Reactor Materials Program electrochemical potential measurements by ORNL with unirradiated and irradiated stainless steel specimens.

摘要

Effect of irradiation of stainless steel on electrochemical potential (ECP) was investigated by measurements in dilute HNO(sub 3) and H(sub 2)O(sub 2) solutions, conditions simulating reactor moderator. The electrodes were made from unirradiated/irradiated, unsensitized/sensitized specimens from R-reactor piping. Results were inconclusive because of budgetary restrictions. The dose rate may have been too small to produce a significant radiolytic effect. Neither the earlier CERT corrosion susceptibility tests nor the present ECP measurements showed a pronounced effect of irradiation on susceptibility of the stainless steel to IGSCC; this is confirmed by the absence in the stainless steel of the SRS reactor tanks (except for the C Reactor tank knuckle area).