Abstract
The key factors affecting crack growth behavior of neutron irradiated stainless steel were investigated in this study. A crack growth rate (CGR) test was conducted under accurate constant K control on a neutron-irradiated 8 mm RCT specimen (9.6 dpa) of high purity 316L stainless steel with Hf addition in simulated BWR (NWC, HWC) and PWR environments at 320°C and 288°C.The effects of water chemistry, electrochemical corrosion potential (ECP), stress intensity factor (K), and temperature on CGR were examined. In addition, the CGR results from this test were integrated with those reported previously in the Cooperative IASCC Research (CIR) program to compared data and determine the effect of the addition of Hf on crack growth rate.
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Ashida, Y., Flick, A., Andresen, P.L., Was, G.S. (2011). The Key Factors Affecting Crack Growth Behavior of Neutron-Irradiated Austenitic Alloys. In: Busby, J.T., Ilevbare, G., Andresen, P.L. (eds) Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors. Springer, Cham. https://doi.org/10.1007/978-3-319-48760-1_76
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DOI: https://doi.org/10.1007/978-3-319-48760-1_76
Publisher Name: Springer, Cham
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