1 Matching Results
Results open in a new window/tab.
Results:
1 - 1 of
1
THE FABRICATION OF THE GRAPHITE-URANIA FUEL FOR THE TRANSIENT REACTOR TEST
The two predominate methods of dispersing uranium in graphite are reviewed and evaluated. This study indicated that the most feasible method of dispersing uranium in graphite would be to fabricate a mixture of graphite and U/ sub 3/O/sub 8/ bonded with a thermosetting resin. A commercial type graphite was developed through independent research, and this fabrication procedure was adapted for the manufacture of the TREAT fuel matrix. (auth)
Date:
February 19, 1959
Creator:
Handwerk, J. H.; McCuaig, F. D. & Bean, C. H.
System:
The UNT Digital Library