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

Technical Report · Thu Jul 01 00:00:00 EDT 1993

DOI:https://doi.org/10.2172/10185742· OSTI ID:10185742

Baumann, E W; Caskey, Jr, G R

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).

• Research Organization: Savannah River Site (SRS), Aiken, SC (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 10185742
• Report Number(s): WSRC-TR-93-321; ON: DE93040726; TRN: 93:021780
• Resource Relation: Other Information: PBD: Jul 1993
• Country of Publication: United States
• Language: English

Related Subjects

37 INORGANIC
ORGANIC
PHYSICAL AND ANALYTICAL CHEMISTRY
36 MATERIALS SCIENCE
22 GENERAL STUDIES OF NUCLEAR REACTORS
STAINLESS STEELS
ELECTROCHEMISTRY
R REACTOR
PIPES
RADIATION EFFECTS
ELECTRIC POTENTIAL
AQUEOUS SOLUTIONS
NITRIC ACID
HYDROGEN PEROXIDE
SAVANNAH RIVER PLANT
PRODUCTION REACTORS
400400
360105
220600
360106
CORROSION AND EROSION
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS