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Corrosion response of nuclear reactor materials to mixtures of decontamination reagents

Journal Article · · Mater. Performance; (United States)
OSTI ID:6050249

An experimental study of the corrosiveness of mixtures of citric acid, oxalic acid, and EDTA to nuclear reactor materials was undertaken. Specimens of type 304 stainless steel (SS), type 410 SS, carbon steel (CS) 1018 and A508, and heat-treated alloy 600 were suspended in recirculating mixtures of two or more combinations of citric acid, oxalic acid, and EDTA at temperatures of 90 C or 117 C for 22 hours. The results suggest that removal of oxalic acid from decontamination solutions should lower the corrosiveness of the solutions to nuclear reactor materials, particularly types 304 SS and 410 SS.

Research Organization:
System Chemistry and Materials Branch, Chalk River Nuclear Labs., Chalk River, Ontario (CA)
OSTI ID:
6050249
Journal Information:
Mater. Performance; (United States), Journal Name: Mater. Performance; (United States) Vol. 28:2; ISSN MTPFB
Country of Publication:
United States
Language:
English

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