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Evaluation of long-term integrity of the fuel assembly removed from the spent fuel pool, 3; Electrochemical test of galvanic specimen with crevice in dilute artificial seawater under $$gamma$$-ray irradiation

Motooka, Takafumi; Ueno, Fumiyoshi

Crevice corrosion of a couple of zirconium and SUS304L were investigated in dilute artificial seawater at ambient temperature under Co-60 $$gamma$$-ray irradiation by electrochemical technique to clarify the occurrence criteria of crevice corrosion. Under simulated an aqueous circumstance in spent fuel pools in Fukushima Daiichi nuclear plant, crevice corrosion potential was greater than spontaneous potential. This result suggests that crevice corrosion little occurs in the dilute chloride solution simulating the spent fuel pool circumstance.

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