POWER REACTOR PROGRAM. Progress Report to E.I. du Pont de Nemours and Company for the Period July 20, 1957 through August 20, 1957
Technical Report
·
OSTI ID:4285026
Tests to determine the effects of Zr content on the corrosion of U-Zr alloys by water were continued. Results are given from studies of dimensional changes in Zircaloy-clad U-2 wt.% Zr extruded tubes resultimg from pickling and horizontal diffusion heat treatment. (For preceding period see NMr-4351.) (D.E.B.)
- Research Organization:
- Nuclear Metals, Inc., Cambridge, Mass.
- NSA Number:
- NSA-13-001369
- OSTI ID:
- 4285026
- Report Number(s):
- NMI-4353
- Country of Publication:
- United States
- Language:
- English
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