Development of Niobium-uranium Alloys for Elevated-temperature Fuel Applications
Title | Development of Niobium-uranium Alloys for Elevated-temperature Fuel Applications PDF eBook |
Author | John A. DeMastry |
Publisher | |
Pages | 72 |
Release | 1961 |
Genre | Niobium alloys |
ISBN |
As a continuation of studies reported in BMI-1400, fabrication characteristics, physical and mechanical properties, and corrosion behavior in NaK, sodium, and water of niobium--uranium binary alloys containing up to 60 wt.% uranium were investigated. Alloys were cast by a skull melting and consumable and nonconsumable arc-melting methods. Fabrication difficulties with alloys containing greater than 25 wt.% uranium were related to coring-type microsegregation during casting. Tensile tests indicated 0.2% offset yield strengths of 16,880, 22,370 and 28,600 psi for niobium2000 deg F. Additional tensile data were obtained for alloys from 1600 to 2400 deg F. Stresses to produce minimum creep rates of 0.001, 0.01, and 0.1%/hr at 1600, 1800, and 2000 deg F were also determined. Both tensile and creep strengths were found to be sensitive to oxygen content. All alloys appeared compatible with NaK at 1600 deg F and with sodium at 1500 deg F. In 600 deg F water, most of the alloys tested exhibited negligible weight changes after 336 days' exposure. Weight changes were greater after 140 days' exposure to 680 deg F water, but corrosion rates were considered satisfactory for a clad fuel. The thermal and electrical conductivities of niobium are lowered by the addition of uranium, while the thermal-expansion characteristics are essentially unaffected. Recrystallization temperatures for 90% cold-reduced niobium-4.38, -14.3, -20, -25.0, and -30 wt.% uranium alloys are 2300, 2300, 2400, 2300, and 2200 deg F, respectively. No appreciable effect of oxygen contents ranging from 100 to 1000 ppm was observed on the composition limits of the gamma immiscibility gap in the niobium-- uranium system. (auth).
DEVELOPMENT OF NIOBIUM-URANIUM ALLOYS FOR ELEVATED-TEMPERATURE FUEL APPLICATIONS.
Title | DEVELOPMENT OF NIOBIUM-URANIUM ALLOYS FOR ELEVATED-TEMPERATURE FUEL APPLICATIONS. PDF eBook |
Author | |
Publisher | |
Pages | |
Release | 1961 |
Genre | |
ISBN |
As a continuation of studies reported in BMI-1400, fabrication characteristics, physical and mechanical properties, and corrosion behavior in NaK, sodium, and water of niobium--uranium binary alloys containing up to 60 wt.% uranium were investigated. Alloys were cast by a skull melting and consumable and nonconsumable arc-melting methods. Fabrication difficulties with alloys containing greater than 25 wt.% uranium were related to coring-type microsegregation during casting. Tensile tests indicated 0.2% offset yield strengths of 16,880, 22,370 and 28,600 psi for niobium2000 deg F. Additional tensile data were obtained for alloys from 1600 to 2400 deg F. Stresses to produce minimum creep rates of 0.001, 0.01, and 0.1%/hr at 1600, 1800, and 2000 deg F were also determined. Both tensile and creep strengths were found to be sensitive to oxygen content. All alloys appeared compatible with NaK at 1600 deg F and with sodium at 1500 deg F. In 600 deg F water, most of the alloys tested exhibited negligible weight changes after 336 days' exposure. Weight changes were greater after 140 days' exposure to 680 deg F water, but corrosion rates were considered satisfactory for a clad fuel. The thermal and electrical conductivities of niobium are lowered by the addition of uranium, while the thermal-expansion characteristics are essentially unaffected. Recrystallization temperatures for 90% cold-reduced niobium-4.38, -14.3, -20, -25.0, and -30 wt.% uranium alloys are 2300, 2300, 2400, 2300, and 2200 deg F, respectively. No appreciable effect of oxygen contents ranging from 100 to 1000 ppm was observed on the composition limits of the gamma immiscibility gap in the niobium-- uranium system. (auth).
Progress Relating to Civilian Applications During June, 1959
Title | Progress Relating to Civilian Applications During June, 1959 PDF eBook |
Author | Russell W. Dayton |
Publisher | |
Pages | 116 |
Release | 1959 |
Genre | |
ISBN |
Development of Niobium Diffusion Barriers for Aluminum-clad Uranium Alloy Fuel Elements
Title | Development of Niobium Diffusion Barriers for Aluminum-clad Uranium Alloy Fuel Elements PDF eBook |
Author | B. N. Briggs |
Publisher | |
Pages | 56 |
Release | 1962 |
Genre | Niobium |
ISBN |
Progress Relating to Civilian Applications During ...
Title | Progress Relating to Civilian Applications During ... PDF eBook |
Author | |
Publisher | |
Pages | 54 |
Release | 1957-10 |
Genre | Aluminum-uranium alloys |
ISBN |
Development and Properties of Uranium-base Alloys Corrosion Resistant in High Temperature Water
Title | Development and Properties of Uranium-base Alloys Corrosion Resistant in High Temperature Water PDF eBook |
Author | I. Cohen |
Publisher | |
Pages | 322 |
Release | 1955 |
Genre | Uranium alloys |
ISBN |
The effects of pile irradiations on the physical properties and corrosion resistance of U-- Mo, U-- Nb; and U--Si alloys are reported. The dimensional stability under irradiation of the gamma phase U-- Mo and U-- Nb alloys is excellent; however, an isotropic volume increase of 4 to 6% per wt.% burnup may limit the ultimate fuel element life. Corrosion resistance of the gamma-phase alloys appesrs to be improved when subjected to s neutron field; this is attributed to an irrsdiation induced stabilization of the gamma phases. The U/ sub 3/Si alloy, on the other hand, suffered severe deterioration, particularly of corrosion resistance. Changes in electrical resistivity, hardness, mechanical properties, and crystal structure are presented and the mechanisms producing the observed changes discussed.
Summaries of Fuels and Materials Development Programs
Title | Summaries of Fuels and Materials Development Programs PDF eBook |
Author | |
Publisher | |
Pages | 114 |
Release | 1960 |
Genre | Government contractors |
ISBN |