Author: John A. DeMastry
Publisher:
ISBN:
Category : Niobium alloys
Languages : en
Pages : 72
Book Description
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
Author: John A. DeMastry
Publisher:
ISBN:
Category : Niobium alloys
Languages : en
Pages : 72
Book Description
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).
Publisher:
ISBN:
Category : Niobium alloys
Languages : en
Pages : 72
Book Description
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 ...
Author:
Publisher:
ISBN:
Category : Aluminum-uranium alloys
Languages : en
Pages : 124
Book Description
Publisher:
ISBN:
Category : Aluminum-uranium alloys
Languages : en
Pages : 124
Book Description
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1202
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1202
Book Description
Progress Relating to Civilian Applications During September, 1959
Author: Russell W. Dayton
Publisher:
ISBN:
Category :
Languages : en
Pages : 108
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 108
Book Description
Progress Relating to Civilian Applications During November, 1959
Author: Russell W. Dayton
Publisher:
ISBN:
Category :
Languages : en
Pages : 114
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 114
Book Description
Progress Relating to Civilian Applications During December, 1959
Author: Russell W. Dayton
Publisher:
ISBN:
Category :
Languages : en
Pages : 106
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 106
Book Description
Reactor Materials
Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 370
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 370
Book Description
Progress Relating to Civilian Applications During July, 1959
Author: Russell W. Dayton
Publisher:
ISBN:
Category :
Languages : en
Pages : 108
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 108
Book Description
Progress Relating to Civilian Applications During August, 1959
Author: Russell W. Dayton
Publisher:
ISBN:
Category :
Languages : en
Pages : 112
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 112
Book Description
Progress Relating to Civilian Applications During February, 1960
Author: Russell W. Dayton
Publisher:
ISBN:
Category :
Languages : en
Pages : 100
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 100
Book Description