The results of the failure analysis, material characterization and stress corrosion cracking (SCC) tests of cold bent, seamless austenitic stainless steel pipes removed from scram system 354 of Ringhals 1 BWR plant after 11 years operating time at 240 °C are presented. The material characterization and also the stress corrosion cracking susceptibility study of the cold bent pipes were performed for materials taken from different depths of the pipe wall thickness. Stress corrosion tests were carried out in simulated BWR water environments at 288°C with varying oxygen contents. The results indicated that highly cold worked material is susceptible to IGSCC without any marked sensitization under constant loading, while dynamic loading results in TGSCC.
|Title of host publication||Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems|
|Subtitle of host publication||Water Reactors|
|Editors||Robert E. Gold, Edward P. Simonen|
|Place of Publication||Warrendale|
|Publisher||Minerals, Metals and Materials Society, TMS|
|Publication status||Published - 1993|
|MoE publication type||A4 Article in a conference publication|
|Event||6th International symposium on Environmental Degradation in Nuclear Power Systems - San Diego, United States|
Duration: 1 Aug 1993 → 5 Aug 1993
|Conference||6th International symposium on Environmental Degradation in Nuclear Power Systems|
|Period||1/08/93 → 5/08/93|
Tähtinen, S., Hänninen, H., & Trolle, M. (1993). Stress corrosion cracking of cold worked austenitic stainless steel pipes in BWR reactor water. In R. E. Gold, & E. P. Simonen (Eds.), Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors (pp. 265-275). Minerals, Metals and Materials Society, TMS.