A system for the recovery of titanium, titanium alloys, zirconium and zirconium alloys is disclosed. The system is fed with a mixture of chips including titanium chips, titanium alloy chips, zirconium chips and zirconium alloy chips, ferromagnetic chips and electrically conductive non-ferromagnetic chips. The system has at least one magnetic separator, a drying device and an Eddy current separator.

A system for the recovery of titanium, titanium alloys, zirconium and zirconium alloys is disclosed. The system is fed with a mixture of chips including titanium chips, titanium alloy chips, zirconium chips and zirconium alloy chips, ferromagnetic chips and electrically conductive non-ferromagnetic chips. The system has at least one magnetic separator, a drying device and an Eddy current separator.

The present disclosure is directed to novel high entropy alloys, including refractory high entropy alloys, and methods of selecting high entropy alloys and refractory high entropy alloys with select nuclear application predetermined properties.

The present disclosure is directed to novel high entropy alloys, including refractory high entropy alloys, and methods of selecting high entropy alloys and refractory high entropy alloys with select nuclear application predetermined properties.

A process for producing a metal alloy balance wheel by molding includes a) making a mold in the negative shape of the balance wheel; b) obtaining a metal alloy that has a thermal expansion coefficient of less than 25 ppm/° C. and is able to be in an at least partly amorphous state when it is heated to a temperature between its glass transition temperature and its crystallization temperature; c) putting the metal alloy into the mold, the metal alloy being heated to a temperature between its glass transition temperature and its crystallization temperature so as to be hot-molded and to form a balance wheel; d) cooling the metal alloy to obtain a balance wheel made of the metal alloy; and e) releasing the balance wheel obtained in step d) from its mold. The process also includes a step for over-molding flexible centering components in the hub.

This disclosure describes various configurations and components for bimetallic and trimetallic claddings for use as a wall element separating nuclear material from an external environment. The cladding materials are suitable for use as cladding for nuclear fuel elements, particularly for fuel elements that will be exposed to sodium or other coolants or environments with a propensity to react with the nuclear fuel.

Disclosed is an entropy-controlled solid solution matrix BCC alloy having strong resistance to high-temperature neutron radiation damage. The entropy-controlled solid solution matrix BCC alloy includes three or more multicomponent main elements selected from the element group consisting of Zr, Al, Nb, Mo, Cr, V, and Ti selected based on a neutron absorption cross-sectional area and a mixing enthalpy. Each of the elements is included in an amount of 5 to 35 at %, and the entropy-controlled solid solution matrix BCC alloy is a BCC-structure solid solution matrix alloy in a medium-entropy to high-entropy state. In this invention, damage caused by neutron radiation is reduced, and entropy is controlled to thus ensure a solid solution matrix BCC structure having a slow diffusion speed, and accordingly, resistance to void swelling due to radioactive rays is high.

Disclosed is an entropy-controlled solid solution matrix BCC alloy having strong resistance to high-temperature neutron radiation damage. The entropy-controlled solid solution matrix BCC alloy includes three or more multicomponent main elements selected from the element group consisting of Zr, Al, Nb, Mo, Cr, V, and Ti selected based on a neutron absorption cross-sectional area and a mixing enthalpy. Each of the elements is included in an amount of 5 to 35 at %, and the entropy-controlled solid solution matrix BCC alloy is a BCC-structure solid solution matrix alloy in a medium-entropy to high-entropy state. In this invention, damage caused by neutron radiation is reduced, and entropy is controlled to thus ensure a solid solution matrix BCC structure having a slow diffusion speed, and accordingly, resistance to void swelling due to radioactive rays is high.

This disclosure describes various configurations and components for bimetallic and trimetallic claddings for use as a wall element separating nuclear material from an external environment. The cladding materials are suitable for use as cladding for nuclear fuel elements, particularly for fuel elements that will be exposed to sodium or other coolants or environments with a propensity to react with the nuclear fuel.

A method for heat treating a powder part preform including a titanium-based alloy, wherein the method includes the heat treatment of the preform in a furnace at a predetermined temperature, wherein the preform is on a holder during the heat treatment, wherein the holder includes a zirconium-based alloy having a zirconium content greater than or equal to 95% by weight, wherein the holder material has a melting temperature higher than the predefined temperature of the heat treatment, and wherein an anti-diffusion barrier is arranged between the preform and the holder in order to prevent welding of the preform to the holder.