Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors 1999
DOI: 10.1002/9781118787618.ch30
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Characteristics of Crack Propagation through SCC Under BWR Conditions in Stainless Steels Stabilized with Titanium or Niobium

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“…The cracking of sensitised SS in BWR environment has been found to occur at potentials more oxidizing than a threshold potential (À230 mV SHE at 288°C) [18]. Several kinds of ionic impurities, like sulphate, chloride, carbonate, fluoride, chromate, nitrate and phosphate ions, etc., have also been reported to be able to accelerate the initiation and propagation of intergranular stress corrosion cracks in sensitised type 304 stainless steel and alloy 600 in high-temperature water [19][20][21].…”
Section: Introductionmentioning
confidence: 96%
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“…The cracking of sensitised SS in BWR environment has been found to occur at potentials more oxidizing than a threshold potential (À230 mV SHE at 288°C) [18]. Several kinds of ionic impurities, like sulphate, chloride, carbonate, fluoride, chromate, nitrate and phosphate ions, etc., have also been reported to be able to accelerate the initiation and propagation of intergranular stress corrosion cracks in sensitised type 304 stainless steel and alloy 600 in high-temperature water [19][20][21].…”
Section: Introductionmentioning
confidence: 96%
“…Such type of cracking was also observed in austenitic SS stabilized by titanium or niobium which are inherently more resistant to sensitization. Cracking in the stabilized SS was primarily attributed to the decomposition of the stabilized carbides during processing and the subsequent local sensitization of the material during reactor operation [19,39,40].…”
Section: Introductionmentioning
confidence: 99%
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