CARBIDE FUEL DEVELOPMENT. Progress Report, September 15, 1961 to December 31, 1961
Single phase, solid solution, UC-PuC powder was synthesized reproducibly from a mixture of the oxides and carbon. A simple method of monitoring the reaction was developed. UC-PuC-0.1 wt% Ni pellets of 93% theoretical density were made reproducibly, with some samples as high as 95% of theoretical denstty. The pellets contain minor amounts of (U,Pu)/sub 2/C/sub 3/ most of the time. Efforts to make reproducible 95%, single-phase material are under way. Microprobe analysis of UC-0.1 wt% Ni specimens was completed. A second phase apparently promoted by the nickel was shown to be probably U/sub 2/C/sub 3/. Essentially all the nickel was found in solution in the matrix UC. The postirradiation examination of the UC specimens completed to date showed that the UC pellets had the same appearance after irradiation as before irradiation. Their dimensional changes were very slight (1.4% volume increase). Fission gas release was low and within the sensitivity of the initial measurement (3.5% max). The average specimen burnup was 18,500 MW-d/tonne at an average maximum fuel temperature of 760 deg C (1400 deg F). The plutonium facilities continued satisfactory operation at zero contamination level. (auth)
- Research Organization:
- United Nuclear Corp. Development Div., White Plains, N.Y.; Carborundum Co., Niagara Falls, N.Y.
- Sponsoring Organization:
- USDOE
- NSA Number:
- NSA-16-027565
- OSTI ID:
- 4816515
- Report Number(s):
- UNC-5003
- Country of Publication:
- United States
- Language:
- English
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