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Interim assessment of N-Reactor Zircaloy-2 pressure tube corrosion and hydriding

Technical Report ·
OSTI ID:6237083

Nine N-Reactor Zircaloy-2 tubes have been removed from service for examination. The analysis of corrosion and hydriding results for seven tubes with exposures ranging from 356 to 3203 effective full power days is presented in this report. Those N-Reactor operating characteristics that are important to tube corrosion and hydriding analysis, in particular, temperature, neutron flux, and water chemistry data, are also presented. The tube corrosion and hydriding results are referenced to data from studies of N-Reactor tube specimens that were exposed in the Engineering Test Reactor (ETR) G-7 loop. The oxides also are relatively thin on tube OD surfaces (<10 ..mu..m), even at high-flux locations. However, thick oxide layers form on tube ID surfaces that are in contact with the reactor coolant, generally following the flux profile. The flux-enhanced corrosion was modeled, accounting for thermal and radiation effects.

Research Organization:
Pacific Northwest Lab., Richland, WA (USA); UNC Nuclear Industries, Inc., Richland, WA (USA)
DOE Contract Number:
AC06-76RL01857
OSTI ID:
6237083
Report Number(s):
UNI-3107; PNL-5311; ON: DE87008415
Country of Publication:
United States
Language:
English

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