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HIGH-TEMPERATURE WATER AND STEAM-CORROSION BEHAVIOR OF ZIRCONIUM-URANIUM ALLOYS

Technical Report ·
DOI:https://doi.org/10.2172/4223835· OSTI ID:4223835
Weight change vs. time curves expressing the corrosion behavior of zirconium alloys containing additions of 10 through 60 wt.% uranium tested in 600 and 680 F water and in 750 F steam at 1500 psi are presented. The effects of various heat treatments on the subsequent corrosion properties are also included. (auth)
Research Organization:
Westinghouse Electric Corp. Bettis Plant, Pittsburgh
DOE Contract Number:
AT(11-1)-GEN-14
NSA Number:
NSA-13-019258
OSTI ID:
4223835
Report Number(s):
WAPD-TM-167
Country of Publication:
United States
Language:
English

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