NIOBIUM--PROMISING HIGH-TEMPERATURE REACTOR-CORE MATERIAL

Journal Article · Thu Sep 01 00:00:00 EDT 1960 · Nucleonics (U.S.) Ceased publication

OSTI ID:4157854

DeMastry, J A; Dickerson, R F

The properties of niobium and niobium-base alloys were studied for high temperature reactor use. Results indicated that niobium-based, enriched-uranium alloys may be valuable as fuels for use at 1600 to 2000 deg F in a nonoxidizing environment. The properties of unalloyed niobium, capture cross sections, high temperature strengths, effects of cold work on hardness, electrical resistivity of annealed alloys, tensile properties, creep and creep rupture properties, oxygen solubility, and the effects of oxygen on tensile strength were investigated for niobium snd its alloys. Hothardness values were obtaied for niobium-uranium alloys. Rolling ard forging tests indicated that the 20 wt.% alloy was most easily forged. Corrosion tests were conducted in air, CO/sub 2/, NaK, water, and steam. Dath obtained indicated that the niobium-20 wt.% uranium alloy was the best metallic fuel yet developed for high temperature use. (M.C.G.)

• Research Organization: Battelle Memorial Inst., Columbus, Ohio
• NSA Number: NSA-14-023350
• OSTI ID: 4157854
• Journal Information: Nucleonics (U.S.) Ceased publication, Vol. Vol: 18, No. 9; Other Information: Orig. Receipt Date: 31-DEC-60
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

METALS, CERAMICS, AND OTHER MATERIALS
AIR
ANNEALING
CAPTURE
CARBON DIOXIDE
COLD WORKING
CORROSION
CREEP
CROSS SECTIONS
ELECTRIC CONDUCTIVITY
ENRICHMENT
ENVIRONMENT
FORGING
FUELS
HARDNESS
HIGH TEMPERATURE
HOT WORKING
NIOBIUM ALLOYS
NIOBIUM HYDROXIDES
OXIDATION
OXYGEN
PHASE DIAGRAMS
POTASSIUM ALLOYS
REACTORS
ROLLING
SODIUM ALLOYS
SOLUBILITY
STEAM
STRESSES
TENSILE PROPERTIES
TESTING
URANIUM ALLOYS
USES
WATER