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Intergranular stress-corrosion cracking of austenitic stainless steels in PWR boric-acid storage systems

Technical Report ·
OSTI ID:5117226
A review is presented of the available literature on the intergranular stress corrosion cracking (IGSCC) of austenitic stainless steels at temperatures below 100/sup 0/C, as well as the results of an experimental investigation of the IGSCC of Types 304, 304L, and 316L stainless steels conducted in boric acid environments of the type employed in pressurized nuclear reactors (PWRs) for nuclear shim control. The susceptibility of furnace sensitized Type 304SS to IGSCC was studied using slow strain rate tests as a function of pH, temperature, potential, and concentration of suspected contaminants: chloride, thiosulfate, and tetrathionate. Possible alternate alloys, such as Types 304L and 316L stainless steels, were also tested under those specific conditions that render Type 304SS susceptible to cracking. Corrosion potentials that can be attained in air-saturated boric acid solutions in the presence of the above mentioned species were measured in order to evaluate the propensity towards intergranular cracking under conditions simulating those that prevail in service.
Research Organization:
Ohio State Univ., Columbus (USA). Dept. of Metallurgical Engineering
OSTI ID:
5117226
Report Number(s):
EPRI-NP-2531; ON: DE82906465
Country of Publication:
United States
Language:
English