Patent classifications
G21C15/06
CUSTOMIZABLE THIN PLATE FUEL FORM AND REACTOR CORE THEREFOR
A customizable thin plate fuel form and reactor core therefor are disclosed. The thin plate fuel will comprise a fuel material embedded within a matrix material, with the entire unit having a coating. The thin plate fuel may be flat or curved and will have flow channels formed within at least the top surface of the fuel plate. The structure of the thin plate fuel will make it easier for coating with Tungsten or any other suitable material that will help contain any byproducts, prevent reactions with the working fluid, and potentially provide structural support to the thin plate fuel.
CUSTOMIZABLE THIN PLATE FUEL FORM AND REACTOR CORE THEREFOR
A customizable thin plate fuel form and reactor core therefor are disclosed. The thin plate fuel will comprise a fuel material embedded within a matrix material, with the entire unit having a coating. The thin plate fuel may be flat or curved and will have flow channels formed within at least the top surface of the fuel plate. The structure of the thin plate fuel will make it easier for coating with Tungsten or any other suitable material that will help contain any byproducts, prevent reactions with the working fluid, and potentially provide structural support to the thin plate fuel.
Transportable sub-critical modules disposed in intermodal transport container for power generation
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.
Customizable Thin Plate Fuel Form and Reactor Core Therefor
A customizable thin plate fuel form and reactor core therefor are disclosed. The thin plate fuel will comprise a fuel material embedded within a matrix material, with the entire unit having a coating. The thin plate fuel may be flat or curved and will have flow channels formed within at least the top surface of the fuel plate. The structure of the thin plate fuel will make it easier for coating with Tungsten or any other suitable material that will help contain any byproducts, prevent reactions with the working fluid, and potentially provide structural support to the thin plate fuel.
Customizable Thin Plate Fuel Form and Reactor Core Therefor
A customizable thin plate fuel form and reactor core therefor are disclosed. The thin plate fuel will comprise a fuel material embedded within a matrix material, with the entire unit having a coating. The thin plate fuel may be flat or curved and will have flow channels formed within at least the top surface of the fuel plate. The structure of the thin plate fuel will make it easier for coating with Tungsten or any other suitable material that will help contain any byproducts, prevent reactions with the working fluid, and potentially provide structural support to the thin plate fuel.
GAS-COOLED PRESSURE TUBE REACTOR
A gas-cooled pressure tube nuclear reactor is described that uses a room temperature and pressure gas as a primary coolant and a liquid moderator as a secondary coolant. The primary coolant, which may be maintained in a supercritical state, is circulated through fuel columns in a pool of the liquid moderator. The primary coolant removes the heat generated by fission from the nuclear fuel. The heated primary coolant is then passed to one or more turbines to generate power. The primary coolant is then repressurized by one or more compressors using some of the generated power from the turbines. Several modified Brayton cycle configurations are described that are uniquely suited to the operating conditions of the gas-cooled pressure tube reactor.
FUEL CHANNEL ASSEMBLY AND FUEL BUNDLE FOR A NUCLEAR REACTOR
A fuel assembly for a pressure-tube nuclear reactor includes a fuel channel assembly. The fuel channel assembly has an outer conduit and an inner conduit received within the outer conduit. The conduits define an annular fuel bundle chamber for receiving a flow of a coolant in one direction. The inner conduit includes a central flow passage for receiving a flow of the coolant in an opposite direction. A fuel bundle positioned within the fuel bundle chamber consists of fuel elements arranged to form an inner ring surrounding the inner conduit, and an outer ring surrounding the inner ring. The coolant may be light water, and geometries of the fuel assembly may be selected so moderation by the volume of coolant promotes generally uniform power distribution in the fuel elements.
FUEL CHANNEL ASSEMBLY AND FUEL BUNDLE FOR A NUCLEAR REACTOR
A fuel assembly for a pressure-tube nuclear reactor includes a fuel channel assembly. The fuel channel assembly has an outer conduit and an inner conduit received within the outer conduit. The conduits define an annular fuel bundle chamber for receiving a flow of a coolant in one direction. The inner conduit includes a central flow passage for receiving a flow of the coolant in an opposite direction. A fuel bundle positioned within the fuel bundle chamber consists of fuel elements arranged to form an inner ring surrounding the inner conduit, and an outer ring surrounding the inner ring. The coolant may be light water, and geometries of the fuel assembly may be selected so moderation by the volume of coolant promotes generally uniform power distribution in the fuel elements.
FAST NEUTRON REACTOR FUEL ROD
The invention relates to nuclear technology and may be used in preparing fuel rods and fuel assemblies for the cores of fast-neutron reactors utilizing a liquid-metal coolant. The invention reduces metal content of a fuel rod the contact stresses occurring in a fuel rod casing in a reactor core during nuclear fuel burnup. The fast neutron reactor fuel rod includes nuclear fuel disposed in a hermetically-sealed container in the form of a thin-walled tubular casing, and a spacing element wound in a wide-pitch spiral and secured to the casing or to the end components. The spacing element is a thin-walled tube having a longitudinal through-slot along the length thereof. Alternatively, the spacing element is made of a thin-walled tube or a thin band having a middle portion in the form of a tube with a longitudinal through-slot of a set width, and end components of fragments of the cylindrical casing.
FAST NEUTRON REACTOR FUEL ROD
The invention relates to nuclear technology and may be used in preparing fuel rods and fuel assemblies for the cores of fast-neutron reactors utilizing a liquid-metal coolant. The invention reduces metal content of a fuel rod the contact stresses occurring in a fuel rod casing in a reactor core during nuclear fuel burnup. The fast neutron reactor fuel rod includes nuclear fuel disposed in a hermetically-sealed container in the form of a thin-walled tubular casing, and a spacing element wound in a wide-pitch spiral and secured to the casing or to the end components. The spacing element is a thin-walled tube having a longitudinal through-slot along the length thereof. Alternatively, the spacing element is made of a thin-walled tube or a thin band having a middle portion in the form of a tube with a longitudinal through-slot of a set width, and end components of fragments of the cylindrical casing.