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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 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