Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

METALLURGICAL STUDIES OF NIOBIUM-URANIUM ALLOYS

Technical Report ·
DOI:https://doi.org/10.2172/4216701· OSTI ID:4216701

In a continuing program, fabrication characteristics, physical and mechanical properties, and corrosion behavior in air, CO/sub 2/, NaK, water, and steam were studied for . binary niobium fuel alloys containing 10, 20, 30, 40, 50, and 60 wt.% uranium To evaluate the effects of two major impurities of niobium, oxygen, and zirconium, three niobium base stocks, differing according to the level of these impurities, were used for each alloy. The impurity combinations employed were 600 ppm oxygen and 0.74 wt.% zirconium, 700 ppm oxygen, and 0.17 wt.% zirconium, and 300 ppm oxygen and 0.02 wt.% zirconium, Representative specimens of these alloys retained their hardness up to 900 deg C The 10 and 20 wt.% uraniuin alloys were successfully rorged at 2500 deg F and rolled at 1800 deg F to sheet. Fabrication characteristics of the remaining alloys are under investigation. The 0.2% offset yield strength of the 10 wt.% uranium alloy was 57,200 psi at room temperature and 36,900 psi at 1600 deg F. For the 20 wt.% uranium alloy it was 93,200 psi at room temperature and 71.000 psi at 1600 deg F. The corrosion life of all of the alloys in air at 572 deg F and in CO/sub 2/ at 600 deg F was superior to that of unalloyed niobium. In 1000- hr exposures to 600 deg F water most of the alloys exhibited corrosion rates only two or three times greater than that of Zircaloy-2. All oi the alloys appear compatible with NaK at 1600 deg F. The impurity combinations employed in the base niobium appeared to have no effect on the corrosion behavior and mechanical properties of the alloys. (auth)

Research Organization:
Battelle Memorial Inst., Columbus, Ohio
Sponsoring Organization:
USDOE
DOE Contract Number:
W-7405-ENG-92
NSA Number:
NSA-14-004500
OSTI ID:
4216701
Report Number(s):
BMI-1400
Country of Publication:
United States
Language:
English

Similar Records

DEVELOPMENT OF NIOBIUM-URANIUM ALLOYS FOR ELEVATED-TEMPERATURE FUEL APPLICATIONS
Technical Report · Tue Aug 01 00:00:00 EDT 1961 · OSTI ID:4003620

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

NIOBIUM-20 W/O URANIUM, HIGH-TEMPERATURE METALLIC FUEL OF THE FUTURE
Journal Article · Tue Feb 28 23:00:00 EST 1961 · Nuclear Sci. and Eng. · OSTI ID:4058470