INTERGRANULAR STRESS CORROSION CRACKING OF AUSTENITIC STAINLESS STEELS IN PWR BORIC ACID STORAGE SYSTEMS.

D. D. Macdonald*, G. A. Cragnolino, J. Olemacher, T. Y. Chen, S. Dhawale

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

1 Scopus citations

Abstract

A review is presented of the available literature on the intergranular stress corrosion cracking (IGSCC) of austenitic stainless steels at temperatures below 100 degree 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.

Original languageEnglish
Pages (from-to)var paging
JournalElectric Power Research Institute (Report) EPRI NP
StatePublished - 1982

ASJC Scopus subject areas

  • Electrical and Electronic Engineering

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