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U.S. Department of Energy
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HYDROGEN PICKUP OF ZIRCALOY-2 AND ZIRCALOY-4 IN STATIC VS REFRESHED AUTOCLAVING SYSTEMS. Interim Report

Technical Report ·
OSTI ID:4083399

The amount of corrosion product hydrogen pickup in 400 deg C, 1500 psi steam for Zircaloy-2 and Zircaloy-4 is higher in a static autoclave than in a refreshed autoclave system by a factor of approximately two. The hydrogen pickup averaged 26% in the static system as compared to 13% in the refreshed system. The data presented appear to show either that the zirconium alloys tested are sensitive to hydrogen overpressures existing in static autoclave systems or that the higher oxygen concentration in the refreshed system is affecting the mechanism of hydrogen pickup. The corrosion rates of Zircaloy-2 and Zircaloy-4 in 400 deg C, 1500 psi steam were very similar. However, two of the four lots of Zircaloy-4 show premature breakaway, probably due to poor-quality material. One lot of Zircaloy-2 showed normal corrosion weight gains in the static system, but a premature breakaway in the refreshed. An acceptable explanation for this has not yet been found. There are several implications of the data. First, hydrogen pickup of Zircaloy during testing of reactor components can be reduced by operating in a refreshed autoclave. Second, since it was shown environmental conditions had an effect on hydrogen pickup, it may be possible to control H/sub 2/ pickup in reactor systems by environment control. (auth)

Research Organization:
General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
DOE Contract Number:
AT(45-1)-1350
NSA Number:
NSA-18-010471
OSTI ID:
4083399
Report Number(s):
HW-67437
Country of Publication:
United States
Language:
English