Manufacture of Uranium-Niobium Fuel Rods for Irradiation in the Materials Testing Reactor
Description:
Zircaloy-2 clad fuel rods whose fuel was U/sup 238/ -10 wt.% Nb-5 wt.% U/ /sup 235/ were fabricated for testing in the Materials Testing Reactor. The fuel was duplex melted and given a homogenizing heat treatment prior to assembly into extrusion billets. The rods were prepared by co-extruding the fuel alloy in Zircaloy-2 cups, then drawing the rods to size. (auth)
Date:
September 16, 1955
Creator:
Haynes, W. B.
Item Type:
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Partner:
UNT Libraries Government Documents Department