SUMMARY TECHNICAL REPORT FOR THE PERIOD OCTOBER 1, 1957 TO DECEMBER 31, 1957
Evaluations were completed of seven feed materials for the Refinery. The changes in physical properties resulting from degradation of proposed kerosene diluents for the Refinery solvent were studied. Changes in the infrared and ultraviolet spectra of the diluents were examined. Ammonia treatment of uranyl nitrate solution prior to thermal decomposition results in significantly lower iron and nickel levels in the orange oxide but does not increase conversion of sulfated orange oxide to UF/sub 4/. The speed of reduction of orange oxide to UO/sub 2/ is not affected by particle size in the 1 to 100 mu range. The activity of pot-calcined orange oxide was found to vary significantly for successive batches. Significant differences were found in the hydrofluorination rates of UO/sub 2/ derived from two sources. UO/sub 2/ derived from "ammonium diuranate" was hydrofluorinated at high rates and should be amenable to processing with very small excesses of HF in a countercurrent process. A device for continuously detecting the HF concentration of a gaseous HF-H/sub 2/O mixture was fabricated and installed in a Green Salt Plant off-gas line. High-quality green salt (UF/sub 4/) is necessary for good reduction efficiency in the continuous reduction of uranium tetrafluoride to uranium metal with magnesium. Magnesia-alumina spinel shows promise as a refractory material for the reactor. Excellent slag-metal separation and an improved reduction yield were obtained when Domal magnesium was used as the reductant in the production of 13 twelve- inch-diameter uranium derbies. The decontamination factors experienced when UF/ sub 4/ was reduced to derby metal and when derby metal was vacuum melted and cast are reported. Composite vacuum remelt charges, containing pigots produced by salt-melting briquettable cltips, ingot drip crops, reduction scrap, and dingot turnings, were melted. The quality of the ingots obtained was comparable to that of normal production ingots. A chemical method of removing nickel cladding from uranium fuel elements was developed. Substantial savings in direct materials were obtained by recycling a percentage of the clarified acid filtrate. An ID gauge capsble of testing a bore to a depth of 9 inches was developed. Its range at a given setting is plus or minus 0.025 inch, and it is sensitive to a variation of 0.00015 inch. External dimensions of bare fuel elements can be recorded automatically by means of a recording apparatus activated by differential air pressure. Procedures for the spectrographic analysis of twelve impurity elements in magnesium fluoride containing less than one per cent uranium are reported. Heating green salt at elevated temperatures did not adequately improve the stability of the material in the atmosphere. (auth)
- Research Organization:
- National Lead Co. of Ohio, Cincinnati
- DOE Contract Number:
- AT(30-1)-1156
- NSA Number:
- NSA-15-018114
- OSTI ID:
- 4015541
- Report Number(s):
- NLCO-715(Del.)
- Resource Relation:
- Other Information: Decl. with deletions Feb. 3, 1960. Orig. Receipt Date: 31-DEC-61
- Country of Publication:
- United States
- Language:
- English
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