A process is outlined for the production of uranium alloy powders by co- reduction of mintures of uranium oxide and alloy element oxides. The reduction of mechanical mintures of the oxides of uranium and alloy element with calcium in a sealed reaction vessel is shown to produce powder wtth a variation in particle composition, although of consistert composition over various size fractions. The particular alloy systems which are considered are uranium--nickel, uranium-- chromium, uranium --molybdenum, and uranium--niobium. The uranium-molybdenum and uranium--niobium powders are single phase (metastable gamma), which is of consequence in the production of dimensionaHy stable nuclear fuels. Potential applications of some of these alloys are dis...
Binary alloys of uranium with 38 elements in the range 0.01 to 1.0 at.% were made. Three alloys havi...
Fabrication techniques for producing dispersion fuel elements with cores of 30 volume per cent of UC...
The main objective of this master thesis was assessing and evaluating the production of mixed U-Zr n...
Uranium--niobium alloys were prepared by direct reduction with calcium of urardum tetrafluoride and ...
International audienceUranium-molybdenum alloy powders are obtained by a new synthetic route derivin...
Metallic uranium alloys are candidate materials for use as the fuel phase in very-high-density LEU d...
A study was made of the preparation of a uranium - 10 w/O niobium alloy by the bomb reduction of a s...
Methods of melting uranium and its alloys are examined including vacuum induction melting and consum...
From conference on physical metallurgy of uranium alloys; Vail, Colorado, USA (12 Feb 1974). A revie...
Thorium-uranium alloys were studied with the aim of developing alloys with improved irradiation beha...
Information concerning the transformation kinetics of the gamma solid solution of uranium-base alloy...
The main objective of this master thesis was assessing and evaluating the production of mixed U-Zr n...
Argonne National Lab. Results are summarized from irradiation and corrosion tests on alloys of U--Pu...
The feasibility of improving swelling resistance in metallic uranium by increasing the dislocation d...
Metallographic and dilatometric studies of the heat treatment behavior of technical uranium and cert...
Binary alloys of uranium with 38 elements in the range 0.01 to 1.0 at.% were made. Three alloys havi...
Fabrication techniques for producing dispersion fuel elements with cores of 30 volume per cent of UC...
The main objective of this master thesis was assessing and evaluating the production of mixed U-Zr n...
Uranium--niobium alloys were prepared by direct reduction with calcium of urardum tetrafluoride and ...
International audienceUranium-molybdenum alloy powders are obtained by a new synthetic route derivin...
Metallic uranium alloys are candidate materials for use as the fuel phase in very-high-density LEU d...
A study was made of the preparation of a uranium - 10 w/O niobium alloy by the bomb reduction of a s...
Methods of melting uranium and its alloys are examined including vacuum induction melting and consum...
From conference on physical metallurgy of uranium alloys; Vail, Colorado, USA (12 Feb 1974). A revie...
Thorium-uranium alloys were studied with the aim of developing alloys with improved irradiation beha...
Information concerning the transformation kinetics of the gamma solid solution of uranium-base alloy...
The main objective of this master thesis was assessing and evaluating the production of mixed U-Zr n...
Argonne National Lab. Results are summarized from irradiation and corrosion tests on alloys of U--Pu...
The feasibility of improving swelling resistance in metallic uranium by increasing the dislocation d...
Metallographic and dilatometric studies of the heat treatment behavior of technical uranium and cert...
Binary alloys of uranium with 38 elements in the range 0.01 to 1.0 at.% were made. Three alloys havi...
Fabrication techniques for producing dispersion fuel elements with cores of 30 volume per cent of UC...
The main objective of this master thesis was assessing and evaluating the production of mixed U-Zr n...