CERMET fuel element includes a fuel meat of consolidated ceramic fuel particles (preferably refractory-metal coated HALEU fuel kernels) and an array of axially-oriented coolant flow channels. Formation and lateral positions of coolant flow channels in the fuel meat are controlled during manufacturing by spacer structures that include ceramic fuel particles. In one embodiment, a coating on a sacrificial rod (the rod being subsequently removed) forms the coolant channel and the spacer structures are affixed to the coating; in a second embodiment, a metal tube forms the coolant channel and the spacer structures are affixed to the metal tube. The spacer structures laterally position the coolant channels in spaced-apart relation and are consolidated with the ceramic fuel particles to form CERMET fuel meat of a fuel element, which are subsequently incorporated into fuel assemblies that are distributively arranged in a moderator block within a nuclear fission reactor, in particular for propulsion.

CERMET fuel element includes a fuel meat of consolidated ceramic fuel particles (preferably refractory-metal coated HALEU fuel kernels) and an array of axially-oriented coolant flow channels. Formation and lateral positions of coolant flow channels in the fuel meat are controlled during manufacturing by spacer structures that include ceramic fuel particles. In one embodiment, a coating on a sacrificial rod (the rod being subsequently removed) forms the coolant channel and the spacer structures are affixed to the coating; in a second embodiment, a metal tube forms the coolant channel and the spacer structures are affixed to the metal tube. The spacer structures laterally position the coolant channels in spaced-apart relation and are consolidated with the ceramic fuel particles to form CERMET fuel meat of a fuel element, which are subsequently incorporated into fuel assemblies that are distributively arranged in a moderator block within a nuclear fission reactor, in particular for propulsion.

Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material, the interior surface of which is lined in higher temperature regions with an insulation layer of porous refractory ceramic material. A continuous insulation layer extends the length of the fuel assembly or separate insulation layer sections have a thickness increasing step-wise along the length of the fuel assembly from upper (inlet) section towards bottom (outlet) section. A fuel element positioned inward of the insulation layer and between support meshes has a fuel composition including HALEU and has the form of a plurality of individual elongated fuel bodies or one or more fuel monolith bodies containing coolant flow channels. Fuel assemblies are distributively arranged in a moderator block, with upper end of the outer structural member attached to an inlet for propellant and lower end of the outer structural member operatively interfaced with a nozzle forming a NTP reactor.

This patent application is for a process of nuclear power generation with ˜KW output by making the Thorium fuel of LiF+BeF.sub.2+ThF.sub.4 in a Thorium Molten Salt Reactor (Th-MSR) to undergo fission along the thorium fuel cycle by providing thermal neutrons which were obtained by slowing down of fast neutrons from n external neutron generators with the help of graphite moderators carefully arranged inside the Th-MSR.

The molten salt that entered the reactor at a temperature of 600° C. becomes hot to 750° C. due to nuclear fission, goes through a heat exchanger and returns to the reactor. The output power of this reactor is proportional to the number of thermal neutrons supplied to the inside of the reactor, and when the external neutron generator is turned ON-OFF, nuclear power generation is also ON-OFF.

This Th-MSR power generation process with thermal neutron generators, which Dr. Choi is applying for a patent, will be one of the most innovative ways to generate ˜kW range nuclear power with the use of 100% non-radioactive nuclear fuel since until now all the Th-MSR power generation scheme relied upon neutrons from the natural decay of Uranium-235 mixed with the Thorium fuel of LiF+BeF.sub.2+ThF.sub.4 with a mixing ratio of 80% ThF4 to 20% UF4. Key Word Thorium Molten Salt Reactor, Thermal Neutron Generator

A thermoelectric converter including a thermoelectric generator and a radiation source. The thermoelectric generator includes a hot source, a cold source, n-type material, and p-type material. The radiation source emits ionizing radiation that increases electrical conductivity. Also detailed is a method of using radiation to reach high efficiency with a thermoelectric converter that includes providing a thermoelectric generator and a radiation source, with the thermoelectric generator including a hot source, a cold source, n-type material, and p-type material, and emitting ionizing radiation with the radiation source to increase the electrical conductivity which strips electrons in the n-type material, the p-type material, or both the n-type material and p-type material from their nuclei with the electrons then free to move within the material.

The reactor core includes at least one module, solid and liquid neutron moderators. The module contains a casing, at least one heat pipe, one fuel element and thermal insulation. The heat pipe is in the shape of a casing with a wick and contains a coolant. The fuel element is made of nuclear fuel, arranged in the evaporation area of the heat pipe around its casing in thermal contact with it, and enclosed in a can. Low-melting metals with a high boiling point are used as the coolant of the heat pipe. Thermal insulation is arranged between the can and the casing of the module. At least one hole is made in the solid neutron moderator, in which at least one module is arranged. The space between the casing of the module and the solid neutron moderator is filled with a liquid neutron moderator.

Device for producing energy by nuclear fission, and methods of using same. The device comprises 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 has(have) an inlet and an outlet. The device also comprises a molten fuel salt with a fissionable material and a molten moderator salt comprising metal hydroxide(s), metal deuteroxide(s) or a combination thereof and a redox-element having a reduction potential, which is larger than that of the inner tubing material or of the inner tubing material and the core container material. The molten moderator salt is located in the core container, and the molten fuel salt is located in the inner tubing. Alternatively, the molten fuel salt is located in the core container, and the molten moderator salt is located in the inner tubing.

Device for producing energy by nuclear fission, and methods of using same. The device comprises 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 has(have) an inlet and an outlet. The device also comprises a molten fuel salt with a fissionable material and a molten moderator salt comprising metal hydroxide(s), metal deuteroxide(s) or a combination thereof and a redox-element having a reduction potential, which is larger than that of the inner tubing material or of the inner tubing material and the core container material. The molten moderator salt is located in the core container, and the molten fuel salt is located in the inner tubing. Alternatively, the molten fuel salt is located in the core container, and the molten moderator salt is located in the inner tubing.

Electric Heating for Nuclear Reactors is a system and method for the replacement of nuclear fuel rods within the core of a nuclear reactor with submersible (immersion) electric heaters.

This disclosure describes various configurations and components of a molten fuel fast or thermal nuclear reactor in which one or more primary heat exchangers are located above the reactor core of the nuclear reactor.