Some Loop Experiments in NRX Reactor to Study The Corrosion of Mild Steel by Flowing Water at 90 deg F
This work was undertaken to find the water conditions necessary for minimum corrosion in the mild steel thermal shield recirculating systems in NRX and NRU. This report contains the chemical and corrosion results obtained by operating three mild steel loops in which water at 85-95 deg F was recirculated through test sections located in J-rod positions in the NRX reactor. Lowest corrosion rates were found when the water was maintained at pH 10.5 with or without oxygen heing present. In both cases the corrosion was general in nature and no pitting occurred. At pH 7 with oxygen present in the water severe pitting took place and the corrosion rate was several times higher than similar conditions without oxygen in the water. Under oxygen-free conditions the corrosion product was Fe{sub 3}0{sub 4}. At pH 7 and with 3-5 ppm of 0{sub 2} in the water the corrosion product was a mixture of Fe{sub 3}0{sub 4} and gamma-Fe{sub 2}0{sub 3}. At high pH with oxygen present Fe{sub 3}0{sub 4} predominated with some traces of Fe{sub 2}0{sub 3}. The systems tested may be listed in order of increasing corrosiveness: High pH with or without 0{sub 2} in the water < water at pH 7 with no 0{sub 2} present and continual purification < water with no 0{sub 2} present and no purification or pH control < water at pH 7 with 3-5 ppm of 0{sub 2} present. (auth)
- Research Organization:
- Atomic Energy of Canada Ltd., Chalk River Project, Ontario (Canada)
- NSA Number:
- NSA-11-001864
- OSTI ID:
- 4362308
- Report Number(s):
- CRDC-645; AECL-360
- Country of Publication:
- Canada
- Language:
- English
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