Abstract:
There is provided an encapsulated pebble, comprising: a fuel core; and a cage encapsulating the fuel core, wherein the cage comprises at least one gas transport channel therethrough. There is also provided a method of making the encapsulated pebble, a breeding blanket module for a fusion reactor, a fusion reactor and methods and uses thereof.
Abstract:
Nuclear fuel assemblies include fuel elements that are sintered or cast into billets and co-extruded into a spiral, multi-lobed shape. The fuel kernel may be a metal alloy of metal fuel material and a metal-non-fuel material, or ceramic fuel in a metal non-fuel matrix. The fuel elements may use more highly enriched fissile material while maintaining safe operating temperatures. Such fuel elements according to one or more embodiments may provide more power at a safer, lower temperature than possible with conventional uranium oxide fuel rods. The fuel assembly may also include a plurality of conventional UO2 fuel rods, which may help the fuel assembly to conform to the space requirements of conventional nuclear reactors.
Abstract:
Nuclear fuel assemblies include fuel elements that are sintered or cast into billets and co-extruded into a spiral, multi-lobed shape. The fuel kernel may be a metal alloy of metal fuel material and a metal-non-fuel material, or ceramic fuel in a metal non-fuel matrix. The fuel elements may use more highly enriched fissile material while maintaining safe operating temperatures. Such fuel elements according to one or more embodiments may provide more power at a safer, lower temperature than possible with conventional uranium oxide fuel rods. The fuel assembly may also include a plurality of conventional UO2 fuel rods, which may help the fuel assembly to conform to the space requirements of conventional nuclear reactors.
Abstract:
A green body for a 3D ceramic and/or metallic body is produced by providing a metal or a mixture of metals and/or a metalloid and/or a non-metal or mixtures thereof in form of at least one aqueous solutions, such as a metal nitrate solution; if more than one aqueous solutions are provided, they differ in composition and/or isotope concentration. One aqueous metal solution is mixed with a gelation fluid at a first temperature to suppress an internal gelation of the feed solution mixture prior to its ejection. The feed solution mixture is ejected by inkjet printing to the green body under construction. The ejected feed solution is heated mixture on the green body to a second temperature to fix it on the green body under construction. Several process steps are repeated according to a 3D production control model until a desired form of the green body is attained.
Abstract:
A method of producing a nuclear fuel product is provided. The method includes the steps of providing a core comprising aluminium and low-enriched uranium; and sealing said core in a cladding. The core has a low-enriched uranium loading strictly higher than 3.0 gU/cm3 and includes less than 10 wt % of aluminium phase and/or aluminium compounds other than UAl2 phase, than UAl3 phase, and than UAl4 phase. A corresponding nuclear fuel product is also provided.
Abstract:
A new type of nuclear fuel rods. The rod cladding has an elliptical section transverse to its longitudinal direction and each nuclear fuel pellet has a truncated elliptical shape along the major axis of the cladding, the minor axis of the pellets is the same as the length of the minor axis of the cladding except for the assembly clearance j, the difference in length between the major axis of the cladding and the truncated major axis of the pellets is very much larger than the assembly clearance j. Also disclosed is a method of manufacturing nuclear fuel rods and stacking them in the cladding so as to form a nuclear fuel rod.
Abstract:
[Problem] To build a secure and high-efficiency power generation system while achieving a further reduction in the size of the entire system. [Solution] A compact nuclear power generation system is provided with a reactor (3) comprising a core (2) which uses metal fuel containing either or both of uranium-235/238 and plutonium-239, a reactor vessel (1) which houses the core (2), metal sodium which is filled into the reactor vessel (1) and heated by the core (2), and a neutron reflector (9) which maintains the effective multiplication factor of neutrons emitted from the core (2) at approximately one or more to bring the core into a critical state. A main heat exchanger (15) is installed outside the reactor (3). The metal sodium heated by the reactor (3) is supplied to the main heat exchanger (15), and supercritical carbon dioxide that is subjected to heat exchange with the heated metal sodium circulates therethrough. The supercritical carbon dioxide heated by the main heat exchanger (15) drives a turbine (20), and a power generator (21) is operated by the drive of the turbine (20).
Abstract:
A nuclear-fuel pin including a linear element made of a metal nuclear-fuel material consisting of uranium and/or plutonium, and cladding including Fe and Cr or an alloy including at least both of said elements, comprises a main shell provided around the linear nuclear-fuel element, said shell including threads or fibers made of SiC. A method for producing a nuclear-fuel pin is also provided.
Abstract:
A metal particulate fuel system is described. The metal fuel system may include particulate metal fuel for use in nuclear reactors. The particulate metal fuel may include a plurality of particles of at least one enriched alloy where the particles are compacted into a fuel column. The metal particulate fuel system may also include a cladding and/or a gas-filled plenum.
Abstract:
Nuclear fuels for nuclear reactors are described, and include nuclear fuels having a first fuel component of recycled uranium, and a second fuel component of depleted uranium blended with the first fuel component, wherein the blended first and second fuel components have a fissile content of less than 1.2 wt % of 235U. Also described are nuclear fuels having a first fuel component of recycled uranium, and a second fuel component of natural uranium blended with the first fuel component, wherein the blended first and second fuel components have a fissile content of less than 1.2 wt % of 235U.