FUNDAMENTAL AND APPLIED RESEARCH AND DEVELOPMENT IN METALLURGY. Progress Report for April 1959

Technical Report · Fri Jun 12 00:00:00 EDT 1959

OSTI ID:4075717

In beryllium metallurgy, x-ray pure UBe/sub 13/ and ZrBe/sub 13/ were prepared by sintering powder mixtures of uranium and beryllium and zirconium and beryllium at 1400 to l500 deg C in an argon atmosphere. The intermetallics were then ground and hot pressed at 4500 psi. ZrBe/sub 13/ machined well; however, UBe/sub 13/ pressing is still being evaluated. Alloys prepared for diffusion couples included Be-10 at.% Cu, Be-2 at.% Fe, and Be-5 at.% Co. In uranium metallurgy, grain size and texture were evaluated for a graphite cast uranium billet (UK-l44) containing 990 to 995 ppm silicon. Microstructure and texture examinations are reported, and the texture after gamma extrusion is being examined along with grain size. An evaluation was also made of various mold washes for casting Th-U slugs. Four slugs were cast from melt TX-163: these proved to be homogeneous from top to bottom within 0.1%. The ingots made thus far by arc melting indicate that uranium segregation is a problem. Data relating the wt. % zirconium to corrosion rate are reported for uranium interdiffusion specimens in hightemperature water. Electron probe analysis of the interdiffusion zone was initiated. In cold working of uranium, a method was developed for cold drawing by a preliminary oxidizing technique and an annealing treatment. Techniques for electron-beam welding of end caps to coextruded 2S aluminum-clad uranium fuel tubes are being investigated. Weld cracking is a major problem and may be caused by a stress concentration at the root of the weld bead. To study this several caps were machined with an undercut and are being examined. A program for future development of UC rods is outlined, and a summary of ANL-TREAT diffusion couple information concerning solid-solid uranium interactions with other metals is tabulated. Research is reported in development of a thermite system for ANL-TREAT. and results of thermodynamic calculations are presented for several systems involving beryllium. Samples from four new thorium alloy castings that were Zircaloy-2 extrusionclad were heat treated at 800 to 850 deg C for banding studies. Samples of bare-end extrusion-clad alloys were also corrosion tested in 500 deg F water: results are tabulated. Results of extrusion- clad defected-element water corrosion tests are reported as well as results from band strength tests on coextrusion. Zircaloy-2-clad thorium alloys. In zirconium metallurgy, corrosion testing of 12 ternary zirconiumbase alloys in 900 and l000 deg F steam is continuing. Results of corrosion testing to date are tabulated. Oxidation experiments to determine the feasibility of hot-working unclad yttrium were conducted: however, the method was not considered desirable because of oxygen gettering. Cold swaging of yttrium is being investigated, and experience in drawing thin-wall tubing is reported. Optimum extrusion temperatures are reported for a series of stainless-steelclad uranium billets. (J.R.D.)

• Research Organization: Nuclear Metals, Inc., Concord. Mass.
• NSA Number: NSA-15-006333
• OSTI ID: 4075717
• Report Number(s): NMI-2077
• Resource Relation: Other Information: Decl. Sept. 1, 1960. Orig. Receipt Date: 31-DEC-61
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

METALS, CERAMICS, AND OTHER MATERIALS
ANNEALING
ARGON
ATMOSPHERE
BERYLLIUM
CASTING
COBALT ALLOYS
COPPER ALLOYS
CORROSION
CRACKING
DIFFUSION
DISTRIBUTION
ELECTRIC ARCS
ELECTRON BEAMS
ELECTRONS
EXTRUSION
FUEL CANS
GRAPHITE
HIGH TEMPERATURE
INTERMETALLIC COMPOUNDS
IRON ALLOYS
MECHANICAL PROPERTIES
MELTING
METALLOGRAPHY
METALLURGY
MICROSCOPY
OXIDATION
POWDERS
PRESSURE
RODS
SEGREGATION
SILICON
SINTERING
SLUGS
STAINLESS STEELS
STRESSES
TESTING
THERMODYNAMICS
THORIUM
TUBES
URANIUM
WATER
WELDING
X RADIATION
YTTRIUM
ZIRCONIUM