Abstract
SCC initiation behavior of 15% CF specimens cut from four different alloy 182 weldments was investigated in 360 °C simulated PWR primary water under constant load at the yield stress using direct current potential drop to perform in situ monitoring of SCC initiation time. Within each weldment, one or more specimens underwent SCC initiation within 24 h of reaching full load while some specimens had much longer initiation times, in a few cases exceeding 2500 h. Detailed examinations were conducted on these specimens with a focus on different microstructural features such as preexisting defects, grain orientation and second phases, highlighting an important role of microstructure in crack initiation of alloy 182.
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Acknowledgements
The authors gratefully acknowledge the financial support from U.S. Nuclear Regulatory Commission and Electric Power Research Institute. In addition, support is recognized from the Office of Nuclear Energy, U.S. Department of Energy through the Light Water Reactor Sustainability Program for providing SCC initiation testing systems. Key technical assistance from Robert Seffens, Ryan Bouffioux, Clyde Chamberlin and Anthony Guzman is acknowledged for SCC initiation testing and materials preparation activities.
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Disclaimer: This report was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party’s use, or the results of such use, of any information, apparatus, product, or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights. The views expressed in this paper are not necessarily those of the U.S. Nuclear Regulatory Commission.
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Toloczko, M., Zhai, Z., Bruemmer, S. (2019). SCC Initiation Behavior of Alloy 182 in PWR Primary Water. In: Jackson, J., Paraventi, D., Wright, M. (eds) Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The Minerals, Metals & Materials Series. Springer, Cham. https://doi.org/10.1007/978-3-030-04639-2_9
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DOI: https://doi.org/10.1007/978-3-030-04639-2_9
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