Document Details
Title:
Corrosion evaluation of N reactor pressure tube 1756
Author(s):
Document Location:
OSTI
Document Type:
REPORT
Publication Date:
Declassification Date:
1981 Mar 23
Declassification Status:
Declassified
Document Pages:
50
Accession Number:
BNWL-CC-1401
Originating Research Org.:
Battelle-Northwest, Richland, WA
OpenNet Entry Date:
2022 Jul 27
OpenNet Modified Date:
2022 Jul 26
Description/Abstract:
N Reactor Zircaloy-2 pressure tube No. 1756 and its associated ASTM A234 steel nozzles were examined for corrosion and hydrogen content after approximately 300 days exposure in-reactor. Visual examination showed tight, adherent, dull black oxides in the pressure tube except for scratching in the bottom due to sliding of fuel and fuel spacers through the tube during charge- discharge operations. Several fretted areas up to $sup 3$/$sub 8$ inch wide by $sup 1$/$sub 2$ inch long by up to 13 mils deep were observed at the downstream end--these pits were caused by vibration of the fuel spacers against the pressure tube. Hydrogen levels were fairly constant along the tube length with an average of about 19 +- 6 ppm except at one location. At approximately 30 inches from the front end of the tube a sharp peak to a maximum of 58 ppm hydrogen occurred. The reason for the peak is unknown.