CARBIDE FUEL DEVELOPMENT. Progress Report, January 1, 1962 to March 31, 1962
Reproducibly high density UC-PuC pellets containing minor amounts of (U,Pu)/sub 2/C/sub 3/ were made with nickel sintering aid. Average densities of 95% and maximum densities of 96.6% of theoretical were obtained. High density, singlephase UC-PuC pellets were made by sintering at high temperatures. Densities of 94% of theoretical appear to be attainable. Improved identification of microstructural constituents was made by means of metallography, x-ray diffraction, and microprobe analysis. Development of specialized chemical analysis techniques continued. The post-irradiation examination of the UC specimens was completed. Mass spectrometer analysis showed that 0.4% of the fission gases was released. Metallographic examination of the UC did not reveal any channges in structure. Metallographic examination of the metal specimen parts that were in contact with UC was completed. No evidence for interaction with niobium and slight evidence for interaction with stainless steel was found. The latter was not deleterious. Perturbation factors were calculated for the UC- PuC experiments. Negotiations continued, in order to select the most suitable test reactor. (auth)
- Research Organization:
- United Nuclear Corp. Development Div., White Plains, N.Y.; Carborundum Co., Niagara Falls, N.Y.
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AT(30-1)-2899
- NSA Number:
- NSA-16-027566
- OSTI ID:
- 4800249
- Report Number(s):
- UNC-5013
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-62
- Country of Publication:
- United States
- Language:
- English
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