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High temperature oxidation behavior of Zr-1Nb cladding alloy E110.

Journal Article · · J. Nucl. Mater.

Oxidation experiments were conducted at 1000-1200 C in flowing steam with samples of as-received Zr-1Nb alloy E110 tubing and/or polished E110 tubing. The purpose was to determine the oxidation behavior of this alloy under postulated loss-of-coolant accident conditions in light water reactors. The as-received E110 tubing exhibited a high degree of susceptibility to nodular oxidation and breakaway oxidation at relatively low test times, as compared to other cladding alloys. The nodules grew much more rapidly at 1000 C than 1100 C, as did the associated hydrogen uptake. The oxidation behavior was strongly affected by the surface condition of the materials. Polishing to {approx}0.1 {micro}m roughness (the roughness of the as-received tubing was {approx}0.4 {micro}m) delayed breakaway oxidation. Polishing also removed surface impurities. For polished samples oxidized at 1100 C, no significant nodular oxidation appeared up to 1000 s. For polished samples oxidized at 1000 C, hydrogen uptake >100 wppm was delayed from {approx}300 s to >900 s. Weight-gain coefficients were determined for pre-breakaway oxidation of polished-only and machined-and-polished E110 tubing samples: 0.162 (mg/cm{sup 2})/s{sup 0.5} at 1000 C and 0.613 (mg/cm{sup 2})/s{sup 0.5} at 1100 C.

Research Organization:
Argonne National Laboratory (ANL)
Sponsoring Organization:
NRC
DOE Contract Number:
AC02-06CH11357
OSTI ID:
967941
Report Number(s):
ANL/NE/JA-63251
Journal Information:
J. Nucl. Mater., Journal Name: J. Nucl. Mater. Journal Issue: 3 ; Sep. 15, 2009 Vol. 393; ISSN 0022-3115; ISSN JNUMAM
Country of Publication:
United States
Language:
ENGLISH

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