PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING JULY 1961

Technical Report · Tue Aug 01 04:00:00 EDT 1961

OSTI ID:4838469

Dayton, R W; Tipton, Jr, C R

Progress is reported for various reactor fuel projects. Observations on the behavior of U/sub 3/O/sub 8/ - CaO, U/sub 3/O/sub 8/ - CdO, and U/sub 3/O/sub 8/ - Al/sub 2/0/sub 3/ mixtures held at 1200-C and 6 x 10/sup 4/ atm for 24 hr are reported. The sliding friction of type 304 stainless steel surfaces at 80 to 1200 deg F decreased when sodium was introduced between the surfaces. X-ray diffraction studies of the phases existing in cast Nb-40.2 wt % Pu-1.2 wt% Si and Nb-23.7 wt% Pu-2.8 wt % Si alloys are reported. U - 10 wt % Nb base alloys were found to increase their hardness with increasing Pu content. Development of tubular fuel element fabrication by explosive forming and expansion of seam- welded flat plates is described. Fractional areas of contact of Ni - Cu couples vacuum hot-pressed at 1000 deg F and pressures of 2000 and 4000 psi are reported. Skull arc-melting techniques were developed for the melting and casting of uranium carbide. The physical properties of uranium carbide compacts irradiated to 0.7 at.% burnup are described. Limitations of Al/sub 2/0/sub 3/ coatings on fuel particles are discussed. The densities of pyrolytic carbon coatings on fuel powders were determined. Postirradiation studies were made on coated fuel particles in graphite spheres. Evidence was found for migration or recrystallization in NaCl crystals and for decoration of dislocations by precipitated Ag in AgCl crystals exposed to fission recoils. Studies were made on the reactions of UC with pyrolytic carbon coatings and of U0/sub 2/ with Al/ sub 2/0/sub 3/ coatings. Results of studies of BeO coating deposition on U0/sub 2/ shot are given. Development of oxide-coated U0/sub 2/ particles was continued. Corrosion studies were made in the Fluoride Violatility process on INOR-8, Hastelloy X, and W-5 wt % Cu-5 wt% Ni alloy with ZrO/sub 2/ additions and a HF sparge at 700 deg C. and on HyMu-80 in LiF-Nar- ZrF/sub 4/ melt sparged with F, at 500 deg C. work on joining oi type 410 stainless steel to Zircaloy-2 is described. Studies of irradiation effects on Hastelloy X-clad U0/sub 2/ and U0/ sub 2/ - BeO specimens were carried out. corrosion resistance of soldered Th-Th, Th-U, and U-U joints plated with Ni was evaluated by exposure to 100% humid air and subsequent bend tests. (D.L.C.)

• Research Organization: Battelle Memorial Inst., Columbus, Ohio
• DOE Contract Number: W-7405-ENG-92
• NSA Number: NSA-15-032066
• OSTI ID: 4838469
• Report Number(s): BMI-1534(Del.)
• Country of Publication: United States
• Language: English

Related Subjects

AIR
ALLOYS
ALUMINUM OXIDES
BEHAVIOR
BERYLLIUM OXIDES
BURNUP
CADMIUM OXIDES
CALCIUM OXIDES
CARBON
CASTING
CHEMISTRY
COATING
COPPER
CORROSION
CRYSTALS
DENSITY
DEPOSITS
DIFFRACTION
ELECTRIC ARCS
EXPANSION
FABRICATION
FISSION
FLUORIDES
FLUORINE
FRICTION
FUEL ELEMENTS
FUELS
GRAPHITE
HARDNESS
HUMIDITY
HYDROFLUORIC ACID
IRRADIATION
MELTING
NICKEL
NIOBIUM
PLATES
PLATING
PLUTONIUM
POWDERS
PRECIPITATION
PRESSURE
REACTORS
RECOILS
SILICON
SILVER
SILVER CHLORIDES
SODIUM CHLORIDES
STAINLESS STEELS
SURFACES
TEMPERATURE
THORIUM
URANIUM CARBIDES
URANIUM DIOXIDE
URANIUM OXIDES
VACUUM
VOLATILITY
X RADIATION
ZIRCALOY