CARBIDE FUEL DEVELOPMENT. Progress Report, May 1, 1960 to July 31, 1960
Fabrication studies of natural UC were completed. Higher sintering tempenatures or changes in binder nu-xtures did not improve densities. Fabrication of enriched UC for the irradiation tests was completed. An average density of 12.8 g/cc ( 94% of theoretical) was obtained, with some as high as 13.1 g/cc ( 96% of theoretical). The UC-cladding compatibility tests were completed. The longest tssts were 4000 hr at 820 ts C. Visible reactions occurred between UC and Zircaloy-2, beryllium, Inconel-x, and 2.5 Cr--1 Mo alloy. The plutonium facility is complete and leaktight with all the equipment installed. (For preceding period see NDA-2145-4.) (W.L.H.)
- Research Organization:
- Nuclear Development Corp. of America, White Plains, N.Y.; Carbonundum Co., Niagara Falls, N.Y.
- NSA Number:
- NSA-15-009333
- OSTI ID:
- 4098453
- Report Number(s):
- NDA-2145-5
- Country of Publication:
- United States
- Language:
- English
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