NUCLEAR FUEL RESEARCH FUEL CYCLE DEVELOPMENT PROGRAM QUARTERLY PROGRESS REPORT, OCTOBER 1 TO DECEMBER 31, 1960
Uranium Oxide Fuel. A laboratory scale process was developed for fabricating UO/sub 2/ pellets by low-temperature sintering in N/sub 2/. The relationship between pellet density and sintering temperature was established. A density of 95% of theoretical was attained at 1200 to 1300 deg C with a minimum initial O/U ratio of 2.25. At least a 1-hr soaking in H/sub 2/ at 1200 to 1300 deg C is required to remove excess O/sub 2/. It was found that approximately 3000 ppm fluoride seriously inhibits sintering and that oxidation-reduction cycling of the contaminated oxide restores the original activity. A two-month corrosion test on sintered UO/sub 2/ pellets in 680 deg F water was completed without any evidence of corrosion. Uranium Carbide. It was found that the C content of methane-produced UC can be reduced from 4.8 to 4.4 wt % by reducing the carburizing temperature from 750 to 650 deg C. Some results are presented using propane as a carburizing medium. The propane-produced UC could be compacted at 35 and 50 tsi with 3 wt % cetyl alcohol as a binder-lubricant. Results are presented for UO/sub 2/-graphite pellets reacted prior to melting and pellets charged directly into the skull furnace without being previously reacted. (D.L.C.)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-15-027076
- OSTI ID:
- 4843891
- Report Number(s):
- NYO-2691
- Country of Publication:
- United States
- Language:
- English
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