PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING OCTOBER 1958
Thermal-conductivity and electrical-resistivity measurements were made on U-1.5 wt,% Zr, encapsulated in Zircaloy-2 with a NaK thermal bond. Data are presented on thermal conductivity measurements made on UO/sub2/ specimens. A method of sink-float measurement to identify factors affecting irradiation- induced volume changes in graphite was continued. The stress-rupture and creep properties of 15% cold-worked Zircaloy-2 are being investigated in the 290 to 400 deg C temperature range in vacuum. High-purity single crystals of Mo are being prepared for irradiation-damage studies. A feasibility study of the neutron- activation method for the elemental analysis of portland cement was completed and preliminary experiments were initiated. The chemical analyses of irradiated and nonirradiated cetane, stearic acid, and the corresponding urea complexes were continued. A study of the mechanisms by which U solidifies in a cylindrical mold is being made. Coatings of Mo compounds on Croloy 2 1/4 were studied as potential protective coatings against liquid Bi. Work on the study of valence effects of oxide additions to UO/sub 2/ indicates that additions of Y/sub 6/O/sub 3/ are better stabilizers than La/sub 2/O/sub 3/ in 3000 deg F air. Measurements of hydrogen-absorption isotherms for the Zr-25 wt.% U alloy were made. An investigation was made of the effect of irradiation damage on the mechanical properties of type 347 stainless steel. Niobium uranium alloys containing 20 to 70 wt.% U were prepared in small heats. A program aimed at improving the irradiation stability and corrosion resistance of Th-U alloys is being conducted. Fatigue studies of Inconel and INOR-8 are presented. A study of the kinetics and mechanism of the reaction of N/sub 2/ with Nb is presented. A study of the U-Nb constitutional diagram is being performed. Data are reported on the fabrication of fueled graphite spheres. Materials of construction for use in the various proposed processes for the recovery of spent reactor fuel elements are being evaluated. Titanium is being investigated for the Darex Process dissolver, Carpenter 20Cb, Ni-o-nel, and Illium 98 for Thorex and Sulfex solutions, and INOR- 1 and INOR8 for the fluoride-volatility processes. Properties of UC are being determined. The preparation of an initial series of Ta and Ta-W alloys for Pu- alloy compatibility evaluation is in progress. A study to determine the effect of neutron irradiation on the mechanical properties of Ta is reported. (For preceding period see BMI-1294.) (W.L.H.)
- Research Organization:
- Battelle Memorial Inst., Columbus, OH (United States)
- Sponsoring Organization:
- Sponsor not identified
- DOE Contract Number:
- W-7405-ENG-92
- NSA Number:
- NSA-13-015343
- OSTI ID:
- 4852092
- Report Number(s):
- BMI-1301
- Resource Relation:
- Other Information: Decl. June 12, 1959
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BONDING
CAPSULES
ELECTRIC CONDUCTIVITY
FUEL CANS- - INTERMETALLIC COMPOUNDS
MEASURED VALUES
POTASSIUM ALLOYS
SODIUM ALLOYS
THERMAL CONDUCTIVITY
URANIUM ALLOYS
URANIUM DIOXIDE
ZIRCALOY
ZIRCONIUM ALLOYS
COLD WORKING
CREEP
FAILURES
FUEL CANS
INTERMETALLIC COMPOUNDS
STRESSES
TEMPERATURE
VACUUM
IMPURITIES
MEASURED VALUES- - MOLYBDENUM
MONOCRYSTALS
PREPARATION
RADIATION EFFECTS
ACTIVATION ANALYSIS
CEMENTS
NEUTRON BEAMS
ALKANES
IRRADIATION
ORGANIC ACIDS
QUALITATIVE ANALYSIS
UREA
CYLINDERS
SOLIDIFICATION
URANIUM
BISMUTH
COATING
CORROSION PROTECTION
CROLOY
LIQUID METALS
MOLYBDENUM COMPOUNDS
STAINLESS STEELS
AIR
HIGH TEMPERATURE
LANTHANUM OXIDES
STABILITY
YTTRIUM OXIDES
ADSORPTION
HYDROGEN
MECHANICAL PROPERTIES
NIOBIUM ALLOYS
CORROSION
THORIUM ALLOYS
ALUMINUM ALLOYS
CHROMIUM ALLOYS
FATIGUE
INCONEL ALLOYS
INOR-8
MOLYBDENUM ALLOYS
NICKEL ALLOYS
TITANIUM ALLOYS
CHEMICAL REACTIONS
NIOBIUM
NITROGEN
REACTION KINETICS
PHASE DIAGRAMS
FABRICATION
FUELS
GRAPHITE
SPHERES
QUANTITATIVE ANALYSIS
TENSILE PROPERTIES
URANIUM CARBIDES
PLUTONIUM ALLOYS
TANTALUM
TANTALUM ALLOYS
TUNGSTEN ALLOYS