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U.S. Department of Energy
Office of Scientific and Technical Information

POWER REACTOR PROGRAM. Progress Report to E.I. du Pont de Nemours and Company for the Period April 1, 1960 through April 30, 1960

Technical Report ·
OSTI ID:4158586

Foliowing the extrusion of two tubes having different experimental end shapes, three prototype outer tubes (designated as 74, 75, and 76) of the new thin-walled design were produced. Tube 74 is being processed for flow testing at Savannah River. Tube 75 will be evaluated as an irradiation candidate after it is heat treated. Tube 76, which has a shorter core, will be autoradiographed and destructively examined. A development program was initiated to obtain basic data for assistance in the design of billets for coextrusion. During the preparation of two thin-walled prototype VBWR tubes, one with an as-cast U-1.5 wt.% Mo core and the other with an epsilonized U-1 wt.% Si core, the casting operation was investigated to evolve an economical process. Additional tensile. creep, and stress-rupture data were obtained on unalloyed U and on U-1.5 wt.% Mo alloy to provide data for comparison with irradiation behavior. The study of the effects of processing variables on ductility has essentially been completed. The investigation to reduce the cost of the procedure for etching zircaloy was completed. (For preceding period see NMI-7226.) (W.L.H.)

Research Organization:
Nuclear Metals, Inc., Concord, Mass.
NSA Number:
NSA-14-023267
OSTI ID:
4158586
Report Number(s):
NMI-7227
Country of Publication:
United States
Language:
English