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U.S. Department of Energy
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GRAPHITE FUEL STUDIES. PART 2. FINE GRINDING OF ARTIFICIAL GRAPHITE

Technical Report ·
OSTI ID:4199306
Homogeneous dispersions of fissile and fertile material in graphite are being currently considered as fuel for hightemperature, gas-cooled nuclear reactors. A possible method of fuel preparation involves compartion of finely ground artificial graphite with U and Th metal powders. Size reduction of antificial graphite is therefore of interest in the preparation of graphite-fuel compacts. Reactor graphite was successively size reduced in a jaw crusher, pin disk mill and ball mill to give a material 50% finer than a microns, and with a B.E.T. nitrogen adsorption surface area ranging up to 18.4 m/sup 2//g. The variables in ball milling were studied, and in particular it was found that Ni- hard balls gave a faster grinding rate, but a higher contamination than was obtained with steel balls. Leaching with boiling HCI was effective in removing contamination introduced by these grinding media. The Rosin-Rammler function, R = 100e/sup -/ (x/x-bar)/sup n/ applied to the size distributions of the ground graphite. In the size range 70 to 1000 microns, the distribution constant n equalled 1. However, above and below this size range, the distribution constant approximated 2. This high value of n for the sub-sieve range was not previously reported, but is not peculiar to artificial graphite. Other materials were found to have a similar value of n. (auth)
Research Organization:
Australia. Atomic Energy Commission Research Establishment, Lucas Heights, New South Wales
NSA Number:
NSA-14-005558
OSTI ID:
4199306
Report Number(s):
AAEC/E-41
Country of Publication:
Country unknown/Code not available
Language:
English