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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 November 18, 1957 through January 25, 1958

Technical Report ·
OSTI ID:4298828

The fabrication and evaluation of full-size U-Zr (Zircaloy-2 clad) tubes were continued. A technique was developed for satisfactory bright etching of tubes, but work is still required for precise measurement of the amount of cladding removed in the eteh. Studies on techniques for the diffusion heat treatment were continued. It was established that 7 hrs at 880 C, followed by water quenching of the vacuum chamber in which the tube is contained, was a satisfactory heat treatment schedule. The amount of uranium that diffuses to the surface during this heat treatment is considered negligible, but the amount of creep of the Zircaloy-2 is a major problem. (For preceding period see NMI- 4356.) (W. D. M.)

Research Organization:
Nuclear Metals, Inc., Cambridge, Mass.
NSA Number:
NSA-13-001372
OSTI ID:
4298828
Report Number(s):
NMI-4357
Country of Publication:
United States
Language:
English