Physical and mechanical metallurgy of uranium and uranium alloys
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:298274
- Sandia National Labs. (United States)
Engineering disadvantages of unalloyed uranium include relatively low strength, low ductility, and poor oxidation and corrosion resistance. As-cast uranium typically exhibits very large grains that cause nonuniform deformation and low tensile ductility. Uranium is often alloyed to improve its corrosion resistance and mechanical properties. Titanium is most commonly used to increase strength; niobium and molybdenum, to increase oxidation and corrosion resistance; and vanadium, to refine alpha grain size in castings. Under equilibrium conditions these elements are extensively soluble in the high-temperature gamma phase, slightly soluble in the intermediate temperature beta phase, and essentially insoluble in the low-temperature alpha phase. Uranium alloys are vacuum solution heat treated in the gamma range to dissolve the alloying elements and remove hydrogen. The subsequent microstructures and properties are determined by the cooling rate from the solution treatment temperature. Oxidation and corrosion resistance increases with increasing the amount of alloy in solid solution. As a result, alloys such as U-6%Nb and U-10%Mo are often used in applications requiring good corrosion resistance.
- OSTI ID:
- 298274
- Report Number(s):
- CONF-981106--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 79; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
Similar Records
DEVELOPMENT AND PROPERTIES OF URANIUM-BASE ALLOYS CORROSION RESISTANT IN HIGH TEMPERATURE WATER. PART III. CORROSION MECHANISM OF URANIUM-BASE ALLOYS IN HIGH TEMPERATURE WATER
PHYSICAL METALLURGY AND PROPERTIES OF ZIRCONIUM-URANIUM ALLOYS
ON THE IMPROVEMENT OF METALLIC URANIUM FUEL. II. THERMAL CYCLING AND CORROSION TESTS OF EXTRUDED URANIUM RODS AND SOME URANIUM ALLOYS
Technical Report
·
Sun Jul 01 00:00:00 EDT 1956
·
OSTI ID:4330224
PHYSICAL METALLURGY AND PROPERTIES OF ZIRCONIUM-URANIUM ALLOYS
Technical Report
·
Thu Oct 30 23:00:00 EST 1958
·
OSTI ID:4306479
ON THE IMPROVEMENT OF METALLIC URANIUM FUEL. II. THERMAL CYCLING AND CORROSION TESTS OF EXTRUDED URANIUM RODS AND SOME URANIUM ALLOYS
Journal Article
·
Mon Jul 01 00:00:00 EDT 1963
· Nippon Genshiryoku Gakkaishi (Japan)
·
OSTI ID:4647102