Development and application of the SCC parameter to predicting SCC in the secondary side of steam generators

Zhi Fang, Roger W. Staehle

Research output: Chapter in Book/Report/Conference proceedingConference contribution

3 Scopus citations

Abstract

Hideout return data from steam generators shows that environments in secondary side crevices tend to have values of pH in the mid-range and specifically neither in the alkaline or acidic ranges where SCC has been extensively studied. Alloys 600 and 690 have exhibited SCC in this range of pH in laboratory tests. Specific environments in which such SCC has been observed that is relevant to the mid-range of pH have contained species that include lead, copper, chloride, reduced sulfur and combinations of boric acid and sodium hydroxide. These environments can be investigated for their influence on possible SCC using an SCC parameter. The SCC parameter is derived from comparing fast and slow polarization scans. The result from this comparison produces a parameter called the SCC parameter, PSCC, which can be determined as a function of potential. Using conventional polarization measurements, SCC has been predicted in environments containing sulfur of valence from -2 to +6 and chloride in the mid-range of pH for alloys 600, 690 and 800 at 95°C. The effects of sulfur and chloride species on the breakdown potentials and the passive current densities are described. The preliminary SCC tests have been conducted at the potentials where SCC was predicted.

Original languageEnglish (US)
Title of host publicationProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -
EditorsS. Bruemmer, P. Ford, G. Was
PublisherMinerals, Metals and Materials Society
Pages689-694
Number of pages6
ISBN (Print)0873394755, 9780873394758
DOIs
StatePublished - Jan 1 1999
EventProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors - - New Portbeach, CA, United States
Duration: Aug 1 1999Aug 5 1999

Publication series

NameProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -

Other

OtherProceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors -
CountryUnited States
CityNew Portbeach, CA
Period8/1/998/5/99

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