuclear power generator unit also includes a plurality of radiation shields provided at a plurality of interior walls inside the container to surround the sealed pressure vessel. The radiation shields are configured to shield radiation generated by the nuclear power module. The radiation shields include a movable shield configured to be movable between a position inside the container and a position on an exterior wall of the container.

A system for nuclear power generation can include an accelerator-driven subcritical nuclear reactor that operates using molten-salt fuel. The reactor includes a target positioned to receive a proton beam and to be cooled by the molten-salt fuel. A voltage signal is applied to an electrode in contact with the molten-salt fuel in the reactor for controlling corrosion of the target and other portions of the reactor. In one embodiment, the target is used as the electrode. In another embodiment, an electrode other than the target is used.