A previous investigation concerned with liquid-core fuel elements and the materials from which they could be constructed revealed tht an alloy of U--5 wt. % Nb had considerable promise as container material. Results are given from a further investigation of this alloy, as well as another containing 10 wt. % Nb, to determine the time and temperature limits within which tbe oxide layer remains protective, the factors which hasten or delay the breakdown of the film, and the mechanism whereby the film deteriorites, (auth
Methods of melting uranium and its alloys are examined including vacuum induction melting and consum...
The feasibility of improving swelling resistance in metallic uranium by increasing the dislocation d...
In the search for a corrosion-resistant high-uraniumcontent alloy for use as core material in high-t...
As a continuation of studies reported in BMI-1400, fabrication characteristics, physical and mechani...
As a continuation of studies reported in BMI-1400, fabrication characteristics, physical and mechani...
In a continuing program, fabrication characteristics, physical and mechanical properties, and corros...
Thorium-uranium alloys were studied with the aim of developing alloys with improved irradiation beha...
In a continuing program, fabrication characteristics, physical and mechanical properties, and corros...
Argonne National Lab. Results are summarized from irradiation and corrosion tests on alloys of U--Pu...
A study was made of the preparation of a uranium - 10 w/O niobium alloy by the bomb reduction of a s...
A limited study consisting of scoping experiments was carried out to determine if a uranium-niobium ...
The basic requirements for dispersion-type fuel elements and the basis for the selection of the comp...
In research in support of the GCRE, procedures for the fabrication of stainless steel-clad flat-plat...
Uranium--niobium alloys were prepared by direct reduction with calcium of urardum tetrafluoride and ...
Uranium, a nuclear fuel material, can oxidize and degrade in reactor conditions. Previous studies ha...
Methods of melting uranium and its alloys are examined including vacuum induction melting and consum...
The feasibility of improving swelling resistance in metallic uranium by increasing the dislocation d...
In the search for a corrosion-resistant high-uraniumcontent alloy for use as core material in high-t...
As a continuation of studies reported in BMI-1400, fabrication characteristics, physical and mechani...
As a continuation of studies reported in BMI-1400, fabrication characteristics, physical and mechani...
In a continuing program, fabrication characteristics, physical and mechanical properties, and corros...
Thorium-uranium alloys were studied with the aim of developing alloys with improved irradiation beha...
In a continuing program, fabrication characteristics, physical and mechanical properties, and corros...
Argonne National Lab. Results are summarized from irradiation and corrosion tests on alloys of U--Pu...
A study was made of the preparation of a uranium - 10 w/O niobium alloy by the bomb reduction of a s...
A limited study consisting of scoping experiments was carried out to determine if a uranium-niobium ...
The basic requirements for dispersion-type fuel elements and the basis for the selection of the comp...
In research in support of the GCRE, procedures for the fabrication of stainless steel-clad flat-plat...
Uranium--niobium alloys were prepared by direct reduction with calcium of urardum tetrafluoride and ...
Uranium, a nuclear fuel material, can oxidize and degrade in reactor conditions. Previous studies ha...
Methods of melting uranium and its alloys are examined including vacuum induction melting and consum...
The feasibility of improving swelling resistance in metallic uranium by increasing the dislocation d...
In the search for a corrosion-resistant high-uraniumcontent alloy for use as core material in high-t...