POWER REACTOR PROGRAM. Progress Report to E.I. du Pont de Nemours and Company for the Period November 18, 1957 through January 25, 1958
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
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